ML19319D928
| ML19319D928 | |
| Person / Time | |
|---|---|
| Site: | Rancho Seco |
| Issue date: | 06/04/1976 |
| From: | SACRAMENTO MUNICIPAL UTILITY DISTRICT |
| To: | |
| References | |
| NUDOCS 8003270600 | |
| Download: ML19319D928 (21) | |
Text
.
4 9
APPENDIX B E
OPERATING LICENSE NO. DPR-54 TECHNICAL SPECIFICATIONS FOR 'llIE RANCHO SECO UNIT 1 SACRAMENTO MJNICIPAL UTILITY DISTRICT DOCKET NO. 50-312 g
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8003270[OO pgg-y
o TABLE OF CONTENTS
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1.0 DEFINITIONS 1
2.0 ENVIRONMENTAL PROTECTION CONDITIONS 4
2.1 Maximum Discharge Temperature 4
2.2 Chforine 5
2.3 Dissolved Solids 5
2.4 pH 7
2.5. Other Chemicals Which Affect Water Quality 7
2.6 Racioactive Discharges 9
3.0 NON-RADIOLOGICAL ENVIRONMENTAL SURVEILLANCE PROGRAMS 25 3.1 Erosion 25 3.2 Drift Contamfpants 25 3.3 Liquid Effluent Contaminants 26 3.4 Noise 26 3.5_ Fogging 27 3.6 Reservoir Drawdown 29 4.0 RADIOLOGICAL ENVIRONMENTAL MONITORING 31 4.1 Fish 31 4.2 Algae and Other Aquatic Plants 31' 4.3 Surface and Runoff Water 32 4.4 Mud and Silt 33 4.5 Fresh Milk Sampling 34 4.6 Rabbits 35 4.7 Edible Vegetation 36 4.8 Well Water 37 4.9 Airborne Particulate and Iodine 37 4.10 Direct Radiation 38 5.0 ADMINISTRATIVE CONTROLS 42 5.1 Responsibility 42 5.2 Organization 42 5.3 Review and Audit 42 5.4 Action to be taken in Event of Violation of an Environmental Protection Limit 43 5.5 Procedures 44 5.6 Plant Reportirg Requirements 44 5.7 Records Retention 46 5.8 Special Requirements 47 i
l 2.6 Radioactive Discharges Objective To define the limits and conditions for the contiolled release of radioactive materials in liquid and gaseous effJuents to the environs to ensure that these releases are as low as practicable. These re-leases should not result in radiation exposures in unrestricted areas greater than a few percent of natural background exposures. The release rate for all effluent discharges shall be within the limits specified in 10 CFR Part 20.
To assure that the releases of radioactive material above background to unrestricted areas be as low as practicable as defined in Appendix I to 10 CFR Part 50, the following design objectives apply:
For liquid wastes:
A.
The annual dose above background to the total body or any organ of an individual from all reactors at a site should not exceed 5 mrem in an unrestricted area.
B.
The annual total quantity of radicactive materials in liquid waste, excluding tritium and dissolved gases, discharged from each reactor should no_t exceed 5 C1.
For gaseous wastes:
C.
The annual total quantity of noble gases above background dis-charged from the plant should result in an air dose due to gamma radiation of less than 10 mrad, and an air dose due to beta radiation of less than 20 mrad, at any location near ground level which could be occupied by individuals at or beyond the boundary of.the site.
D.
The annual total quantity of all radiciodines and radioactive material in particulate forms above background from all reactors at a site should not result in an annual dose to any organ of an
'.ndividual in an unrestricted area from all pathways of exposure in excess of 15 mrem.
E.
The annual quantity of iodine-131 discharged from each reactor at a site should not exceed 1 Ci.
2.6.1 Specifications for Liquid Waste Discharges A.
.The concentration of radioactive materials released in liquid wastes from all reactors at the site shall not exceed the values specified in 10 CFR Part 20, Appendix B. Table II, Column 2, for unrestricted areas..
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B.-
The release rate of radioactive materials in liquid wastes, ex-cluding tritium and dissolved gases, shall not exceed 10 Ci/ reactor /
calendar quarter.
C. -
The release rate of radioactive materials in liquid wastes, excluding tritium and dissolved gases, shall not exceed 20 Ci/ reactor in any 12 consecutive months.
D.
During release of radioactive wastes, the effluent control monitor shall be set to alarm and to initiate the automatic closure of the waste discharge valve prior to exceeding the limits specified in 246.1.a above.
E.
The operability of the automatic isolation valves in the liquid discharge lines shall be demonstrated quarterly.
' F.
The equipment installed in the liquid radioactive waste system shall be maintained and shall be operated to process ra.ioactive liquid wastes prior to their discharge when the projected cumulative release rate will cxceed 1.25 C1/ reactor / calendar quarter, excluding tritium and dissolved gases.
G.
The maximum radioactivity to be contained in any liquid radwaste tank that can be discharged directly to the environs shall not exceed 10 C1, excluding tritium and dissolved gases.
H.
When the release rate of radioactive materials in liquid wastes, excluding tritium'and dissolved gases, exceeds 2.5 Ci/ reactor /
calendar quarter, the licensee shall make an investigation to identify the causes for such release rates, define and inititate a program of action to reduce such release rates to the design objective levels listed in Section 2.6, and report these actions to the Commission within 30 days from the end of the quarter during whir the release occurred.
2.6.2 Specifications for Liquid Waste Sampling and Monitoring A.
Plant records shall be maintained of the radioactive concentration and volume before dilution of liquid waste intended for discharge and the average dilution flow and length cf time over which each discharge occurred.' Plant records shall be submitted in accordance with Section 5.6.1 of these specifications.
Estimates of the error associated with each reported value shall be included.
15.
Prior to release of each batch of liquid waste, a sample shall be taken from that. batch and analyzed for the concentration of each significant gamma energy peak in accordance with Table 2.6-1 to demonstrate compliance with Specification 2.6.1 using the flow rate into which the waste is discharged during the period of discharge.,
C.
Sampling and analysis of liquid radioactive waste shall be per-formed in cccordance.with Table 2.6-1.
Prior to taking samples from a monitoring tank, at least two tank volumes shall be recirculated or the agitator shall be operated sufficiently to achieve complete mixing, c
D.
The liquid radioactive wastes shall be continuously monitored and recorded during release. Whenever these monitors are inoperable for a period not to exceed 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, two independent samples of each tank to be discharged shall be analyzed and two plant personnel shall independently check valving prior to the discharge.
If these maaitors are inoperable for a period exceeding 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, no liquid waste tank shall be released and any release in progress shall be tensinated.
E.
The flow rate of liquid radioactive waste shall be measured and recorded during release.
F.
All liquid radiation monitors shall be calibrated at least quarterly by means of a radioactive source which has been calibrated-to a National Bureau of Standards source.
Each 1
monitor shall also have a functional test monthly and an
' nstrument check prior to making a release.
i 2
Bases The release of radioactive materials in liquid waste to unrestricted areas shall not exceed the concentration limits specified in 10 CFR Part 20 and should be as low as practicable in accordance with the requirements of 10 CFR Part 50.36a. These specifications provide reasonable assurance that the resulting annual exposure to the total body or any organ of an individual in an unrestricted area vill not exceed 5 area. At the;same time, these specifications permit the flexibility of operation, compatible with considerations of health and safety, -to assure that the public is provided a dependable source of power under unusual operating conditions which may temporarily result in releases higher than the design objective levels but still within tha ' concentration Itaits specified in 10 CFR Part 20.
It is expected that by using this operational' flexibility under unusual operation conditions, and exerting every effort to keep levels of radioactive material in liquid wastes as low as practicable, the ann'ual releases'will not exceed a small fraction of the concentration
' limits specified in 10 CFR Part 20.
The design objectives have been developed based on operating experience taking into account a combination of variables including defective fuel, primary system leakage, primary:to secondary ' system leakage and the performance of the various waste treatment systems, and are consistent with Appendix I'to 10 CFR Part 50..
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' Specification 2.6.1.A requires the licensee to limit the concentration of radioactive materials in liquid wastes from the site to levels specified in 10 CFR-Part 20, Appendix B, Table II, Column 2, for unrestricted areas.
This specification provides assurcnce that no cember of the general public will be exposed to liquid containing radioactive materials in excess of limits considered permissible under tha ccmmission's Rules and Regulations-using - the guidelines given in Regulatory Guide 1.21.
Specifications 2.6.1.B and 2.6.1.C establish the upper limits for the
' release of' radioactive materitis in liquid effluents. The intent of these Specifications is to permit the'licensec the flexibility of operation to assure that the public is provided a dependable source of
- power under unusual operating conditions which may temporarily result in releases higher than the levels normally achievable when the plant and the liquid waste treatment systems are functioning as designed.
Re-leases of up to these;11mits will result in concentrat!.ons of radioactive material in liquid wastes at small percentages of the 13cits specified in 10 CFK Part 20.
Specifications 2.6.1.D and 2.6.1.E require that suitable equipment to con-trol and monitor the releases of rcdioactive materials in liquid wastes ate operating during any period these relecses are taking place censistent with.the-requirements of 10 CFR Part 50, Appendix A, Design Criterion 64.
Specification 2.6.1.F requires that the licensee maintain and operate the equipment installed in the liquid waste systems to reduce the release of radioactive materials in liquid effluents to as low as practicable consistent with the requirements of 10 CFR Part 50.36a. Normal use and maintenance'of installed equipment in the liquid waste system provides reasonable assurance that the quanticy released will not exceed the design objective. In order to keep releases of radioactive materials as low as practicable,'the specification requires operation of equipment
~ henever it appears that the projected cumulative discharge rate will w
exceed ~ one-fourth of this design objective annual quantity during any calendar quarter.
3 Specification 2.6.1.G limits the amount of radioactivity that may be inadvertently released to the environment to an amount that will not
+
exceed'the Technical Specification'11mit.-
In addition to limiting conditions for operation listed under Specification 2.6.1.B and 2.6.1.C, the reporting requirements of Specification 2.6.1.H delineate that the licensee shall identify
'the cause whenever the release rate of radioactive materials in liquid wastes exceeds one-half the design objective annual quantity during any calendar quarter and describe the proposed program of action to reduce such release rate to design objective levels on a timely basis. This report must be filed within 30 days following the calendar. quarter ~in which the release occurred.
+
The sampling and monitoring requirements given under specification 2.6.2 provide assurance that radioactive materials in liquid wastes are properly controlled and monitored in conformance with the re-quirements of Design Criteria 60 and 64.
These requirements provide the data for.the licensee and the Commission to evaluate the plant's performance relative to radioactive liquid wastes released to the environment.
Reports on'the quantities of radioactive materials released in liquid wastes are furnished to the Commission according to.Section 5.6.1 of these Technical Specifications in conformance with Regulatory Guide 1.21.
On the basis of such reports and any additional information the Commission may obtain from the licensee-or others, the Commission may from time to time require the licensee to take such ac, tion as the Commission deems appropriate.
The environmental release points to be monitored in Section 2.6.2 include all the monitored release points as provided for in the Final Safety Analysis Report.
2.6.3 Specifications.for Gaseous Waste Discharges A.
(1) The release rate limit of noble gases shall be:
EQg ( 62 i
+ 110 Egg]$1 i+n where Q = release rate (sum of 3 vents) from the unit y
vent in Ci/sec (ground release) i = the individual nuclide n = total nuclides EY = the average gamma energy per disintegration ES = the average beta energy per disintegration Refer to Table 2.6-3 for E and E values to be used.
Y U
.(2) -The release rate limit of all radioiodines and radioactive materials in particulate form with half-lives greater than eight days, released to the environs as part of *.he gaseous wastes shall be:
5 1.7 x 10 q i 1 where Q = release rate (sum of 3 vents) from the unit vent in Ci/sec (ground release) -
B.
(1) The average release rate of noble gases during any calendar quarter shall be:
IQg [390 i
+ 350 ifg] 1 1 i+n (2) The average release rate of noble gases during any 12 consecutive months shall be:
IQh [780 i
+ 700 ifg] $ 1 i+n (3) The average release rate of all iodines and radio-active materials in particulate form with half-lives greater than eight days during any calendar quarter shall be:
0 2.14 x 10 Q$1 (4) The average release rate of all iodine and radio-active materials in particulate form with half-lives greater than eight days during any period of 12 con-see tive conths shall be:
6 4.28 x 10 q iy v
-(5)- The amount of iodine-131 released during any calendar quarter shall not exceed 2 C1.
(6) The amount of iodine-131 released during any period of
- 12. consecutive months shall not exceed 4 C1.
C.
Should the ~ conditions of 2.6.3.C(l), (2), or (3) listed below exist, the licensee shall make-an. investigation to identify the causes of the release rates, define and initiate a program of action to reduce the release rates to design objective levels, listed in'Section 2.6, and report these actions to the Commission within 30 days from the end of the quarter during which the' releases occurred.
(1) If the average release rate of noble gases during any calendar quarter is:
[1545 I
+ 1413 5 ) > 1 IQ g
g y
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(2) 'If the average release rate of all iodines and radioactive materials in particulate form with half-lives greater than
.eight days during any calendar quarter is:
6 8.55 x 10 q 31 y
-(3) If the amount of iodine-131 released during any calendar quarter is greater than 0.5 Ci.
D.
During the release of gaseous wastes from the primary system waste gas holdup _ system the effluent monitor shall be operating i
and set to alarm and to initiate the automatic closure of the waste gas discharge valve prior to exceeding the limits specified in 2.6.3. A (1) above. The operability of the automatic isolation valves shall be demonstrated quarterly.
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.E.
The maximum activity to be contained in one vaste gas storage
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tank shall not exceed 135,000 curies (considered as Xe-133).
2.6.4 Specifications for Caseous Waste Sampling and Monitoring A.
Plant records shall be maintained and reports of the sampling and analysis results shall be submitted in accordance with Section'5.6.1 of these Specifications.- Estimates of.the error acsociated with each reported value should be included.
B.
Gaseous _ releases'to the environment, except from the turbine building ventilation exhaust and as noted in Specification 2.6.4.C, shall be continuously monitored for gross radioactivity and the flow measured and recorded. Whenever these monitors are inoperable, grab samples shall be taken and analyzed daily for gross radioactivity. If these monitors are inoperable for more than seven days, these releases shall be terminated.
C..
During the release of gaseous wastes from the primary system
-waste gas holdup system, the gross' activity monitor,' the iodine collection' device, and the particulate collection device shall be operating.
D.- -All waste gas monitors shall be. calibrated at least quarterly by:means-of a known' radioactive source which has been calibrated to a National Bureau of Standards' source.
Each monitor shall have a functional test at least monthly and instrument check at least daily.
- E.
. Sampling and analysis-of _ radioactive material in gaseous waste,-
particulate form,-and_radioiodine shall be performed in accordance with Table 2.6-2.
'(Monitoring of radiciodine in gaseous release
'from the turbine gland seal-exhaust is not required until December 1, 1974) e 9
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f Bases-The release of radioactive materials in gaseous wastes to un-restricted areas shall not exceed the concentration limits
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specified in 10 CFR Part 20, and in accordance with the require-ments of 10 CFR Part 50.36a.
These specifications provide reasonable. assurance that the re-sulting annual air dose due to gamma radiation will not exceed 10 mrad, and an annual air dose due to beta radiation will not exceed 20 mrad from noble gaces and that the annual dose to any organ of an individual from iodinos and particulates will not exceed 15 mrem. At the same.tima these specifications permit the flexibility of operation, compatible with considerations of health and safety, ato assure that the public is prov! led with a dependable source ~of power under unusual operating concitions which may' temporarily result in releases higher than the design objective levels but still within the concentration limits specified in 10 CFR Part 20.
It is expected that using this operational flexibility under unusual operating conditicas, and by exerting every effort to keep levels of radioactive material in gasenus wastes as low as practicable, the annral releases will not exceed a small fraction of the concentration limits specified in 10 CFR Part 20.
Thece efforts chould include con-sideration of meteorological conditions during releases.
There is a reduction factor of 243 by which the maximum permissible concentration of radioactive iodine in air should be reduced to allow for the grass-cow-milk pathway.
(The factor is 1220 for the grass-goat-milk pathway.) This factor has been derived for radioactive iodine, taking into account the milk pathway. It has been applied to radionuclides of iodine and to all radionuclides in particulate form with a half-life greater than eight days. The factor is not appropriate for iodine where milk is not a pathway of exposure ~or for the other radionuclides.
The design objectives have been developed based on operating experience.taking into account a combination of system variables including defective fuel, primary system leakage, primary to secondary system leakage, and the performance of the various
-waste. treatment systems.
For. Specification 2.6.3.A(1) dose calculations have been made for
.the critical sector. These calculations consider site meteorology, j
buoyancy characteristics, and radionuclide content of the effluent 1
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L of-each unit. Meteorological calculations for offsite. locations
.were performed, aruf the most critical one was selected to set the
-release rate. The controlling distance is 640 meters to the north.
The'gammt dose contribution was determined using the equation 7.63
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in Section 7-5.2.5-of Meteorology and Atomic Energy - 1968. The releases from vents are considered to be ground level releases which could result in a beta dose from cloud submersion. The beta dose
-contribution was determined using-Equation 7.21, as described in Section 7-4.1 of Meteorology and Atomic Energy - 1968.- The beta
- dose contribution was determined on the basis of an infinite cloud passage with semi-infinite geometry for a ground level release (submersion ~ dose). The beta and gamma components of the gross radioactivity'in gaseous effluents were combined to determine the allowable continuous release rate. Based on these calculations, a-continuous release' rate of gross radioactivity in the amount specified -in 2.6.3. A(1) will not result in offsite annual doses above background in excess of~the limits specified in 10 CFR Part 20.
2 -
The average gamma and beta energy per disintegration used in the equation of Specification 2.6.3.A(1) will be based on the average i
composition of gases determined from the plant vent and ventilation exhausts. The average energy per beta or gamma disintegration for
~those radioisotopes determined to be present from the isotopic analyses are given la Table 2.6-3.
Where isotopes are identified
-that are not listed in Table 2.6-3, the gamma energy are determined
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from Table of Isotopes, C. M. Lederer, J. M. Hollander, and I. Perlman, Sixth Edition,:1967,.and the. beta energy shall be as'given in USNRDL-4
-TR-802, II.
Spectra of Individual Negatron Emitters (Beta Spectra),
O. Hogan, P._E.-Zigman, and J. L. Mackin.
5
- For. Specification 2.6.3.A(2), dose calculations have been made for the critical sectors and critical pathways for all radioiodines and radioactive material in particulate form, with half-lives greater than eight days. The calculations consider site meteorology for these. releases.
For -radiciodines and radioactive materials in particulate form, the contro111ng'sectorforunitventreleasgsistgeNsectorata
- sec/m.) for the' dose due to distance of 640 meters (X/Q = 7.8 x 10
- inhalation.- The nearest milk cow is located in the NW sector at a distance'of 11,000 mgters. 3The applicable X/Q 'at the nearest milk cow is 7.05 x 10- sec/m. 'The grass-cow-milk-child' thyroid chain is controlling.-
- The assumptions used for these calculations are:
(1) onsite meteoro-
- logical data-for the most-critical 22.5 degree sector; (2) credit for
. building wake; and (3) a reconcentration factor 243 was applied-for
.possible ecological chain effects from radioactive iodine and-particulate releases.- J
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Specification 2.6.3.B establishes upper limits for the releaces of noble gases, iodines and particulates with half-lives greater than eight days, and iodine-131 at twice the design objective annual quantity durir~ any calendar quarter, or four times the design
. objective annua _ quantity during any period of 12 consecutive months.
The intent of this specification is to permit the licensee the flexibility of operation to assure that the public is provided a
. dependable source of power under unusual operating conditions which may temporarily result in higher releases than the objectives.
In addition to the limiting conditions for operation of Specifications 2.6.3.A and 2.6.3.B. the reporting requirements of 2.6.3.C delineate that the cause be identified whenever the release of gaseous effluents exceeds one-half the design objectivo cnnual quantity during any calendar quarter and describe the proposed program of action to reduce such release rates to the design objectives.
Specification 2.6.3.D requires that suitable equipment to monitor
.and control the radioactive gaseous releases are operating during any period these releases are taking place.
Specification 2.6.3.E limits the maximum offsite dose above background to below the limits of 10 CFR Part 20, postulating that the rupture of a vaste gas storage tank holding the maximum activity releases all of the contents to the atmosphere.
The sampling and monitoring requirements given under Specification 2.6.4 provide assurance that radioactive materials released in gaseous wastes are properly controlled and monitored in conforman e with the requirements of Design Criteria 60 and 64.
These require-ments provide the data for the licensee and the Commission to evaluate the plant's performance relative to radioactive wastes released to the environment. Reports on the quantities of radioactive materials re-leased in gaseous effluents are furnished to the Commission on the basis of Section 5.6.1 of these Techn 11 Specifications and in conformance vith Regulatory Guide 1.21.
On the basis of such reports and any additional information the Commission may obtain from the licensee or others, the Commission may from time to time require the licensee co take such action as the Commission deems appropriate.
The environmental release points to be monitored in Section 2.6.4 in-clude all the monitored release points identified in the Final Safety Analysis Report. Inasmuch as the monitoring of radioiodines in gaseous release from the turbine gland seal exhaust is a recent requirement, a short delay for implementation of this monitoring is allowed in Specification 2.6.4.E to enable the licensee to provide appropriate capability. Fulfillment of this item of the General Design Criteria prior to December 1, 1974 is not necessary to assure the health and
safety of the public for the followinF reasons:
(a) provisions are included to monitor for radioactive contamination in the secondary coolant, which is the source of turbine gland seal steam; (b) pro-visions are included to monitor individual gamma emitters in the gland seal er.haust, which will provide an indicator to estimate possible radf.oiodine from this low-flow release point; and (c) based on provisions (a) and (b) above, the radioiodine release from the gland seal exhaust may be estimated and corrective action pursued.
Specification 2.6.4.B excludes monitoring the turbine building venti-lation exhaust since this release is expected to be a negligible release point. Many PWR reactors do not have turbine building enclosures. To be consistent in this requirement for all PWR reactors, the monitoring of gaseous releases from turbine buildings is not required.
2.6.5 Specifications for Solid Waste Handling and Disposal A.
Measurements shall be made to determine or estimate the total curie quantity and principle isotopic composition of all radio-active solid waste shipped offsite.
B.-
Solid wastes in storage and preparatory to shipment shall be monitored and packaged to assure compliance with 10 CFR Part 20, 10 CFR Part 71, and 49 CFR Parts 171-178.
C.
Reports of the radioactive solid waste shipments, volumes, principle l
isotopes, and total curie quantity, shall be submitted in accordance i
with Section 5.6.1.
Bases The requirements for solid radioactive waste handling and disposal given under Specification 2.6.5 provide assurance that solid radio-active materials stored at the plant and shipped offsite are packaged in conformance with 10 CFR Part-20, 10 CFR Part 71, and 49 CFR Parts 171-178. These requirements provide the data for the licensee and the Commission to evaluate the handling and storage facilities for solid radwaste, and to evaluate the environmental impact of offsite shipment 1
and storage. Reports on the quantities, principle isotopes and volumes of the shipments, are furnished to the Commission according to
,.Section 5.6.1 of these Technical Specifications. On the basis of such i
reports and any additional information the Commission may obtain from the licensee or others, the Commission may from time to time require
'the licensee to take such action as the Commission deems appropriate. l
. ~..
b Table 2.6-1 RAPIOACTIVE LIQUID SAMPLING AND ANALYSIS-Linuid Sampling Type of Detectable Source Frequency Activity Analysis Concentrations (uCi/ml)(3)
'A.
Tank Batch Releases Each Batch Individual Gamma Emitters 5'x 10-7 (2)
One Batch / Month Dissolved Cases 10-5 Weekly Composite (1)
Ba-La-140, I-131~
10'0 s
-8 SrL89 5 x 10 g
Monthly Composite ( )
-5 11-3 10 Gross a Quarterly Composite (1)
' 5 x 10-0 i
4 a
4 4
m
Table 2.6-1-~(Continued)
NOTES:
(1)l lA composite sample is one in which the quantity of liquid sampled is proportional to the quantity of liquid waste 3
' discharged from the plant.
'(2)
For certain mixtures of gamma-emitters,.it may not be possible to measure radionuclides in concentrations near their sensitivity.
limits'when other nuclides are present in the sample in much
-greater concentrations. Under these circumstances, it will be more appropriate to calculate the concentrations of such radio-nuclides using measured ratios with those radionuclides which are routinely i(entified and measured.
-(3)
The detectability limits for activity analysis are based on the technical leasibility and on 'the potential significance in the i
environment of the quantities released.
For some nuclides, lower detection limits may be readily achievable and when nuclides are measured below the stated limits, they should also be reported.
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(4)
The power level and cleanup or purification flow rate at the sample' time shall also be reported.
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Ttble 2.6-2
.T RADIOACTIVE CASEOUS WASTE SAMPLING AND ANALYSIS Gaseous >
Sampling Type of-
. Detectable E
iSource Frequency
' Activity? Analysis.
Concentr
'(uCi/ml)gons-4 A.
Waste.Cas Decay, Each Tank Individual Comma' Emitters
'10
~
Tank RF.:ases
-0
'U-3 10
-k II) - 1
.B.'..ContainmentLPurge Releases
,Each Purge Individual Camma' Emitters
'10
~0 11-3 10
. C. ; Condenser Air Ejector Monthly Individual ~Camma Emitters 10~
(2)( )
' Releases
-6 11-3 10 D.
Environmental'Relcase Points Monthly Individual Camma Emitters 10-4 (2)(3),
.(Gas Samples)
~0
-3 10
-12 (4)
U Ucekly (Charcoal Sample)
- 10
-10 Monthlv -(Charcoal Sampic)
I-133, I-135 10 i
t Weekly (Particulates)
Individual Gamma Emitters
_yy (4)
(at least for Ba-La-140, I-131 10 Monthly Composite (5)
Sr-89 10~11
.(Particulates)
Gross a 10
. Quarterly Con:posite( )
~11 Sr-90 10 (Particula t. m) w
.n 2
Tabic. 2 6-2 (Continued)
NOTES:
(1)
The'above detectability limits for activity analysis are based on technical feasibility and on-the potential significance.in the
. environment of the quantities released.
For some nuclides, ' lower detection limits may be readily achievabic.and when nuclides are measured below the stated limits, they should also be reported.
.(2)
Analyses shall also be performed following each refueling, startup or similar operational occurrence which could alter the mixture of radionuclides.
(3)
For certain mixtures of gamma emitters, it may noe be possible to
-measure radinnuclides at levels near their sensitivity limits when other nuclides are present in the sampic at much higher levcis.
i Under these circumstances, it will be tore appropriate to calculate
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the levels of such radionuclides using observed ratios with those radionuclides which are measurable.
(4)
. When the average daily gross radioactivity release rate execeds that given in 2. 6.3.c. (1) or where the steady state gross radioactivity I
release rato increases by 50% over the previous corresponding po.cr level steady state release rate, the iodinc and particulate collection device shall be recoved.and analyzed to determine the change in iodine-131 and particulate release rate. The analysis shall be done daily following such chang.c until it is shown that a pattern exists
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.which can be used to predict the release rate; after which it may revert to weekly 1 sampling frequ.ncy.
1 (5)
To be representative of the average cuantitics and concentrations of radioactive materials in particulate form released in gaseous effluents, s,amples should be collected in proportion to the rate of flow of the effluent strean.
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Table 2.6 AVERAGE ENERGY PER DISINTEGRATION
. Isotope.
Ey,mev/ dis -(Ref)'
EI,mev/ dis (
(Ref) g Kr-83m 0.00248-
_(1)~
0.0371 (1)
~ Kr-85
.0.0022 (1) 0.250 (1)
'Kr-85m 0.159 (1) 0.253 (1) uKr-87.
0.793 (1) 1.32 (1)
Kr-88 1.95 (1) 0.377 (1)
-Kr-89 2.22 (2) 1.37 (2)
Kr-90 2.10
'(2) 1.01 (2)
Xe-131m' O.0201 (1).
0.143 (1)
,Xe-133 0.04'54
' (1).
0.135 (1)
Xe-133m -
0.042
.(1) 0.19 (1)
Xe-135 0.247 (1) 0.317 (1)
Xe-135m :
0.432 (1) 0.095 (1)
Xe-137 0.1941 (1) 1.64 (1)
Xe-138 1.18 (1) 0.611 (1)
(1) 0;UL-4923, Radioactive' Atoms Supplement I, M. S. Martin, November'
- 1973..
'(2) NEDO-12037. " Summary :of Gamma and Beta Emitters and Intens;.ty Data; M. E. ' Meek, R. : S. Oilbert,' January 1970..- (The average 8 energ- 'was
/
computed ~ from" the re.aximum energy using the ICRP II -equation, not the-1/3.value assumption used in this reference.)
,(3);The average B energy includes conversion electrons.-
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5.6 Plant Reporting Requirements 5.6.1 Routine Reports
- A report on operating experience relate to the environment protection limits (Section 2) and on environmental surveillsace
]
programs (Section 3 a d 4) for ti.s previous six months will be submitted as part of the Semiannual Operating Report within 60 days after January 1 and July 1 of each year. The first such ~
' period,will begin with the date of initial criticality. The report will be a sunmaary of the results, with detailed ' data only where necessary, and will include an assessment of observed impacts of the station's operation'on the environment. In the
~
-event that some results are not available within the 60-day-period, the report should be submitted, noting and explaining the reasons for the missing results. The missing data shall
'be submitted as soon as possible in a supplementary report..
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The report will include a summary of the quantities'of radioactive effluents released from the plant as outlined in USAEC Regulatory
- Guide 1.21, with data summarized on a monthly basis following a
. standard format.
If statistically significant variations of offsite environmental radionuclide concentrations with time are observed, a comparison of these results with effluent releases shall be provided.
L Individual samples or observations which show results greater than l.
the levels stated in the Reporting Requirements in Sections 3.0 and 4.0 herein shall be specially noted and discussed in the Report.
Results of all radiological samples-taken shall be summarized on a quarterly basis following a standard format for inclusion in the semiannual report.
5.6.2 Non-Routine Reports.
A.
Radioactive Discharge The reporring requirements.for radioactive discharges are specified in Section 2.6 of these specifications.
B.
Radiological Environmental Monitoring l-l 1.
If'a measured level of radioactivity in " critical path-way environmental medium samples" indicates that the l
l resultant annual dose to an individual from these
[.
levels could equal or exceed 8 times the design objective, a plan will be submitted within one week advising the AEC of the proposed action to ensure the plant related annual doses will be within the ' design objective.
l 2.
If samples of " critical pathway environmental media" collected over a calendar quarter show total levels of radioactivity that could result in accumulated plant related doses to an. individual for that quarter of 1/2 the annual design objective, the results shall L
.be reported and'a plan submitted and implemented within 30 days'to limit conditions so that the annual dose to
-an individual will not exceed the design objective.
C.
Nonradiological In the event'an environmental protection limit (Section 2)
- is. exceeded, a report level (Sections 3 and 4) is reached, or an unusual event involving a--significant environmental impact g
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occurs, a report will be made within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> by telephone or~ telegraph to the Director of the Regional tegulatory Operations' Office, followed by a written repcrt within 10
~ days to the Director of the Regional Regula'.ory Operations Office (cc to Director of Licensing).
~
The written report and to the extent possible, the preliminary telephone' and telegraph report, will:
(a) describe, analyze and evaluate the occurrence, including extent and. magnitude of the impact, (b). describe the cause of the occurrence and (c) indicate the corrective action (including any sig'nificant changes made in procedures) taken to preclude repetition of the occurrence and to prevent similar occurrences involving similar components or systems.
5.6.3
- Charges, 1.
When a change-to the plant design, to the plant operation, or to the procedures described in Section 5.5 is planned which would have a significant adverse effect on the environment or which involves an environmental matter or question nor pre-viously reviewed and evaluated by the AEC, a report on the change will be made to the AEC prior to implementation. - The report will include a description and evaluation of the change including a supporting benefit-cost analysis.
2.
Changes or additions tofpermits and certificates required by Fed?ral, State, local and regional authorities for the pro-Laction of the environment will be reported. When the required
. changes are submitted to the concerned agency for approval, they will also be submitted to the Deputy Director for Reactor Projects, Directorate of Licensing, USAEC, for o
information. The submittal will include an evaluation of the environmental impact of the change.
3.
Request for changes in environmental technical specifications will be submitted to the Deputy Director of Reactor Projects, Directorate of -Licensing, USAEC, for prior review and authorization. 'The request will' include an evaluation of the impact of the change, including a supporting benefit-cost analysis.
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