ML19289G327
| ML19289G327 | |
| Person / Time | |
|---|---|
| Site: | La Crosse File:Dairyland Power Cooperative icon.png |
| Issue date: | 08/14/1979 |
| From: | DAIRYLAND POWER COOPERATIVE |
| To: | |
| Shared Package | |
| ML19253A417 | List: |
| References | |
| NUDOCS 7908270421 | |
| Download: ML19289G327 (50) | |
Text
8 e
ENCLOSURE 1 PROPOSED CHANGES TO TECHNICAL SPECIFICATIONS 2082 294
~l 9 @770%>l
1.0 DEFINITIONS CHANNEL CALIBRATION 1.4 A CHANNEL CALIBRATION shall be the adjustment, t-necessary, of the channel output such that it responds with the necessary range and accuracy to known values of the parameter which the channel monitors.
The CHANNEL CALIBRATION shall encompass the entire channel including the sensor and alarm and/or trip functions, and shall include the CHANNEL FUNCTIONAL TEST.
The CHANNEL CALIBRATION may be performed by any series of sequential, aver-lapping or total channel steos such that the entire channel is calibrated.
CHANNEL CHECK 1.5 A CHANNEL CHECK shall be the qualitative assessment of channel be-havior during operation by observation.
This determination shall include, where possible, comparison of the channel indication and/or status with other indications and/or status derived from independent instrumentation channels measuring the same parameter.
CHANNEL FUNCTIONAL TEST 1.6 A CHANNEL FUNCTIONAL TEST shall be:
a.
Analog channels - the injection of a simulated signal into the channel as close to the sensor as practicable to verify OPERABILITY including alarm and/or trip functions.
b.
Bistable channels - the injection of a simulated signal into the sensor to verify OPERABILITY including alann and/or trip functions.
SOURCE CHECK 1.29 A SOURCE CHECK shall be the qualitative assessment of channel response when the channel sensor is exposed to a radioactive source.
OFFSITE DOSE CALCULATION MANUAL (0DCM) 1.30 An 0FFSITE DOSE CALCULATION MANUAL (0DCM) shall be a manual contain-ing the methodology and parameters to be used in the calculation of offsite doses due to radioactive gaseous and liquid effluents and in the calcula-tion of gaseous and liquid effluent monitoring instrumentation alarm / trip setpoints.
Requirements of the ODCM are provided in Specification 6.15.
LACBWR l-1
1.0 DEFINITIONS - (Cont'd)
GASEOUS RADWASTE TREATMENT SYSTEM 1.31 A GASE0US RADWASTE TREATMENT SYSTEM is any system designed and installed to reduce radioactive gaseous effluents by collecting primary coolant system offgases from the primary system and providing for delay or holdup for the purpose of reducing the total radioactivity prior to release to the environment.
VENTILATION EXHAUST TREATMENT SYSTEM 1.32 A VENTILATION EXHAUST TREATMENT SYSTEM is any system designed and installed to reduce gaseous radiciodine or radioactisa material in parti-culate form in effluents by passing ventilation or vent exhaust gases through charcoal absorbers and/or HEPA filters for the purpose of removing iodines or particulates from the gaseous exhaust stream prior to the release to the environment.
Such a system is not considered to have any effect on noble gas effluents.
Engineered Safety Feature (ESF) atmospheric cleanup systems are not considered to be VENTILATION EXHAUST TREATMENT SYSTEM components.
2082 296 LACBWR l-2
TABLE 1.2 FREQUENCY NOTATION NOTATION FREQUENCY S
At least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
D At least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
W At least once per 7 days.
M At least once per 31 days.
Q At least once per 92 days.
SA At least once per 184 days.
R At least once per 18 months.
S/U Prior to each reactor startup.
P Completed Prior to each release.
N.A.
Not applicable.
2082 297 LACBWR l-3
INSTRUMENTATION RADI0 ACTIVE LIQUID EFFLUENT INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.3.8 The radioactive liquid effluent monitoring instrumentation channels shown in Table 3.3-11 shall be OPERABLE with their alarm / trip setpoints within the specified limits to ensure that the limits of Specification 3.11.1.1 are not exceeded.
APPLICABILITY: As shown in Table 3.3-11.
ACTION:
a.
With a radioactive liquid effluent monitoring instrumentation channel alarm / trip setpoint less conservative than the value shown in Table 3.3-11 which ensures that the limits of 3.11.1.1 are met, immediately suspend the release of radioactive liquid effluents monitored by the affected channel or declare the channel inoperable.
b.
With one or moreof the above required radioactive liquid effluent monitoring instrumentation channels inoperable, take the ACTION required by Table 3.3-11.
c.
The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.
SURVEILLANCE REQUIREMENTS 4.3.3.8.1 The setpoints shall be determined in accordance with procedures as described in the ODCM and shall be recorded on the Liquid Waste Batch Form L-81.
4.3.3.8.2 Each radioactive liquid effluent monitoring instrumentation channel shall be demonstrated OPERABLE by performance of the CHANNEL CHECK, SOURCE CHECK, CHANNEL FUNCTIONAL TEST, and CHANNEL CALIBRATION operations during the conditions and at the frequencies shown in Table 4.3-11.
4.3.3.8.3 Records - Auditable records shall be maintained, in accordance with procedures in the ODCM, of all radioactive liquid effluent monitoring instrumentation alarm / trip setpoints. Setpoints and setpoint calculations shall be available for review to ensure that the limits required by Specification 3.11.1.1 are met.
2082 298 LACBWR 3/4 3-44
TABLE 3.3-11 RADI0 ACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION
=c" MINIMUM CHANNELS APPLICABLE ALARM / TRIP INSTRUMENT OPERABLE CONDITIONS SETPOINT ACTION 1.
Gross Radioactivity Monitors Not Providing Automatic Termination of Release a.
Liquid Radwaste Effluent Line 1
At All Times 0CDM #
51 b.
Service Water System Effluent Line 1
At All Times 0CDM #
52 2
2.
Flow Rate Measurement Devices a.
Liquid Radwaste Effluent Line 1
At All Times NONE 53 cD C73 N
NwW
TABLE 3.3-11 (Cont'd)
TABLE NOTATION ACTION 51 With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirements, effluent releases may be resumed for up to 14 days, provided that prior to initiating a release:
l.
At least two independent samples are analyzed in accordance with Specification 4.11.1.1.3, and; 2.
At least two technically qualified members of the Facility Staff independently verify the release rate calculations and discharge valving; Otherwise, suspend release of radioactive effluents via this pathway.
ACTION 52 With the numbers of channels OPERABLE less than reauired by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue for up to 14 days provided that at least oncer per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> grab samples are collected and analyzed for gross radioactivity (beta or gamma) at a lower limit of detection of at least 10-7 pCi/ml.
ACTION 53 With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue for up to 14 days provided the flow rate is estimated at least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> during the actual releases.
2082 300
~
LACBWR 3/4 3-46
TABLE 4.3-11 E
g; RADI0 ACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS
!5 CHANNEL CHANNEL SOURCE FUN CTIONAL CHANNEL INSTRUMENT CHECK CHECK TEST CALIBRATION 1.
Gross Beta or Gamma Radioactivity Monitors Providing Alarm But Not Providing Automatic Isolation a.
Liquid Radwaste Effluent Line D,P(2)
M Q(1)
R(4) b.
Turbine Condenser Cooling Water Line D
M Q(1)
R(4) w2 2.
Flow Rate Measurement Devices a.
Liquid Radwaste Effluent Line D(3)
N.A.
Q R
N O
CD N
tr4 O
TABLE 4.3-11 (Cont'd)
TABLE NOTATION (1) The CHANNEL FUNCTIONAL TEST shall also demonstrate that control room alarm annunciation occurs if any of the following conditions exist:
1.
Instrument indicates measured levels above the alarm / trip setpoint.
2.
Circuit failure.
3.
Instrument indicates a downscale failure.
(2) A CHANNEL CHECK of residual radioactivity shall be perfonned within one hour of beginning of release.
(3) CHANNEL CHECK shall consist of verifying indication of flow during periods of release.
CHANNEL CHECK shall be made at least once daily on any day or. which continuous, periodic, or batch releases are made.
(4) The CHANNEL CALIBRATION shaii include the use of a known liquid radioactive source positioned in a reproducible geometry with respect to the sensor and emitting beta and gamma radiation with the fluences and energies in the ranges measured by the channel during normal operation.
20~82 302 LACBWR 3/4 3-48
INSTRUMENTATION RADI0 ACTIVE GASEOUS EFFLUENT INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.3.9 The radioactive gaseous process and effluent monitoring instru-mentation channels shown in Table 3.3-12 shall be OPERABLE with their alarm / trip setpoints within the specified limits to ensure that the limits of Specification 3.11.2.1 are not exceeded.
APPLICABILITY: As shown in Table 3.3-12.
ACTION:
a.
With a radioactive gaseous process or effluent monitorin-instrumentation channel alarm / trip setpoint less conservative than the value shown in Table 3.3-12 which ensures that the limits of 3.11.2.1 are met, declare the channel inoperable.
b.
With one or more radioactive gaseous process or effioant monitoring instrumentation channels inoperable, take the ACTION required by Table 3.3-12.
c.
The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.
SURVEILLANCE REQUIREMENTS 4.3.3.9.1 The setpoints shall be determined in accordance with procedures as described in the ODCM and shall be recorded in the calibration records.
4.3.3.9.2 Each radioactive gaseous process or effluent monitoring instru-mentation channel shall be demonstrated OPERABLE by performance of the CHANNEL CHECK, SOURCE CHECK, CHANNEL FUNCTIONAL TEST, and CHANNEL CALI-BRATION operations during the conditions and at the frequencies shown in Table 4.3-12.
4.3.3.9.3 Auditable records shall be maintained of the calculations made, in accordance with procedures in the OCDM, of all radioactive process and effluent monitoring instrumentation alarm / trip setpoints.
Setpoints and setpoint calculations shall be available for review to ensure that the limits required by Specification 3.11.2.1 are met.
7082 303 LACBWR 3/4 3-49
9 TABLE 3.3-12 9
is RADI0 ACTIVE GASE0US EFFLUENT MONITORING INSTRUMENTATION MINIMUM CHANNELS APPLICABLE INSTRUMENT OPERABLE CONDITIONS ALARM / TRIP SETPOINT ACTION 1.
Main Condenser Offgas System Monitoring System (10-Minute Holdup Tank Effluent) a.
Noble Gas Activity Monitor 1
ODCM #
58 b.
System Flow Rate Measuring Device 1
NONE 54 u,
s
[l 2.
Offgas Treatment System 3,
Explosive Gas Monitoring System c)
< 4% Hydrogen By Volume 56 a.
Hydrogen Monitor 1
3.
Reactor Containment Building Ventilation Monitor System a.
Gaseous Activity Monitor 1
ODCM #
55 b.
Particulate Activity Monitor 1
ODCM #
55 c.
Sampler Flow Rate Measurement Device 1
ODCM #
54 Ncp C73 N
w CD E:> '
5; TABLE 3.3 (Cont'd)
RADI0 ACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION MINIMUM CHANNELS APPLICABLE INSTRUMENT OPERABLE CONDITIONS ALARM / TRIP SETPOINT ACTION 4.
Offgas Storage Vault Discharge Monitor (After Treatment System) a.
Noble Gas Activity ODCM #
55 Monitor 1
b.
System Flow Rate Measuring Device 1
NONE 54 u,
1 5.
Stack Monitoring System u,
2n a.
Gaseous Activity Moni tor 1
ODCM #
55 b.
Particulate Activity Monitor 1
ODCM #
55 c.
Iodine Sampler NONE, Verify Presence of Car-57 Cartridge 1
tridge and System Operation d.
Particulate Sampler NONE, Verify Presence of Fil-57 Filter 1
ter and System Operation e.
Sampler Flow Rate ODCM #
54 P')
Measuring Device 1
o c:o rs) u O
LJ1
TABLE 3.3-12 (Cont'd)
TABLE NOTATION
- During releases via this pathway.
- During offgas treatment system operation.
ACTION 58 With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, gases from the main condenser offgas system may be released to the environment provided:
1.
The offgas delay system is not bypassed; and 2.
The offgas delay system noble gas activity monitor is OPERABLE; Otherwise, be in at least HOT STANDBY within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.
ACTION 54 With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue for up to 28 days provided the flow rate is estimated at least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.
ACTION 55 With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue for up to 28 days provided grab samples are taken at least ont per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> and these samples are analyzed for gross activity within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
ACTION 56 With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, operation of the offgas treatment system may continue for up to 28 days provided recombiner temperatures are monitored hourly and indicate recombination is satisfactory.
ACTION 57 With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue for up o 28 days, provided samples are continuously collected with auxiliary sampling equipment for periods on the order of seven (7) days and analyzed within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> af ter the end of the sampling period.
2.082 306 LACBWR 3/4 3-52
TABLE 4.3-12 l
RADI0 ACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS CHANNEL SURVEILLANCE CHANNEL SOURCE FUNCTIONAL CHANNEL REQUIREMENT INSTRUMENT CHECK CHECK
_ TEST CALIBRATION CONDITIONS 1.
Main Condenser Offgas System Monitoring System (10-Minute Holdup Tank Effluent) a.
Noble Gas Activity Monitor D
M Q(1)
R(3) b.
System Flow Rate Measuring Devica D
N.A.
Q(7)
R 2.
Offgas Treatment System Explosive Gas Monitoring System u,
O a.
Hydrogen Monitor D
N.A.
M Q(4) 3.
Reactor Containment Building Ventilation Monitoring System a.
Gaseous Activity Monitor D
M Q(1)
R(3) or (5) b.
Particulate Activity Monitor
-D,[
M Q(1)
R(5) c.
Sampler Flow Rate Measuring Device D
N.A.
Q(7)
R N
CD CI)
N u
C)
N r
f
~-
)
g TABLE 4.3 (Cont'd)
RADI0 ACTIVE GASE0US EFFLUENT MONITORING TNSTRUMENTATION SURVEILLANCE REQUIREMENTS CHANNEL SURVEILLANCE
,s
~'
~
CHANNEL SOURCE FUNCTIONAL CHANNEL REQUIREMENT INSTRUMENT CHECK CHECK TEST CALIBRATION CONDITIONS 4.
Offgas Storage Vault Discharge Monitor (After Treatment System) i a.
Noble Gas Activity Monitor D
M Q(6)
R(3) b.
Systen Flow Rate Measuring Device D
N.A.
N.A.
R 5.
Stack Monitoring System m
s'[
a.
Gaseous Activity Monitor D
M Q(2)
R(3) or (5) b.
Particulate Activity Monitor D
M Q(2)
R(5) c.
Iodine Sampler Cartridge D
N.A.
N.A.
N.A.
d.
Particulate Sampler Filter D'
N.A.
N.A.
N.A.
e.
Sampler Flor Rate Measuring Device D
N.A.
Q(7)
R N
O CD N
u O
CD a
TABLE 4.3-12 (Cont'd)
TABLE NOTATION
- During releases via this pathway.
- During offgas treatment system recombiner operation.
(1) The CHANNEL FUNCTIONAL TEST shall also demonstrate that automatic isolation of this pathway and control room alarm annunciation occurs if any of the following conditions exist:
1.
Instrument indicates measured levels above the alarm / trip setpoint.
2.
Circuit failure (provides con t rol room annunciation alarm only).
3.
Instrument indicates a downscale failure (provides control room annunciation alarm only).
(2) The CHANNEL FUNCTIONAL TEST shall also demonstrate that control room alarm annunciation occurs if any of the following conditions exist:
1.
Instrument indicates measured levels above the alarm / trip setpoint.
2.
Circuit failure.
3.
Instrument indicates a downscale failure.
(3) The CHANNEL CALIBRATION for radioactivity measurement instrumen-tation shall be performed by analyzing the gaseous radioactive stream for specific activity.
(4) The CHANNEL CALIBRATION shall include the use of standard g s samples containing a ne inal:
1.
One volume percent hydrogen, balance nitrogen; and 2.
Four volume percent hydrogen, balance nitrogen.
LACBWR 3/4 3-55 2082 309
TABLE 4.3-12 (Cont'd)
TABLE NOTATION (5) The CHANNEL CALIBRATION shall include the use of a known radio-active source positioned in a reproducible geometry with respect to the sensor and emitting beta and ganma radiation with the fluences and energies in the ranges measured by the channel during nomal operation.
(6) The CHANNEL FUNCTIONAL TEST shall demonstrate that the contro?
room local alarm occurs if the instrument indicates neasured levels above the alarm / trip setpoint.
(7) The CHANNEL FUNCTION TEST shall demonstrate that the control room local alarm occurs if the flow instrument indicates measured levels below the minimum and/or above the maximum alarm / trip setpoint.
2082 310 3/4 3-56 LACBWR
I 3/4.11 RADI0 ACTIVE EFFLUENTS 3/4.11.1 LIQUID EFFLUENTS CONCENTRATION LIMITING CONDITION FOR OPERATION 3.11.1.1 The concentration of radioactive material released at any time from the site to unrestricted areas (see Figure 3.11-1) shall be limited to the concentrations specified in 10 CFR Part 20, Appendix B, Table II, Column 2, for radionuclides other than dissolved or entrained noble gases.
For dissolved or entrained noble gases, the concentration shall be limited to 2 x 10-4 uCi/ml total activity.
APPLICABILITY: At all times.
ACTION:
With the concentration or radioactive material released from the site to unrestricted areas exceeding the above limits, immediately restore con-centration within the above limits and provide prompt notification to the Commission pursuant to Specification 6.9.1.12.
SURVEILLANCE REQUIREMENTS 4.11.1.1.1 The concentration of radioactive material at any time in liquid effluents released from the site shall be continuously monitored in accordance with Table 3.3-11.
4.11.1.1.2 The radioactivity content of each batch of radioactive liquid waste to be discharged shall be determined prior to release by sampling and analysis in accordance with Table 4.11-1.
The results of pre-release analyses shall be used with the calculational methods in the ODCM to assure that the concentration at the point of release is limited to the values in Specification 3.11.1.1.
4.11.1.1.3 Post-release analyses of samples from batch releases shall be performed in accordance with Table 4.11-1.
The results of the post-release analyses shall be with the calculational methods inthe ODCM to assure that the concentrations at the point of release are limited to the values in Specification 3.11.1.1.
4.11.1.1.4 Reports.
The semiannual Radioactive Effluent Release Report shall include the information spec 1fied in Specification 6.9.1.9.
LACBWR 3/4 11-1
TABLE 4.11-1 RADIOACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAM Lower Limit Sampling Minimum Type of Activity of Detection Liquid Release Type Frequency Analysis Analysis (LLO)
Frequency (uC1/ml)3 P
P A. Batch Waste Re-Each Batch Each Batch Principal Gama 5 x 10-7 b lease Tanksd Emitterse I-131' 1 x 10-6 P
One Batch /M M
Dissolved and 1x 10-5 Entrained Gases P
H-3 1 x 10-5 Each Batch ll Conpositec Gross a 1 x 10-7 P
Each Batch Q
5 x 10-a Compositec Sr-89, Sr-90 2082 312 LAC 8WR 3/4 11-2
TABLE 4.11-1 (Cont'd)
TABLE NOTATION a.
The lower limit of detection (LLD) is defined in Table Notation a.
of Table 4.12-1 of Specification 4.12.1.1.
b.
For certain radionuclides with low gamma yield or low energies, or for certain radionuclide mixtures, it may not be possible to measure radionuclides in concentrations near the LLD. Under these circum-stances, the LLD may be increased inversely proportionally to the magnitude of the gama yield (i.e., 5 x 10-7/I, where I is the photon abundance expressed as a decimal fraction), but in no case shall the LLD, as calculated in this manner for a specific radio-nuclide, be greater than 10% of the MPC value specified in 10 CFR 20, Appendix B, Table II, Column 2.
c.
A compcsite sample is one in which the quantity of liquid sampled is proportional to the quantity of liquid waste discharged and in which the method of sampling employed results in a specimen which is representative of the liquid released.
Prior to analyses, all samples taken for the composite shall be thoroughly mixed in order for the composite sample to be representa-tive of the effluent release.
d.
A batch release is the discharge of liquid wastes of a discrete volume.
The principal gama emitters for which the LLD specification will e.
apply are exclusively the following radionuclides: Mn-54, Fe-59, Co-58, Co-60, Zn-65, Mo-99, Cs-134, Cs-137, Ce-141, and Ce-144.
This list does not mean that only these nuclides are to be detected and reported. Other peaks which are measurable and identifiable, together with the above nuclides, shall also be identified and reported.
Nuclides which are below the LLD for the analyses should not be reported as being present at the LLD level. When unusual circumstances result in LLD's higher than required, the reasons shall be documented in the semiannual Radioactive Effluent Release Report.
LACBWR 3/4 11-3 2082 313
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2082 H4 3/4 11-4
RADI0 ACTIVE EFFLUENTS DOSE LIMITING CONDITION FOR OPERATION 3.11.1.2 The dose or dose comitment to an individual from radioactive materials in liquid effluents released to unrestricted areas (see Figure 3.11-1) shall be limited:
a.
During any calendar quarter to 1 1.5 mrem to the total body and to 1 5 mrem to any organ, and b.
During any calendar year to 1 3 mrem to the total body and to 1 10 mrem to any organ.
APPLICABILITY:
At all times.
ACTION:
With the calculated dose from the release of radioactive a.
materials in liquid effluents exceeding any of the above limits, prepare and submit to the Commission within 30 days, rursuant to Specification 6.9.2, a Special Report which ident'fies the cause(s) for exceeding the limit (s) and defines the :orrective actions to be taken to reduce the releases of radioa :tive materials in liquid effluents during the remainder c : the current calendar quarter and during thesubsequent th, ee calendar quarters so that the average dose or dose commitment to an individual from such releases during these four calendar quarters is within 3 mrem to the total body and 10 mrem to any o rgan,
b.
The provisions of Sepcifications 3.0.3 and 3.0.4 are not applicable.
SURVEILLANCE REQUIREMENTS 4.11.1.2.1 Dose Calculations.
Cumulative dose contributions from liquid effluents shall be determined in accordance with the Offsite Dose Calcu-lation Manual (0DCM) at least once per 31 days.
4.11.1.2.2 Reports. The semiannual Radioactive Effluent Release Report shall include the information specified in Specification 6.9.1.9.
2082 315 LACBWR 3/4 11-5 l
RADI0 ACTIVE EFFLUENTS LIQUID WASTE TREATMENT LIMITING CONDITION FOR OPERATION 3.11.1.3 The liquid radwaste treatment system shall be OPERABLE.
The system shall be used to reduce the radioactive materials in liquid wastes prior to their discharge when the projected dose due to liquid effluent releases to unrestricted areas (see Figure 3.11-1) when averaged over 31 days would exceed 0.30 mrem to the total body or 1.0 mrem to any organ.
APPLICABILITY:
At all times.
ACT:0N:
a.
With radioactive liquid waste being discharged without treatment and in excess of the above limits, prepare and submit to the Commission within 30 days, pursuant to Specification 6.9.2, a Spchl Report which includes the following infonnation:
1.
Identification of equipment or subsystems not OPERABLE and the reason for nonoperability.
2.
Action (s) taken to restore the nonoperable equipment to OPERABLE status.
3.
Summary description of action (s) taken to prevent a recurrence, b.
The provisions of Specification 3.0.3 and 3.0.4 are not applicable.
SURVEILLANCE REQUIREMENTS 4.11.1.3.1 Doses to liquid releases to unrestricted areas shall be projected at least once per 31 days.
4.11.1.3.2 The liquid radwaste system shall be demonstrated OPERABLE at least once per 92 days unless the liquid radwaste system has been utilized to process radioactive liquid effluents during the previous 92 days.
2082 316 LACBWR 3/4 11-6
RADI0 ACTIVE EFFLUENTS 3/4.11.2 GASE0US EFFLUENTS DOSE RATE LIMITING CONDITION FOR OPERATION 3.11.2.1 The dose rate at any time in the unrestricted areas (see Figure 5.1-1 due to radioactive materials released in gaseous effluents from the site shall be limited to the following values:
a.
The dose rate limit for noble gases shall be < 500 mrem /yr to the total body and < 3000 mrem / year to the skin, and b.
The dose rate limit for all radiciodines and for all radioactive materials in particulate form and radionuclides other than noble gases, with half lives greater than 8 days, shall be < 1500 mrem / year to any organ.
APPLICABILITY:
At all times.
ACTION:
With the dose rate (s) exceeding the above limits, immediately decrease the release rate to comply with the limit (s) given in 3.11.2.1 and orovide prompt notification to the Commission.ursuant to Specifica+ ion 6.9.1.12.
SURVEILLANCE REQUIREMENTS 4.11.2.1.1 The release rate at any time of noble gases in gaseous efflu-ents shall be controlled by the offsite dose rate as established above in Specification 3.11.2.1.
4.11.2.1.2 The noble gas effluent continuous monitors having provisions for the automatic termination of gaseous releases, as listed in Table 3.3-12, shall be used to limit offsite doses within the values established in Specification 3.11.2.1 when monitor setpoint values are exceeded.
4.11.2.1.3 The release rate of radioactive materials, other than noble gases, in gaseous effluents shall be determined by obtaining representative samples and performing analyses in accordance with the sampling and analysis program, specified in Table 4.11-2.
4.11.2.1.4 The dose rate in unrestricted areas, due to radioactive materials other than noble gases released in gaseous effluents, shall be determined to be within the required limits by using the results of the sampling and analysis program, specified in Table 4.11-2, in performing the calculations of dose rate in unrestricted areas.
4.11.2.1.5 Reports The semiannual Radioactive Effluent Release Report shall include the information specified in Specification 6.9.1.9.
LACBWR 3/4 11-7 082 317
{
TABLE 4.11-2 RADI0 ACTIVE GASE0US WASTE SAMPLING AND ANALYSIS PROGRAM Minimum Lower Limit of Sampling Analysis Detection (LLD)
Gaseous Release Type Frequency Frequency Type of Activity Analysis (uCi/cc)a A.
Main Condenser Off-Mc.d Each Sample Principal Ganma Emittersh 1 x 10-4b Gas System 10-Minute Grab Sample Holdup Tank Effluent B.
Off-Gas Storage Mc.d Each Sample Principal Gamma Emittersh 1 x 10-4b Vault Discharge Grab Sample C.
Stack Effluents Continuous 9 We I-131 1 x 10-12 Charcoal 7
Sample I-133 1 x 10-10 oa Continuous 9 We Principal Gaama Emittersh Particulate (I-131, Others) 1 x 10-11 Sample Continuous 9 M
Particulate Gross Alpha 1 x 10-11 Sample Continuous 9 Q Composite Particulate Sr-89, Sr-90 1 x 10-Il Sample Mc Each Sample H-3 1 x 10-Il 00 N
u s
TABLE 4.11-2 (Cont'd)
TABLE NOTATION a.
The lower limit of detection (LLD) is defined in Table Notatiun a.
of Table 4.12-1 of Specification 4.12.1.1.
b.
For certain radionuclides with low gamma yield or low energies, or for certain radionuclide mixtures, it may not be possible to measure radionuclides in concentrations near the LLD.
Under these circum-stances, the LLD may be increased inversely proprotionally to the magnitude of the gama yield (i.e.,1 x 10-4/I, where I is the photon abundance expressed as a decimal fraction), but in no case shall the LLD, as calculated in this manner for a specific radionuclide, be greater than 10% of the MPC value specified in 10 CFR 20, Appendix B, Table II, Column 1.
c.
Ana yses shall also be perfonned following shutdown, startup, or similar operational occurrence which could significantly alter the mixture ar concentration of radionuclides.
d.
During releases via this pathway.
Analyses shall also be performed at least once within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> e.
following each shutdown, startup or similar operational occurrence which could lead to significant increases or decreases in radio-iodine releases. When samples collected for 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> are analyzed, the corresponding LLD's may be increased by a factor of 10.
f.
(Daleted).
g.
The ratio of the sample flow rate to the sampled stream flow rate shall be known for the time period covered by each dose or dose rate calculation made in accordance with Specifications 3.11.2.1, 3.11.2.2, and 3.11.2.3.
h.
The principal gamma emitters for which the LLD specification will apply are exclusively the following radionuclides:
Kr-87, Kr-88, Xe-133, Xe-133m, Xe-135, nd Xe-138 for gaseous emissions and Mn-54, Fe-59, Co-58, Co-60, Zn-65, Mo-99, Cs-134, Cs-137, Ce-141 and Ce-144 for particulate missions.
This list does not mean ttat only these nuclides are to be detected and reported.
Other peal.s which are measurable and identifiable, together with the above nuclides, shall also be identified and reported. Nuclides which are below the LLD for the analyses should not be reported as being present at the LLD level for that nuclide. When unusual circumstances result in LLD's higher than required, the reasons shall be documented in the semi-annual effluent report.
LACBWR 3/4 11-9
RADI0 ACTIVE EFFLUENTS DOSE, NOBLE GASES LIMITING CONDIT!0N FOR OPERATION 3.11.2.2 The air dose in unrestricted areas (see Figure 5.1-1) due to noble gases released in gaseous effluents shall be limited to the following:
a.
During any calendar quarter, to 1 5 mrad for ganma radiation and 5 10 mrad for beta radiation; b.
During any calendar year, to 1 10 mrad for ganma radiation and i 20 mrad for beta radiation; (The dose design objectives shall also be reduced based on expected public occupancy of areas, e.g., beaches and visitor centers within the unrestricted area boundary.
APPLICAP'LITY:
At all times.
ACTION-a.
With the calculated air dose from radioactive noble gases in gaseous effluents exceeding any of the above limits, prepare, and submit to the Commission within 30 days, pursuant to Specification 6.9.2, a Special Report which identifies the cause(s) for exceeding the limit (s) and defines the corrective actions to be taken to reduce the releases of radioactive noble gases in gaseous effluents during the remainder of the current calendar quarter and during the subsequent three calendar quarters so that the average dose during these four calerdar quarters is within (10) mrad for ganna radiation and ('.0) mrad for beta radiation.
b.
The provisions of Specification 3.0.3 and 3.0.4 are not applicable.
SURVEILLANCE REQUIREMENTS 4.11.2.2.1 Dose Calculations Cumulative dose contributions for the total time period shall be determined in accordance with the Offsite Dose Calcu-lation Manual (00CM) at least once every 31 days.
4.11.2.2.2 Reports The semiannual Radioactive Effluent Release Report shall include the information specified in Specification 6.9.1.9.
2082 320 LACBWR 3/4 11-10 i
RADI0 ACTIVE EFFLUENTS DOSE, RADI010 DINES, RADI0 ACTIVE MATERIAL IN PARTICULATE FORM, AND RADIONUCLIDES OTHER THAN N0BLE GASES LIMITING CONDITION FOR OPERATION 3.11.2.3 The dose to an individual from radioiodines, radioactive materials in particulate form, and radionuclides other than noble gases, with half-lives greater than 8 days, in gaseous effluents released to unrestricted areas (see Figure 5.1-1) shall be limited to the following:
a.
During any calendar quarter to 1 7.5 mrem; b.
During any calendar year to 1 15 mrem; (The dose design objective shall be reduced based on predicted carbon-14 releases if effluent sampling is not provided.)
APPLICABILITY: At all times.
ACTION:
a.
With the calculated dose from the release of radioiodines, radioact've materiali in particulate form, or radionuclides other thi n noble gases in gaseous effluents exceeding any of the above 'iniits, prepare and submit to the Commission within 30 days, pc suant to Specification s.9.2, a Special Report which ident. Pies the cause(s) for exceeding the limit and defines the terrective actions to be taken to reduce the releases of radiciodines, radioactive materials in particu-late fonn, and radionuclides other than noble gases, with t,alf-lives greater than 8 days, in gaseous effluents durir.1 the remainder of the current calendar quarter and during t: e subsequent three calendar quarters so that the average dose or dose commitment to an individual from such releases during these four calendar quarters is within (15) mrem to any organ.
b.
The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.
SURVEILLANCE REQUIREMENTS 4.11.2.3.1 Dose Calculations Cumulative dose contributions for the total time period shall be determined in accordance with the ODCM at least once every 31 days.
4.11.2.3.2 Reports The semiannual Radioactive Effluent Release Report shall include the information specified in Specification 6.9.1.9.
} Q}
LACBWR 3/4 11-11
RADI0 ACTIVE EFFLUENTS GASE0US RADWASTE TREATMENT LIMITING CONDITION FOR OPERATION 3.11.2.4 The gaseous radwaste treatment system shall be OPERABLE. The gaseous radwaste treatment system shall be used to reduce radioactive materials in gaseous wastes prior to their discharge when the projected gaseous effluent air doses due to gaseous effluent releases to unre-stricted areas (see Figure 5.1-1) when averaged over 31 days would exceed 0.2 mrad for gamma radiation and 0.4 mrad for beta radiation.
APPLICABILITY: At all times.
ACTION:
a.
With gaseous wastes being discharged for more than 31 days without treatment and in excess of the above limits, prepare and submit to the Comission within 30 days, pursuant to Specification 6.9.2, a Special Report which includes the following information:
1.
Identification of equipment of subsystems not OPERABLE and the reason for nonoperability.
2.
Action (s) taken to restore the non-operable equipment to OPERABLE STATUS.
l 3.
Summary description of action (s) taken to prevent a recurrence, f
l b.
The provisions of Specification 3.0.3 and 3.0.4 are not applicable.
SURVEILLANCE REQUIREMENTS 4.11.2.4.1 Doses due to gaseous releases to unrestricted areas shall be projected at least once per 31 days.
4.11.2.4.2 The gas radwaste treatment systems shall be demonstrated OPERABLE at least once per 92 days unless the appropriate system has been utilized to process radioactivo gaseous effluents during the previous 92 days.
2082 322 l
LACBWR 3/4 11-12
RADI0 ACTIVE EFFLUENTS DOSE LIMITING CONDITION FOR OPERATION 3.11.2.5 The dose or dose canmitment to a real individual from all uranium fuel cycle sources is limited to < 25 mrem to the total body or any organ (except the thyroid, which is limited to < 75 mrem) over a period of 12 co.secutive months.
APPLICABILITY: At all times.
ACTION:
a.
With the calculated dose from the release of radioactive materials in liquid or gaseous effluents exceeding twice the limits of Specifications 3.11.1.2.a, 3.ll.l.2.b, 3.ll.2.2.a, 3.ll.2. 2.b, 3. ll.2. 3.a, or 3. ll.2.3.b, prepare and su bmi t a Special Report to the Commission pursuant to Specification 6.9.2 and limit the subsequent releases such that the dose or dose commitment to a real individual from all uranium fuel cycle sources is limited to < 25 mrem to the total body or any organ (except thyroid, wEich is limited to < 75 mrem) over 12 consecutive months. This Special Report shall include an analysis which demonstrates that radiation exposures tc all real individuals from all uranium fuel cycle sources (including all effluent pathways and direct radiation) are less than the 40 CFR Part 190 Standard.
Otherwise, obtain a variance from the Commission to permit releases which exceeds the 40 CFR Part 190 Star:dard, b.
The provisions of Specification 3.0.3 and 3.0.4 are not applicable.
SURVEILLANCE REQUIREMENTS 4.11.2.5.1 Dose Calculations Cumulative dose contributions from liquid and gaseous effluents shall be determined in accordance with Specifications 3.11.1.2.a. 3.ll.l.2.b, 3.ll.2.2.a, 3.11.2.2.b, 3.11.2.3.a, and 3.ll.2.3.b, and in accordance with the Offsite Dose Calculation Manual (0DCM).
4.11.2.5.2 Reports Special Reports shall be submitted as recuired under Specification 3.ll.2.5.a.
2082 323 LACBWR 3/4 11-13
RADI0 ACTIVE EFFLUENTS EXPLOSIVE GAS MIXTURE LIMITING CONDITION FOR OPERATION 3.11.2.6 The concentration of hydrogen in the main condenser offgas treatment system shall be limited to < 4% by volume after recombination.
APPLICABILITY: At all times.
ACTION:
a.
With the concentration of hydrogen in the main condenser offgas treatment system exceeding the limit, restore the concentration to within the limit with 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />.
b.
The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.
SURVEILLANCE REQUIREMENTS 4.11.2.6 The concentration of hydrogen in the main condenser offgas treatment system shall be determined to be within the above limits by continuously monitoring the waste gases in the main condenser offgas treatment system with the hydrogen monitors required OPERABLE by Table 3.3-12 of Specification 3.3.3.9.
~2082 324 LACBWR 3/4 11-14
RADI0 ACTIVE EFFLUENTS 3/4.11.3 SOLID RADI0 ACTIVE WASTE LIMITING CONDITION FOR OPERATION 3.11.3.1 The solid radwaste system shall be OPERABLE and used to provide for the packaging of other radioactive wastes, and to ensure the meeting of the requirements of 10 CFR Part 20 and of 10 CFR Part 71 prior to shipment of radioactive wastes from the site.
APPLICABILITY: At all times.
ACTION:
a.
With the requirements of 10 CFR Part 20 and 10 CFR Part 71 not satisfied, suspend shipments of defective containers of solid radioactive wastes from the site.
b.
With the solid radwaste system not OPERABLE for more than 31 days, when required to meet 10 CFR Part 20 and 10 CFR Part 71, prepare and submit to the Commission within 30 days, pursuant to Specification 6.9.2, a Special Report which includes the following information:
1.
Identification of equipment of subsystems not OPERABLE and the reasons for inoperability.
2.
Action (s) taken to restore the incrarable equipment to OPERABLE status.
3.
A description of alternative used for packaging of wastes.
4.
Suninary description of action (s) taken to prevent a recurrence.
c.
The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.
SURVEILLANCE REQUIREMENTS 4.11.3.1.1 The solid radwaste system shall be demonstrated OPERABLE at least once per 92 days, or there be the capability for packaging of waste by meeting one or more of the conditions below:
a.
By perfonnance of functional tests of the equipment and compclents of the solid radwaste system.
b.
By operating the solid radwaste system at least once in the previous 92 days.
c.
Verification of the existence of a valid contract for packaging.
LACBWR 3/4 11-15 2082 325
SURVEILLANCE REQUIREMENTS - (Cont'd) 4.11.3.1.2 Reports - The semiannual Radioactive Effluent Release Report shall include the following information for each type of solid waste shipped offsite during the report period:
a.
container volume, total curie quantity (determined by measurement or estimate),
b.
principal gamma radionuclides (determined by measurement or c.
estima te),
d.
type of waste (e.g., spent resin, compacted dry waste, evaporator bottoms), and type of container (e.g., LSA, Type A, Type B, Large Quantity).
e.
2082 326 LACBWR 3/4 11-16
3/4.12 RADIOLOGICAL ENVIRONMENTAL MONITORING 3/4.12.1 MONITORING PROGRAM LIMITING CONDITION FOR OPERATION 3.12.1 The radiological environmental monitoring program shall be con-ducted as specified in Table 3.12-1.
APPLICABILITY: At all times.
ACTION:
a.
With the radiological environmental monitoring program not being conducted as specified in Table 3.12-1, prepare and submit to the Comission, in the Annual Radiological Operating Report, a description of the reasons for not conducting the program as required and the plans for preventing a recurrence.
(Deviations are permitted from the required sampling schedule if specimens are unobtainable due to hazardous conditions, seasonal unavail-ability, or to malfunction of automatic sampling equipment.
If the latter, every effort shall be made to complete corrective action prior to the end of the next sampling period.)
b.
With the level of radioactivity in an environmental sampling medium at one or more of the locations specified in Table 3.12-1 exceeding the limits of Table 6.9-2 when averaged over any calendar quarter, prepare and submit to the Comission within 30 aays from the end of the affected calendar quarter, a Special Report which includes an evaluation of any release conditions, environmental factors or other aspects which caused the limits of Table 6.9-2 to be exceeded.
This report is not required if the measured level of radioactivity was not the result of plant effluents; however, in such an event, the condition shall be reported and described in the Annual Radiological Environmental Operating Report.
c.
With milk or fresh leafy vegetable samples unavailable from any of the sample locations required by Table 3.12-1, prepare and submit to the Commission within 30 days, pursuant to Specifi-cation 6.9.2, a Special Report which identifies the cause of the unavailability of samples and identifies locations for obtaining replacement samples. The locations from which samples were un-available may then be deleted from Table 3.12-1 orovided the locations from which the replacement samples were obtained are added to the environmental monitoring program as replacement locations, if available.
d.
The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.
2082 327 LACBWR 3/4 12-1
SURVEILLANCE REQUIREMENTS 4.12.1.1 The radiological environmental monitoring samples shall be collected pursuant to Table 3.12-1 from the locations shown on Figure 3.12-1 and shall be analyzed pursuant to the requirements of Table 3.12-1 and 4.12-1.
4.12.1.2 Reports - The results of analyses performed on the radio-logical environmental monitoring scmples shall be summarized in the Annual Radiological Environmental Operating Report, pursuant to Specification 6.9.1.6.
i 2082 328 i
LACBWR 3/4 12-2 l,
TABLE 3.12-1 r-5 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM g
Exposure Pathway Sampling and Type of Frequency and/or Sample Sample Locations **
Collection Frequency of Analysis 1.
AIRBORNE a.
Radiciodine and Locations #4, #6, Continuous operation of Radioiodine canister.
Particulates
- 15, #16, #17, sampler with sample collec-Analyze at least once per
- 10, and #22 tion as required by dust 7 days for I-131.
loading but at least once per 7 days.
Particulate sampler.
Analyze for gross beta radioactivity > 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> following filti'r change.
u,
];
Perform gamma isotopic analysis on each sample 73 when gross beta activity is > 10 times the mean of control sample. Perform gamma isotopic analysis on composite (by location) sample at least once per 92 days.
2.
DIRECT RADIATION Locations #1-#21 At least once per 92 days.
Gamma dose. At least once
> 2 dosimeters at per 92 days.
i'ach location.
- Sample locations are shown on Figure 3.12-1.
N CD 00 N
u N
TABLE 3.12 (Cont'd) r_
M RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Exposure Pathway Sm,pling and Type and Frequency and/or Sample Sample Locations **
Collection Frequency of Analysis 3.
WATERBORNE a.
Surface Locations #15, #27 Composite
- sample collected Gamma isotopic analysis of and #30 over a period of < 31 days.
each composite sample.
Tritium analysis of compo-site sample at least once per 92 days.
b.
Ground Locations *6 and At least or. ' per 92 days.
Gamma isotopic and tritium
- 29 analyses of each sample.
w1 c.
Drinking Locations #24 and Sample collected at least Gross beta and gamma iso-93
- 31 every 31 days.
topic analysis of each sample. Tritium analysis of composite sample at least once per 92 days, d.
Sediment from Locations #22, #27, At least twice per year.
Gamma isotopic analysis of Shoreline and #30 each sample.
- Composite samples shall be collected by collecting an aliquot during at least three batch effluent discharges.
- Sample locations are shown on Figure 3.12-1.
N CD 00 N
w U
CD
5; TABLE 3.12 (Cont'd)
RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Exposure Pathway Sampling and Type and Frequency and/or Sample Sample Locations **
Collection Frequency of Analysis 4.
INGESTION a.
Milk Locations #17, #18, At least once per 15 days Gamma isotopic and I-131 and #23 when animals are on pasture; analysis of each sample.
at least once per 31 days at other times.
b.
Fish and Locations #15 or One sample in season, or at Gamma isotopic analysis on Invertebrates
- 26 and h30 or *27 least once per 184 days if edible portions.
or #28 not seasonal. One sample j{
of each of the following species at two locations:
m O,
1.
Carp 2.
Catfish c.
Food Products Locations #17, #16 At time of harvest.
One Gamma isotopic analysis on or #23, and #18 sample of each of the fol-edible portion.
lowing classes of food products:
1.
Legumes 2.
Feed Grains 3.
Garden Vegetables Location #17 At time of harvest.
One Gamma isotopic analysis.
sample of broad leaf P')
vegetation.
Oco N
- Sample locations are shown on Figure 3.12-1.
t,a u
f' s ' ua I
ir ;'
s
- ""l[l
< ^Q\\
if f p
..nu.s o v.,
,i j'
nI
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/
o w:,
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E NVI R O N M E. N TA L q)T/ '*;O D-h,p W" Q SURVEY l
PROG R A M
/
9
/ rnoA=3 j G
}
h SAMPLE L OC AT I O N g
7
- _ q P AIR l
=-*'
u f DOSL ASS E SSHE NT
/;
jl LOCATION N
M MILK SAM PL E li m@
/
' 'f' TRAIL ER P4nn
/
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& S~ AILES S
T-
~
/
k h.5 MILEC south I I _"
_[]
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/
2082 3M Radiological Environmental Monitoring Sample Locations Figure 3.12-1
TABLE 4.12-1 g
MAXIMUM VALUES FOR THE LOWER LIMITS OF DETECT 10ti (LLD)*
A orne Pa d ulate Water Fish Milk Food Products Sediment 3)
(pCi/kg, wet)
(pCi/1)
(pCi/kg, wet)
(pCi/kg. dry)
Analysis (pCi/l)
(
gross beta 4
1 x 10-2 b
3 2 A 1000D g
54 l'
130 g
59 30 260 Fe
[
58,60 15 130 Co 65 30 260 Zn 95Zr-Nb 15 131 1
7 x 10-2 1
60C 3
134,137 15(10 ). 18 1 x 10-2 130 15 80 150 Cs 140 15 15 Ba-La N
O.
CD N
u tr4 tr4
TABLE 4.12-1 (Con t' d)
TABLE NOTATION The LLO is the smallest ccacentration of radioactive material in a a
sample that will be detected with 95% probability with 5% probability of falsely concluding that a blank observation represents a "real" signal.
For a particular measurement system (which may include radio-chemical separati on):
4.66 sb LLD
=
E x V x 2.22 x Y x exp(-Att)
WHERE:
LLD is, the lower limit of detection as defined above (as pCi per unit mass or volume) sb is the standard deviation of the background counting rate or of the counting rate of a blank sample as appropt iate (as counts per minute)
E is the counting efficiency (as counts per trar.sf armation)
V is the sample size (in units of mass or volume) 2.22 is the number of traasformation per minute per picocurie Y is the fractional radiochemical yield (when applicable)
A is the radioactive decay constant for the particular radio-nuclide at is the elapsed time between sample collection (or end of the sample collection period) and time of counting The value of sb used in the calculation of the LLD for a detection system shall be based on the actual observed variance of the back-ground counting rate or of the counting rate of the blank samples (as appropriate) rather than on an unverified theoretically predicted variance.
In calculating the LLD for a radionuclide detennined by gamma-ray spectrometry, the background shall include the typical contributions of other radionuclides normally present in the samples (e.g., potassium-40 in milk samples.
2082 334 LACBWR 3/4 12-8
/
TABLE 4.12 _1 (Cont'd)
TABLE NOTATION Analyses shall be performed in such a manner that the stated LLDs will be achieved under routine conditions. Occasionally background fluctuations, unavoidably small sample sizes, the presence of interfering nuclides, or other uncontrollable circumstances may render these LLDs unachievable.
In such cases, the contributing facters will be identified and described in the Annual Radiological Environmental Operating Report.
b-LLD for drinking water.
c - LLD for leafy vegetables.
2082 335 l
LACBWR 3/4 12-9 l
RADIOLOGICAL ENVIRONMENTAL MONITORING 3/4.12.2 INTERLABORATORY COMPARISON PROGRAM LIMITitfG CONDITION FOR OPERATION
(
3.12.2 Analyses shall be performed on radioactive materials supplied as
, part of an Interlaboratory Comparison Program which has been approved by NRC.
APPLICABILITY: At all times.
ACTION:
4 a.
With analyses' riot being performed as required above, report the corrective actions taken to prevent a recurrence to the Conriission in the Annual Radiological Environmental Operating r
Report.
s b.
The provisions of Specification 3.0.3 and 3.0.4 are not applicable.
SURVELLLANCE REQUIREMENTS '
4.12.2 The results of analyses performed as part of the above required Interlaboratory Comparison Program shall be included in the Annual Radio-
+
logical Environmental Operating Report, pursuant to Specification 6.9.1.6.
J\\
I t
6 2082 336 LACBWR 3/4 12-10
~
INSTRUMENTATION BASES 3/4.3.3.8 RADI0 ACTIVE LIQUID EFFLUENT INSTRUMENTATION The radioactive liquid effluent instrumentation is provided to monitor and control, as applicable, the releases of radioactive materials in liquid effluents during actual or potential releases of liquid effluents.
The alarm / trip setpoints for these instruments shall be calculated in accordance with NRC approved methods in the ODCM to ensure that the alarm / trip will occur prior to exceeding the limits of 10 Cii Part 20.
The OPERABILITY and use of this instrumentation is consistent with the requirements of General Design Criteria 60, 63, and 64 of Appendix A to 10 CFR Part 50.
3/4.3.3.9 RADI0 ACTIVE GASE0US PROCESS AND EFFLUENT MONITORING INSTRl; MENTATION The radioactive gaseous effluent instrumentation is provided to monitor and control, as applicable, the releases of radioactive materials in gaseous effluents during actual or potential releases of gaseous effluents.
The alarm / trip setpoints for these instruments shall be calculated in accordance with NRC approved methods in the ODCM to ensure that the alarm / trip will occur prior to exceeding the limits of 10 CFR Part 20.
The process monitoring instrumentation includes provisions for monitoring the concentrations of potentially explosive gas mixtures in the main condenser offgas treatment system. The OPERABILITY and use of this instrumentation is consistent with the requirements of General Design Criteria 60, 63, and 64 of Appendix A to 10 CFR Part 50.
2082 337 LACBWR B 3/4 3-4
3/4.11 RADI0 ACTIVE EFFLUENTS BASES 3/4.11.1 LIQUID EFFLUENTS 3/4.11.1.1 CONCENTRATION This specification is provided to ensure that the concentration of radio-active materials released in liquid waste effluents from the site to unrestricted areas will be less than the concentration levels specified in 10 CFR Part 20, Appendix B, Table II.
This limitation provides addi-tional assurance that the levels of radioactive materials in bodies of water outside the site will not result in exposures within (1) the Section II.A design objectives of Appendix I,10 CFR Part 50, to an individual and (2) the limits of 10 CFR Part 20.106(e) to the population.
The concentration limit for noble gases is based upon the assumption that Xe-135 is the controlling radioisotope and its MPC in air (submersion) was converted to an equivalent concentration in water using the methods described in International Connission on Radiological Protection (ICRP)
Publication 2.
3/4.11.1.2 DOSE This specification is provided to implement the requirements of Sections II. A, III. A and IV.A of Appendix I,10 CFR Part 50.
The Limiting Condition for Operation implements the guides set forth in Section II.A of Appendix I.
The ACTION statements provide the required operating flexibility and at the same time implement the guides set forth in Section II.A of Appendix I to assure that the releases of radioactive material in liquid effluents will be kept "as low as is reasonably achievable." Also, for fresh water sites with drinking water supplies which can be potentially affected by plant operations, there is reason-able assurance that the operation of the facility will not result in radionuclide concentrations in the finished drinking water that are in excess of the requirements of 40 CFR 141. The dose calcualtions in the ODCM implement che requirements in Section III. A of Appendix I that conformance with the guides of Appendix I be shown by calculational procedures based on models and data such that the actual exposure of an individual through appropriate pathways is unlikely to be substantially underestimated. The equations specified in the ODCM for calculating the doses due to the actual release rates of radioactive materials in liquid effluents will be consistent with the methodology provided in Regulatory Guide 1.109, " Calculation of Annual Doses to Man from Routine with 10 CFR Part 50, Appendix I," Revision 1, October 1977 and Regulatory Guide 1.113. " Estimating Aquatic Dispersion of Effluents from Accidental and Routine Reactor Releases for the Purpose of Implementing Appendix I,"
April 1977. NUREG-0133 provides methods for dose calculations consistent with Regulatory Guides 1.109 and 1.113.
LACBWR B 3/4 11-1 2082 338
RADI0 ACTIVE EFFLUENTS BASES 3/4.11.1.3 LIQUID WASTE TREATMENT The OPERABILITY of the liquid radwaste treatment system ensures that this system will be available for use whenever liquid effluents require treat-ment prior to release to the environment. The requirements that the appropriate portions of this system be used when specified provides assur-ance that the releases of radioactive materials in liquid effluents will be kept "as low as is reasonably achievable." This specification imple-ments the requirements of 10 CFR Part 50.36a, General Design Criterion 60 of Appendix A to 10 CFR Part 50 and design objective Section ll.D of Appendix I to 10 CFR Part 50. The specified limits governing the use of appropriate portions of the liquid radwaste treatment system were speci-fied as a suitable fraction of the guide set forth in Section II.A of Appendix I,10 CFR Part 50, for liquid ef fluents.
3/4.11.2 GAFEOUS EFFLUENTS 3/4.11.2.1 DOSE RATE This specification is provided to ensure that the dose rate at anytime at the exclusion area boundary from gaseous effluents from all units on the site will be within the annual dose limits of 10 CFR Part 20 for unrestricted areas.
The annual dose limits are the doses associated with the concentra-tions of 10 CFR Part 20, Appendix B, Table II.
These limits provide reasonable assurance that radioactive material discharged in gaseous effluents will not result in the exposure of an individual in an unre-stricted area, either within or outside the exclusion area boundary, to annual average concentrations exceeding the limits specified in Appendix B, Table II of 10 CFR Part 20 (10 CFR Part 20.106(b)).
For individuals who may at times be within the exclusion area boundary, the occupancy of the individual will be sufficiently low to compensate for any increase in the atmospheric diffusion factor above that for the ex-clusion area boundary.
The specified release rate limits restrict, at all times, the corresponding gamma and beta dose rates above background to an individual at or beyond the exclusion area boundary to 5 500 mrem /
year tothe total body or to 5 3000 mrem / year to the skin.
These release rate limits also restrict, at all times, the corresponding thyroid dose rate above background to an infant via the cow-milk-infant pathway to 1 1500 mrem / year for the nearest cow to the plant.
2082 339 LACBWR B 3/4 11-2
RADI0 ACTIVE EFFLUENTS BASES 3/4.11.2.2 DOSE, N0BLE GASES This specification is provided to implement the requirements of Sections II.B, III.A, and IV.A of Appendix I, 10 CFR Part 50. The Limiting Condi-tion for Operation implements the guides set forth in Section II.B of Appendix I.
The ACTION statements provide the required operating flexi-bility and at the same time implement the guides set forth in Section IV.A of Appendix I assure that the releases of radioactive material in gaseous effluents will be kept "as low as is reasonably achievable." The Eurveil-lance Requirements implement the requirements in Section III. A of Appendix I that conformance with the guides of Appendix I is to be shown by calcu-lational procedures based on models and data such that the actual exposure of an individual through the appropriate pathways is unlikely to be sub-stantially underestimated. The dose calculations established in the ODCM for calculating the doses due to the actual release rates of radioactive noble gases in gaseous effluents will be consistent with the methodology provided in Regulatory Guide 1.109, " Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I," Revision 1, October 1977 and Regulatory Guide 1.111, " Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Ef fluents in Routine Releases from Light-Water-Cooled Reactors," Revision 1, July 1977.
The ODCM equations provided for detennining the air doses at the exclusion area boundary will be based upon the historical average atmospheric conditions.
NUREG-0133 provides methods for dose calculations consistent with Regulatory Guides 1.109 and 1.111.
3/4.11.2.3 DOSE, RADIO 10 DINES, RADI0 ACTIVE MATERIAL IN PARTICULATE FORM AND RADIONUCLIDES OTHER THAN NOBLE GASES This specification is provided to implement the requirements of Sections II.C, III. A, and IV.A of Appendix I,10 CFR Part 50. The Limiting Conditions for Operation are the guides set forth in Section II.C of Appendix I.
The ACTION statements provide the required operating flexibility and at the same time implement the guides set forth in Section IV. A of A;pendix I to assure that the releases of radioactive materials in gaseous effluents will be kept "as low as is reasonably achievalbe." The ODCM calculational methods specified in the surveil-lance requirements implement the requirements in Section III. A of Appendix I that conformance with the guides of Appendix I be shown by calculational procedures based on models and data such that the actual exposure of an individual through appropriate pathways is unlikely to be substantially uncerestimated.
The ODCM calculational methods approved by NRC for calculating the doses due to the actual release rates of the subject materials are required to be consistent with the methodology provided in Ragulatory Guide 1.109, " Calculating of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I," Revision I, October 1977 and Regulatory Guide 1.111, " Methods for Estimating Atmospheric Transport and 2N2 b
LACBWR B 3/4 11-3
RADI0 ACTIVE EFFLUENTS BASES Dispersion of Gaseous Effluents in Routine Releases from Light-Water-Cooled Reactors," Revision 1, July 1977.
These equations also provide for detennining the actual doses based upon the historical average atmospheric conditions. The release rate specifications for radiciodines, radioactive material in particulate form and radionuclides other than noble gases are dependent on the existing radionuclide pathways to man, in the unrestricted area. The pathways which are examined in the develop-ment of these calculations are:
(1) individual inhalation of airborne radionuclides, (2) deposition of radionuclides onto green leafy vegetation with subsequent consumption by man, (3) deposition onto grassy areas where milk animals and mean producing animals graze with consumption of the milk and meat by man, and (4) deposition on the ground with subsequent exposure of man.
3/4.11.2.4 GASE0US WASTE TREATMENT The OPERABILITY of the gaseous radwaste treatment system ensures that the system will be available for use whenever gaseous effluents require treat-ment prior to release to the environment.
The requirement that the appropriate portions of the system be used when specified provides reason-able assurance that the releases of radioactive materials in gaseous effluents will be kept "as low as is reasonably achievable." This speci-fication implements the requirements of 10 CFR Part 50.36a, General Design Criterion 60 of Appendix A to 10 CFR Part 50, and design objective Section IID of Appendix I to 10 CFR Part 50.
The specified limits governing the use of appropriate portions of the systems were specified as a suitable fraction of the guide set forth in Sections II.B and ll.C of Appendix I, 10 CFR Part 50, for gaseous effluents.
3/4.11.2.5 DOSE This specification is provided to meet the reporting requirements of 40 CFR 190.
3/4.11.2.6 EXPLOSIVE GAS MIXTURE This specification is provided to ensure that the concentration of potentially explosive gas mixtures contained in the waste gas treatment system is maintained below the flanmability limits of hydrogen and oxygen.
Automatic control features are included in the system to pre-vent the hydrogen concentrations from reaching these flammability limits.
These automatic control features include containment of the hydrogen automatic diversion to recombiners. Maintaining the concentration of hydrogen below the flammability limits provides assurance that the releases of radioactive materials will be controlled in conformance with the requirements of General Design Criterion 60 of Appendix A to 10 CFR Part 50.
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RADI0 ACTIVE EFFLUENTS BASES 3/4.11.3 SOLID RADI0 ACTIVE WASTE The OPERABILITY of the solid radwaste system ensures that the system will be available for use whenever solid radwastes require processing and packaging prior to being shipped offsite.
This specification implements the requirements of 10 CFR Part 50.36a and General Design Critiera 60 of Appendix A to 10 CFR Part 50.
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3/4.12 RADIOLOGICAL ENVIRONMENTAL MONITORING BASES 3/4.12.1 MONITORING PROGRAM The radiological monitoring program required by this specification provides measurements of radiation and of radioactive materials in those exposure pathways and for those radionuclides which lead to the highest potential radiation exposures of individuals resulting from the station operation.
This monitoring program thereby supplements the radiological effluent monitoring program by verifying that the measurable concentrations of radioactive materials and levels of radiation are not higher than expected on the basis of the effluent measurements and modeling of the environmental exposure pathways.
The initially specified monitoring program will be effective for at least the first three years of commercial operation.
Following this period, prog *am changes may be initiated based on operational experience.
The detection capabilities required by Table 4.12-1 are state-of-the-art for routine environmental measurements in industrial laboratories.
LLD's for drinking water meet the requirement of 40 CFR 141.
3/4.12.2 INTERLABORATORY COMPARISON PROGRAM The requirement for participation in a Interlaboratory Comparison Program is provided to ensure that independent checks on the precision and accuracy of the measurements of radioactive material in environmental sample matrices are performed as part of a quality assurance program for environmental monitoring in order to demonstrate that the results are reasonable valid.
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ENCLOSURE 2
Reference:
Proposed Technical Specification 3.11.1.3 The liquid waste treatment system was designed to meet 10 CFR 20 limits.
Being of early design, the liquid waste system does not incorporate the latest advances in design technology.
The evap-orator and ion exchanger are the two major processing components in the system.
The evaporator has a design capacity of 1 gpm and is not functional at the present time.
The evaporator was used initially for sample runs early in the plant's history.
It was concluded that the evaporator would not be able to handle routine volumes efficiently.
The volume of water generated due to the operation of the evaporator exceeded the volume reduction achievable with the evaporator.
The evaporator has never been used at LACBWR for the treatment of liquid wastes.
The ion exchanger is used to process tanks in order to reduce their activity levels to below 10 CFR 20 limits based on conservative dilution values.
This processing is required for less than 10% of all batch releases.
The unit has a design flowrate of 20 gpm.
Ex-perience has shown that at flowrates approaching the design values, the decontamination factor (DF) approaches one. 'Thus, to achieve higher DF's lower flowrates are used.
Historically, these flow-rates have been maintained at 1-5 gpm in order to achieve an acceptable DF.
The ion exchanger can process a small number of batches on an occasional basis but is not capable of processing every batch discharge.
This is not necessary in order to meet 10 CFR 20 limits.
The above information and actual discharge data provide the basis for proposal specification 3.11.1.3.
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