ML20084C558
| ML20084C558 | |
| Person / Time | |
|---|---|
| Issue date: | 09/03/1982 |
| From: | NRC |
| To: | |
| References | |
| NUREG-0473, NUREG-0473-DRFT, NUREG-0473-R03-DRFT7, NUREG-473, NUREG-473-DRFT, NUREG-473-R3-DRFT7, NUDOCS 8404300089 | |
| Download: ML20084C558 (90) | |
Text
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NUREG-0473 Revision 3
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STANDARD RADIOLOGICAL EFFLUENT TECHNICAL SPECIFICATIONS FOR BOILING WATER REACTORS March 1982 SEPTEMBER 1982 1
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N INDEX DEFINITIONS SECTION PAGE 1.0 DEFINITIONS Action.............................................................
1-1 Channel Calibration................................................
1-1 Channel Check......................................................
1-1 Channel Functional Test............................................
1-1 Dose Equivalent I-131..............................................
1-1 Gaseous Radwaste Treatment System..................................
1-2 Member (s) of the Pub1ic............................................
1-2 Offsite Dose Calculation Manual (0DCM).............................
1-2 Operable - Operability.............................................
1-2 Operational Mode - Mode............................................
1-2 Process Control Program (PCP)......................................
1-2 Purge-Purging......................................................
1-3 Rated Thermal Power................................................
1-3 Site Boundary......................................................
1-3 Solidification.....................................................
1-3 Source Check.......................................................
1-3 l,
The rmd 1 P owe r......................................................
1-3 Unrestricted Area..................................................
1-3 Ventilation Exhaust Treatment System...............................
1-4 Venting............................................................
1-4 1
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NOTE:
Add 3/4.3.3.10 and 3/4.3.3.11 with appropriate page numbers to Index
'l section for Monitoring Instrumentation and its Bases; also add 5.1.3 to Section 5.0 Index and make appropriate additions to Section 6.0 Index.
-BWR-STS-I l
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b bb INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS
_SECTION PAGE 3/4.11 RADIOACTIVE EFFLUENTS 3/4.11.1 LIQUID EFFLUENTS Concentration...................'.........................
3/4 11-1 Dose.....................................................
3/4 11-5 Liquid Waste Treatment...................................
3/4 11-6 Liquid Holdup Tanks......................................
3/4 11-7 Chemical Treatment Ponds.................................
3/4 11-8 3/4 11.2 GASE0US EFFLUENTS Dose Rate................................................
3/4 11-9 Dose-Noble Gases.........................................
3/4 11-13 Dose-Radioiodines, Particulates, and Radionuclide Other than Noble Gases................
3/4 11-14 Gaseous Radwaste Treatment...............................
3/4 11-15 Ventilation Exhaust Treatment............................
3/4 11-16 Explosive Gas Mixture....................................
3/4 11-17 Main Condenser...........................................
3/4 11-19 Mark I or II Containment.................................
3/4 11-20 3/4 11.3 SOLID RADI0 ACTIVE WASTE..................................
3/4 11-21 3/4 11.4 TOTAL D0SE...............................................
3/4 11-22 3/4.12 RADIOLOGICAL ENVIRONMENTAL MONITORING 3/4.12.1 MONITORING PR0 GRAM......................................
3/4 12-1 3/4.12.2 LAND USE CENSUS.........................................
3/4 12-15 3/4.12.3 INTERLABORATORYCOMPARISON.........[....................
3/4 12-19 BWR-STS-I II 3/12/82
@MW INDEX BASES SECTION PAGE 3/4.11 RADIOACTIVE EFFLUENTS 3/4.11.1 LIQUID EFFLUENTS........................................
B 3/4 11-1 3/4.11.2 GASEOUS EFFLUENTS.......................................
B 3/4 11-2 3/4.11.3 SOLID RADI0 ACTIVE WASTE.................................
B 3/4 11-5 3/4.11.4 TOTAL 00SE..............................................
B 3/4 11-6 3/4.12 RADIOLOGICAL ENVIRONMENTAL MONITORING 3/4.12.1 MONITORING PR0 GRAM......................................
8 3/4 12-1 3/4.12.2 LAND USE CENSUS.........................................
B 3/4 12-2 3/4.12.3 INTERLABORATORY COMPARISON PR0 GRAM......................
B 3/4~12-2 I
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i BWR-STS-I a
PWR-STS-I III.
9/3/82
MMT 1.0 DEFINITIONS The defined terms of this section appear in capitalized type and are applicable throughout these Technical Specifications.
ACTION 1.1 ACTION shall be that part of a Specification which prescribes remedial measures required under designated conditions.
CHANNEL CALIBRATION 1.2 A CHANNEL CALIBRATION shall be the adjustment, as 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 CALIBRA-TION 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, overlapping or total channel steps such that the entire channel is calibrated.
CHANNEL CHECK 1.3 A CHANNEL CHECK shall be the qualitative assessment of channel behavior during operation by observation. This determination shall include, where possible, comparison of the channel indication and/or status with other indica-tions and/or status derived from independent instrumentation channels measuring the same parameter.
CHANNEL FUNCTIONAL TEST 1.4 A CHANNEL FUNCTIONAL TEST shall be:
Analog channels - the injection of a signal into the channel as close a.
to the sensor as practicable to verify OPERABILITY including alarm and/or trip functions.
b.
Bistable channels - the injection of a signal into the sensor to verify OPERABILITY including alarm and/or trip functions.
DOSE EQUIVALENT I-131 1.5 The DOSE EQUIVALENT I-131 shall be that concentration of I-131 (af rocurie/ gram) which alone would produce the same thyroid dose as the quantity and isotopic mixture of I-131, I-132, I-133, I-134 and I-135 actually present. The thyroid dose conversion factors used for this calculation shall be those listed in Table III of TID-14844, "Calculstion of Distance Factors for Power and Test Reactor Sites" [or in Table E-7'of NRC Regulatory Guide 1.109, Revision 1, October 1977].
4 BWR-STS-I H
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PWR-STS-I 1-1 9/3/82
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- 1. 0 DEFINITIONS (Continued) 4 GASEOUS RADWASTE TREATMENT SYSTEM g
g 1.6 A GASEOUS RADWASTE TREATMENT SYSTEM is any system designed and installed to reduce radioactive gaseous effluents by collecting primary coolant system offgases from the vnain a system and providing for delay or holdup for the l
purpose of reducing the total radioactivity prior to release to the environment.
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MEMBER (S) 0F THE PUBLIC
- 1. 7 MEMBER (S) 0F THE PUBLIC shall include all persons who are not occupationally associated with the plant.
This category does not include employees of the utility, its contractors or vendors. Also excluded from this category are persons who enter the site to service equipment or to make deliveries. This category does include persons who use portions of the site for recreational, occupational or other purposes not associated with the plant.
OFFSITE DOSE CALCULATION MANUAL (ODCM) 1.8 The OFFSITE DOSE CALCULATION MANUAL shall contain the current methodology and parameters used in the calculation of offsite doses due to radioactive i
gaseous and liquid effluents, in the calculation of gaseous and liquid effluent monitoring alarm / trip setpoints, and in the conduct of the environmental radiological monitoring program.
OPERABLE - OPERABILITY 1.9 A system, subsystem, train, component or device shall be OPERABLE or have OPERABILITY when it is capable of performing its specified function (s),
and when all necessary attendant instrumentation, controls, electrical power, cooling or seal water, lubrication or other auxiliary equipment that are required for the system, subsystem, train, component, or device to perform its function (s) are also capable of performing their related support function (s).
1 OPERATIONAL MODE - MODE 1.10 An OPERATIONAL MODE (i.e., MODE) shall correspond to any one inclusive combination of core reactivity condition, power level, and average reactor coolant temperature specified in Table 1.1.
d PROCESS CONTROL PROGRAM (PCP) 1 1.11 The PROCESS CONTROL PROGRAM shall contain the current formula, sampling, i
analyses, tests, and determinations to be made to ensure that the processing and packaging of solid radioactive wastes based on demonstrated processing of i
actual or simulated wet solid wastes will bo accomplished in such a way as to assure compliance with 10 CFR Part 20, 10 CFR Part 71 and Federal and State regulations and other requirements governing the disposal of the radioactive waste.
BWR-STS-I
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PWR-STS-I 1-2 9/3/82
MMii' 1.0 DEFINITIONS (Continued)
PURGE - PURGING 1.12 PURGE or PURGING is the controlled process o'f discharging air or gas from a confinement to maintain temperature, pressure, humidity, concentration or other operating condition, in such a manner that replacement air or gas is required to purify the confinement.
RATED THERMAL POWER 1.13 RATED THERMAL POWER shall be a total reactor core heat transfer rate to the reactor coolant of MWt.
SITE BOUNDARY 1.14 The SITE BOUNDARY shall be that line beyond which the land is neither owned, nor leased, nor otherwise controlled by the licensee.
SOLIDIFICATION 1.15 SOLIDIFICATION shall be the conversion of wet wastes into a form that meets shipping and burial ground requirements.
SOURCE CHECK 1.16 A, SOURCE CHECK shall be the qualitative assessment of channel response when the channel sensor is exposed to a source of increased radioactivity.
THERMAL POWER 1.17 THERMAL POWER shall be the total reactor core heat transfer rate to the reactor coolant.
UNRESTRICTED AREA 1.18 An UNRESTRICTED AREA shall be any area at or beyond the SITE BOUNDARY access to which is not controlled by the licensee for purposes of protection of individuals from exposure to radiation and radioactive materials, or any area within the SITE BOUNDARY used for residential quarters or for industrial, commercial, institutional, and/or recreational purposes.
BWR-STS-I PWR-STS-I 1-3.
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i bb 1.0 DEFINITIONS (Continued)
VENTILATION EXHAUST TREATMENT SYSTEM 1.19 A VENTILATION EXHAUST TREATMENT SYSTEM is any system designed and installed to reduce gaseous radiofodine or radioactive material in particulate form in effluents by passing ventilation or vent exhaust gases through charcoal adsorbers 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.
VENTING 1.20 VENTING is the controlled process of discharging air or gas from a con-finement to maintain temperature, pressure, humidity, concentration or other operating condition, in such a manner that replacement air or gas is not pro-vided or required during VENTING.
Vent, used in system names, does not imply a VENTING process.
TABLE 1.1 OPERATIONAL CONDITIONS MODE SWITCH AVERAGE REACTOR CONDITION POSITION COOLANT TEMPERATURE 1.
POWER OPERATION Run Any temperature 2.
STARTUP Startup/ Hot Standby Any temperature 3.
HOT SHUTDOWN Shutdown #
> 200*F 4.
COLD SHUTDOWN Shutdown #
$ 200*F 5.
REFUELING
- Shutdown or Refuel **
1 140*F
- The reactor mode switch may be placed in the Run or Startup/ Hot Standby position to test the switch interlock functions provided that the control rods are verified to remain fully inserted by a second licensed operator or other technically qualified member of the unit technical staff.
- Fuel in the reactor vessel with the vessel head closure bolts less than fully tensioned or with the head removed.
- See Special Test Exception 3.10.3.
1 BWR-STS-I PWR-STS-I l-4 9/3/82
bb0k 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.
t BWR-STS-I e
PWR-STS-I 1-5 9/3/82
l bbN 3/4 LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS 3/4.0 APPLICABILITY LIMITING CONDITION FOR OPERATION 3.0.1 Complidnce with the Limiting Conditions for Operation contained in the succeeding Specifications is required during the OPERATIONAL CONDITIONS or other conditions specified therein; except that upon failure to meet the Limiting Conditions for Operation, the associated ACTION requirements shall be met.
3.0.2 Noncompliance with a Specification shall exist when the requirements of the Limiting Condition for Operation and associated ACTION requirements are not met within the specified time intervals.
If the Limiting Condition for Operation is restored prior to expiration of the specified time intervals, completion of the Action requirements is not required.
3.0.3 When a Limiting Condition for Operation is not met, except as provided in the associated ACTION requirements, within one hour action shall be initiated to place the unit in an OPERATIONAL CONDITION in which the Specification does not apply by placing it, as applicable, in 1
1.
At least HOT SHUTDOWN within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />, and 2.
At least COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
Where corrective measures are completed that permit operation under the ACTION requirements, the ACTION may be taken in accordance with the specified time limits as measured from the time of failure to meet th: Limiting Condition for Operation.
Exceptions to these requirements are stated in the individual Specifications.
3.0.4 Entry into an OPERATIONAL CONDITION or other specified condition shall not be made unless the conditions for the Limiting Condition for Operation are met without reliance on provisions contained in the ACTION requirements. This provision shall not prevent passage through OPERATIONAL CONDITIONS as required to comply with ACTION requirements.
Exceptions to these requirements are stated in the individual Specifications.
M me wm BWR-STS-I 3/4 0-1 3/12/82
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$0b APPLICABILITY SURVEILLANCE REQUIREMENTS 4.0.1 Surveillance Requirements shall be met during the OPERATIONAL MODES or other conditions specified for individual Limiting Conditions for Operation unless otherwise stated in an individual Surveillance Requirement.
4.0.2 Each Surveillance Requirement shall be performed within the specified time interval with:
a.
A maximum allowable extension not to exceed 25% of the surveillance interval, but b.
The combined time interval for any 3 consecutive surveillance intervals shall not exceed 3.25 times the specified surveillance interval.
4.0.3 Failure to perform a Surveillance Requirement within the specified time interval shall constitute a failure to meet the OPERABILITY requirements for a Limiting Condition for Operation.
Exceptions to these requirements are stated in the individual Specifications.
Surveillance Requirements do not have to be l
performed on inoperable equipment.
4.0.4 Entry into an OPERATIONAL MODE or other specified condition shall not be made unless the Surveillance Requirement (s) associated with the Limiting Condition for Operation have been performed within the stated surveillance interval or as otherwise specified.
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DMW INSTRUMENTATION
~ RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.3.10 The radioactive liquid effluent monitoring instrumentation channels shown in Table 3.3-12 shall be OPERABLE with their alarm / trip setpoints set to ensure that the limits of Specification 3.11.1.1 are not exceeded. The alarm /
trip se'. points of these channels shall be determined and adjusted in accordance with the methodology and parameters in the OFFSITE DOSE CALCULATION MANUAL (ODCM).
APPLICABILITY: At all times, j
ACTION:
With a radioactive liquid effluent monitoring instrumentation channel a.
alarm / trip setpoint less conservative than required by the above specification, without delay suspend the release of radioactive liquid effluents monitored by the affected channel, or declare the channel inoperable, or change the setpoint so it is acceptably conservative.
b.
With less than the minimum number of radioactive liquid effluent monitoring instrumentation channels OPERABLE, take the ACTION shown in Table 3.3-12.
Exert best efforts to return the instruments to OPERABLE status within 30 days and, if unsuccessful, explain in the next Semiannual Radioactive Effluent Release Report why the inoperability was not corrected in a timely manner.
c.
The provisions of Specifications 3.0.3, 3.0.4, and 6.9.1.9.b are not applicable.
SURVEILLANCE REQUIREMENTS 4.3.3.10 Each radioactive liquid effluent monitoring instrumentation channel shall be demonstrated OPERABLE by performance of the CHANNEL CHECK, SOURCE CHECK, CHANNEL CALIBRATION and CHANNEL FUNCTIONAL TEST operations at the frequencies shown in Table 4.3-12.
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BWR-STS-I PWR-ST9-7 3/4 3-71 9/3/82
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TABLE 3.3.7.11-1 RADIDACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION v
MINIMUM CHANNELS INSTRUMENT OPERABLE ACTION 1.
GROSS RADI0 ACTIVITY MONITORS PROVIDING ALARM AND AUTOMATIC TERMINATION OF RELEASE a.
Liquid Radwaste Effluent Line (1) 110 2.
GROSS BETA OR GAfte4A RADI0 ACTIVITY MONITORS PROVIDIK1 ALARM BUT NOT PROVIDING AUTOMATIC
, TERMINATION OF RELEASE a.
Service Water System Effluent Line (1) 112 b.
Component Cooling Water System Effluent Line (1) 112 3.
FLOW RATE MEASUREMENT UEVICES I a.
Liquid Radwaste Effluent Line (1) 113 b.
Discharge Canal (1) 1,13 4.
RADI0 ACTIVITY RECORDERS
- a.
Liquid Radwaste Effluent Line (1) 115
- Required only if alare/ trip set point is based on recorder / controller M
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TABLE 3.3.7.11-1 (Continued)
RADI0 ACTIVE LIQUID EFFLUENT HONITORING INSTRUMENTATION e
MINIMUM CHANNELS INSTRUMENT OPERABLE ACTION 5.
TANK LEVEL INDICATING DEVICES **
a.
(1) 114 b.
(1) 114
' c.
(1) 114 e
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- Tanks included in this specification are those outdoor tanks that are not surrounded by liners, dikes, or IS walls capable of holding the tank contents and that do not have overflows and surrounding area drains S3 connected to the liquid radwaste treatment system.
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TABLE 3.3.7.11-1 (Continued) 1 TABLE NOTATION ACTION 110 -
With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases may continue provided that prior to initiating a release:
a.
At least two independent samples are analyzed in accordance with Specification 4.11.1.1.3, and b.
At least two technically qualified members of the Facility Staff independently verify the release rate calculations and discharge line valving; Otherwise, suspend release of radioactive effluents via this pathway.
ACTION 111 -
Not Applicable.
ACTION 112 -
With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent reler-via this pathway may continue provided t.
., at least once per12 hours, grab samples are collected and analyzed for gross radioactivity (beta or gamma) at a limit of detection of at least 10 7 microcuries/ml.
ACTION 113 -
With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue 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 actsal releases.
Pump curves generated in situ may be used to estimate flow.
ACTION 114 -
With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, liquid additions to this tank may continue provided the tank ifquid level is estimated during all liquid additions to the tank.
ACTION 115 -
With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via the affected pathway may continue provided the gross radioactivity level is determined 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 actual releases.
0 BWR-STS-I 3/4 3-75 3/12/82 t
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p TABLE 4.3.7.11 1
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$3 RADI0 ACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS Y'
CHANNEL CHANNEL SOURCE CHANNEL FUNCTIONAL INSTRUMENT CHECK CHECK CALIERATION TEST 1.
GROSS RADI0 ACTIVITY MONITORS PROVIDING ALARM AND AUTOMATIC TERMINATION OF RELEASE
- a. Liquid Radwaste Effluent Line D
P R(3)
Q(1) 2.
GROSS BETA OR G deMA RADI0 ACTIVITY MONITORS PROVIDING ALA.M BUT NOT PROVIDING AUTOMATIC TERMINATION OF RELEASE a.
Servico Water. System Effluent Line D
M R(3)
Q(2) w b.
Component Cooling Water System Effluent 1
Line D
M R(3)
Q(2) 4 as t
3.
FLOW RATE MEASUREMENT DEVICES a.
Liquid Radwaste Effluent Line D(4)
N.A.
R Q
b.
Discharge Canal D(4)
N.A.
R Q
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TABLE 4.3.7.11-1 (Continued) co s.
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CHANNEL
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f.j;7 INSTRUMENT CHECK CHECK CALIBRATION TEST CHANNEL SOURCE CHANNEL FUNCTIONAL iY; 7
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RA.DI0 ACTIVITY RECORDERS
.; m
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a.
Liquid Radwaste Effluent Line D
N.A.
R Q
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5.
TANK LEVEL INDICATING DEVICES p
a.
D*
N.A.
R Q
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D*
N.A.
R Q
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N.A.
R Q
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TABLE 4.3.7.11-1 (Continued)
TABLE NOTATION (1) The CiANNEL FUNCTIONAL TEST shall also demonstrate that automatic isolation of this pathway and control room alarm annunciation occur if any of the following conditions exists:
1.
Instrument indicates measured levels above the alarm / trip setpoint.
2.
Circuit failure.
3.
Instrument indicates a downscale failure.
4.
Instrument controls not set in operate mode.
(2) 1 The CHANNEL FUNCTIONAL TEST shall also demonstrate that control room alarm
' annunciation occurs if any of the following conditions exists:
1.
Instrument indicates measured levels above the alarm setpoint.
2.
Circuit failure.
3.
Instrument indicates a downscale failure.
4.
. Instrument controls not set in operate mode.
(3) The initial CHANNEL CALIBRATION shall be performed using one or more of the reference standards certified by the National Bureau of Standards or using standards that have been obtained from suppliers that participate in measurement assurance activities with NBS.
These standards shall permit calibrating the system over its intended range of energy and measurement range.
For subsequent CHANNEL CALIBRATION, sources that have been related to the initial calibration shall be used.
(Operating plants may substitute previcusly established calibration procedures for this requirement.)
(4) CHANNEL CHECK shall consist of verifying indication of flow during periods of release. CHANNEL CHECK shall be made at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> on days which continuous, periodic, or batch releases are made.
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BWR-STS-I 3/4 3-78 3/12/82 i
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NM INSTRUMENTATION RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.3.11 The radioactive gaseous effluent monitoring instrumentation channels shown in Table 3.3-13 shall be OPERABLE with their alarm / trip setpoints set to ensure that the limits of Specification 3.11.2.1 m.s noc exceeded.
The alarm / trip setpoints of these channels shall be determined and adjusted in accordance with the methodology and parameters in the 00CM.
APPLICABILITY: As shown in Table 3.3-13 ACTION:
With a radioactive gaseous effluent monitoring instrumentation a.
channel alarm / trip setpoint less conservative than required by the above Specification, without delay suspend the release of radioactive gaseous effluents monitored by the affected channel, or declare the channel inoperable, or change the setpoint so it is acceptably conservative.
b.
With less than the minimum number of radioactive gaseous effluent monitoring instrumentation channels OPERABLE, take the ACTION shown in Table 3.3-13.
Exert best efforts to return the instruments to OPERABLE status within 30 days and, if unsuccessful, explain in the next Semiannual Radioactive Effluent Release Report why the inoperability was not corrected in a timely manner.
I c.
The provisions of Specifications 3.0.3, 3.0.4, and 6.9.1.9.b are not appitcable.
SURVEILLANCE REQUIREMENTS 1
4.3.3.11 Each radioactive gaseous effluent monitoring instrumentation channel shall be demonstrated OPERABLE by performance of the CHANNEL CHECK, SOURCE CHECK, CHANNEL CALIBRATION and CHANNEL FUNCTIONAL TEST operations at the frequencies shown in Table 4.3-13.
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BWR-STS-I PWR-STS-I 3/4 3-79 9/3/82
TABLE 3.3.7.12-1 RADI0 ACTIVE GASEOUS EFFLUENT MONITORING INSTRUNENTATION a
MINIMUM CHANNELS INSTRUMENT OPERABLE APPLICABILITY ACTION 1.
MAIN CON 0ENSER OFFGAS TREATMENT SYSTEM EFFLUENT MONITORING SYSTEM a.
Noble Gas Activity Monitor -
Provid hg Alarm and Automatic Termination of Release (1) 123 i
l
- b. i Iodine Sampler (1) 127 c.
Particulate Sampler (1) 127 d.
Effluent System Flow Rate Measuring Device (1) 122 w
e.
Sampler Flow Rate Measuring Device (1) 122 1
2A. MAIN CONDENSER OFFGAS TREATMENT SYSTEM EXPLOSIVE GAS MONITORING SYSTEM (for systems designed to withstand the effects of a hydrogen explosion) a.
Hydrogen Monitor (1) 125 b.
Hydrogen or Oxygen Monitor (1) 125 wD
- 28. MAIN CONDENSER OFFGAS TREATMENT SYSTEM R
EXPLOSIVE GAS MONITORING SYSTEM (for E
systems not designed to withstand the effects of a hydrogen explosion) g h
a.
Hydrogen Monitor (2) 126 b.
Hydrogen or Oxygen Monitor (2) 126
TABLE 3.3.7.12-1 RADI0 ACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION T
MINIMUM CHANNELS INSTRUMENT OPERABLE APPLICABILITY ACTION 3.
REACTOR BUILDING VENTILATION / PURGE MONITORING SYSTEM a.
Noble Gas Activity Monitor (1) 124 b.
Iodine Sampler (1) 127
- c. ' Particulate Sampler (1) 127 d.
Effluent System Flow Rate Monitor (1) 122 e.
Sampler Flow Rate Monitor (1) 122 Y
a 4.
MAIN STACK MONITORING SYSTEM i
a.
Noble Gas Activity Monitor (1) 123
- b. ; Iodine Sampler (1) 127 c.
Particulate Sampler (1) 127 d.
Effluent System Flow Rate Monitor (1) 122 e.
Sampler Flow Rate Monitor (1) 122 5.
TURBINE BUILDING VENTILATION MONITORING R
SYSTEM a.
Noble Gas Activity Monitor (1) 123 h
b.
Iodine Sampler (1) 127 c.
Particulate Sampler (1) 127 I
TABLE 3.3.7.12-1 (Continued) as Ef5 f;
RADI0 ACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION
.Y.'
MINIMUM CHANNELS INSTRUMENT OPERABLE APPLICABILITY ACTION 5.
TURBINE BUILDING VENTILATION MONITORING SYSTEM (Continued) d.
Effluent System Flow Rate Monitor (1) 122 e.
Sampler Flow Rate Monitor (1) 122 6.
AUXILIARY BUILDING VENTILATION MONITORING SYSTEM a.
Noble Gas Activity Monitor (1) 123
$3 b.
Iodine Sampler (1) 127 c.'
Particulate Sampler (1) 127 i
d.:
Flow Rate Monitor (1) 122 2
i
_Q e.
Sampler Flow Rate Monitor (1) 122 7.
. FUEL STORAGE AREA VENTILATION MONITORING SYSTEM a.
Noble Gas Activity Monitor (1) 123 jg b.
Iodine Sampler (1) 127 a>
c.
Particulate Sampler (1) 127 l{f d.
Flow Rate Monitor (1) 122 bhf e.
Sampler Flow Rate Monitor (1) 122 c:'d
TABLE 3.3.7.12-1 (Continued)
RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION
?
~
MINIMUM CHANNELS INSTRUMENT OPERABLE APPLICABILITY ACTION 8.
RADWASTE AREA VENTILATION MONITORING i
SYSTEM a.
Noble Gas Activity Monitor (1) 123 3
b.
Iodine Sampler (1) 127 c.
Particulate Sampler (1) 127 d.
Flow Rate Monitor (1) 122 e.
Saapler Flow Rate Monitor (1) 122 w
do 9.
TURBINE GLAND SEAL CONDENSER VENT ANO.
1 MECHANICAL VACUUM PUMP EXNAUST MONITORING SYSTEM a.{NobleGasActivityMonitor (1) 123
.i
. b.
Iodire Sampler (1) 127
}
c.
Particulate Sampler (1) 127 d.
Flow Rate Monitor (1) 122 e.
Sampler Flow Rate Monitor (1) 122 I
-T
.10.
CONDENSER AIR EJECTOR RADI0 ACTIVITY P3 -
MDNITOR (Prior to Input te Holdup h
c System) m a.
Noble Gas Activity Monitor (1) 121
1 bbb TABLE 3.3.7.12-1 (Continued)
TABLE NOTATION At all times.
During main condenser offgas treatment system operation.
- During operation of the main condenser air ejector.
ACTION 121 -
With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, the contents of the tank (s) may be released to the environment for up to 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> provided:
a.
The offgas system is not bypassed, and b.
The offgas delay system noble gas activity effluent (downstream) monitor is OPERABLE; Otherwise, be in at least HOT STANDBY within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
ACTION 122 -
With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement. effluent releases via this pathway may continue 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 123 -
With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue provided grab samples are taken at least once per12 hours and these samples 4
I 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 />.
O mmet a%)
ACTION 124 -
With the number of channels OPERA 5LL les3 Enan required by the Minimum Channels OPERABLE requirement, suspend release of radioactive effluents via this pathway.
ACTION 125 -
With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, operation of main condenser offgas treatment system may continue provided grab samples are collected at least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> and analyzed within the following 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.
ACTION 126 -
With the number of channnels OPERA 8LE one less than required by the Minimum Channels OPERABLE requirement, operation of this system may continue for up to 14 days.
ACTION 127 -
With the number of channels OPERA 8LE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may c.ontinue provided samples are continuously collected with auxiliary sampling equipment as required in Table 4.11-2.
J 4
BWR-STS-I 3/4 3-84 3/12/82 p-
~
,w
-e-e e
r,-,,--r y
, v w-,
w--o,-,-,,e
--w w,
o,
,,vr-w,
-+-,v
TABLE 4.3.7.12-1 Ei RADI0 ACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS d
CHANNEL MODES IN WHICH CHANNEL SOURCE CHANNEL FUNCTIONAL SURVEILLANCE INSTRUMENT CHECK CHECK CALIBRATION TEST REQUIRED 1.
MAIN CONDENSER OFFGAS TREATMENT SYSTEM EFFLUENT MONITORING SYSTEM
- a. Noble Gas Activity Monitor -
Providing Alam and Automatic Termination of Release D
P R(3)
Q(1)
- b. Iodine Sampler W
N.A.
N.A.
N.A.
R
- c. Particulate Sampler W
N.A.
N.A.
N.A.
- d. Flow Rate Monitor D
N.A.
R Q
- e. ' Sampler Flow Rate Monitor D
N.A.
R Q
2A. MAIN CONDENSER OFFGAS TREATMENT SYSTEM EXPLOSIVE GAS MONITORING SYSTFM (for systems designed to withstand the effects of a hydrogen explosion) a.
Hydrogen Monitor D
N.A.
Q(4)
M b.
N.A.
Q(4) or Q(5)
M
~
M E 28. MAIN CONDENSER OFFGAS TREATMENT SYSTEM D
EXPLOSIVE GAS MONITORING SYSTEM (for systems not designed to withstand the g3 effects of a hydrogen explosion) a.
Hydrogen Monitor D
N.A.
Q(4)
M la I
b.
N.A.
Q(4) or Q(5)
M O
8 m
TABLE 4.3.7.12-1 (Continued) oo T5 b,
Rt.DI0 ACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS CHANNEL MODES IN WHICH CHANNEL SOURCE CHANNEL FUNCTIONAL SURVEILLANCE INSTRUMENT CHECK CHECK CALIBRATION TEST REQUIRED 3.
REACTOR BUILDING VENTILATION / PURGE MONITORING SYSTEM
- a. Noble Gas Activity Monitor D
M R(3)
Q(1)
- b. Iodine Sampler W
N.A.
N.A.
N.A.
- c. Particulate Sampler W
N.A.
N.A.
N.A.
Id
- d. Effluent System Flow Rate Monitor D
N.A.
R Q
- e. Sampler Flow Rate Monitor D
N.A.
R Q
4.
MAIN STACK MONITORING SYSTEM a.INoble Gas Activity Monitor D
M R(3)
Q(2)
- b. Iodine Sampler W
N.A.
N.A.
N.A.
- c. Particulate Sampler W
N.A.
N.A.
N.A.
- d. Effluent System Flow Rate Monitor D
N.A.
R Q
- e. Sampler Flow Rate Monitor D
N.A.
R Q
D
~
ge~
EE -
c6.,
c:d
TABLE 4.3.7.12-1 (Continued) to E
0, RADI0 ACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIRENENTS d
1.
CHANNEL MODES IN WHICH CHANNEL SOURCE CHANNEL FUNCTIONAL SURVEILLANCE INSTRUMENT CHECK CHECK CALIBRATION TEST REQUIRED 5.
TUR8INE BUILDING VENTILATION MDNITORING SYSTEM
- a. Noble Gas Activity Monitor D
M R(3)
Q(2)
- b. Iodine Sampler W
N.A.
N.A.
N.A.
- c. Particulate Sampler W
N.A.
N.A.
N.A.
E44l~t w.%
R
- d., Flow Rate Monitor D
N.A.
R Q
y
- e. Sampler Flow Rate Monitor D
N.A.
R Q
6.
AUNILIARY BUILDING VENTILATION MONITORING SYSTEM a.l Noble Gas Actvity Monitor D
M R(3)
Q(2) 1
- b. Iodine Sampler W
N.A.
N.A.
N.A.
- c. Particulate Sampler W
N.A.
N.A.
N.A.
- d. Flow Rate Monitor D
N.A.
R Q
R
- e. Sampler Flow Rate Monitor D
N.A.
R Q
M
'ea by 2h
p TABLE 4.3.7.12-1 (Continued) l
.=
0, RADI0 ACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS l
1 CHANNEL MODES IN WHICH CHANNEL SOURCE CHANNEL FUNCTIONAL SURVEILLANCE INSTRUMENT CHECK CHECK CALIBRATION TEST REQUIRED l
7.
FUEL STORAGE AREA VENTILATION l
MONITORING SYSTEM
- a. Noble Gas Activity Monitor D
M R(3)
Q(2) l 1
- b. Iodine Sampler W
N.A.
N.A.
N.A.
- c. Particulate Sampler W
N.A.
N.A.
N.A.
g
- d. Flow Rate Monitor D
N.A.
R Q
Y
- e. Sampler Flow Ra'te Monitor D
N.A.
R Q
E 8.
RA8 WASTE AREA VENTILATION MONITORING SYSTEM a.!NobleGasActivityMonitor D
M R(3)
Q(2)
- b. Iodine Sampler W
N.A.
N.A.
N.A
- c. Particulate Sampler W
N.A.
N.A.
N.A
- d. Flow Rate Monitor D
N.A.
R Q
R
- e. Sampler Flow Rate Monitor D
N.A.
R Q
M 2B
~
c4 bz EDk
_n,
TABLE 4.3.7.12-1 (Continued)
TB g,
RADI0 ACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIRENENTS f
~
CHANNEL MODES IN WHICH CHANNEL SOURCE CHANNEL FUNCTIONAL SURVEILLANCE INSTRUMENT CHECK CHECK CALIBRATION TEST REQUIRED 9.
TURBINE GLAND SEAL CONDENSER VENT AND MECHANICAL VACUUM PUMP EXHAUST MONITORING SYSTEM
- a. Noble Gas Activity Monitor D
M R(3)
Q(2)
- b. Iodine Sampler W
N.A.
N.A.
N.A
- c. Particulate Sampler W
N.A.
N.A.
N.A.
- d. Flow Rate Monitor D
N.A.
R Q
- e. Sampler Flow Rate Monitor D
N.A.
R Q
- 10. COM)ENSER AIR EJECTOR RADI0 ACTIVITY MONITOR a.{
Noble Gas Activity Monitor D
M R(3)
Q(2)
C3 reM
- n
@MR TABLE 4.3.7.12-1 (Continued)
TABLE NOTATION
- At all times.
During main condenser offgas treatment system operation.
During operation of the main condenser air ejector.
(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 exists:
1.
Instrument indicates measured levels above the alarm / trip setpoint.
2.
Circuit failure.
3.
Instrument indicates a downscale failure.
4.
Instrument controls not set in operate mode.
(2) The CHANNEL FUNCTIONAL TEST shall also demonstrate that control room alarm annunciation occurs if any of the following conditions exists:
1.
Instrument indicates measured levels above the alarm setpoir.t.
2.
Circuit failure.
3.
Instrument indicates a downscale failure.
4.
Instrument controls not set in operate mode.
(3) The initial CHANNEL CALIBRATION shall be performed using one or more of the reference standards certified by the National Bureau of Standards or using standards that have been obtained from suppliers that participate in measurement assurance activities with NBS.
These standards shall permit calibrating the system over its intended range of energy and measurement range.
For subsequent CHANNEL CALIBRATION,-sources that have been related to the initial calibration shall be used.
(Operating plants may substitute previously established calibration procedures for this requirement.)
(4) The CHANNEL CALIBRATION shall include the use of standard gas samples containing a nominal:
1.
One volume percent hydrogen,. balance nitrogen, and 2.
Four volume percent hydrogen, balance nitrogen.
(5) The CHANNEL CALIBRATION shall include the use of standard gas samples containing a nominal:
1.
One volume percent oxygen, balance nitrogen, and 2.
Four volume percent oxygen, balance nitrogen.
BWR-STS-I 3/4 3-90 3/12/82
1 bubN 1
3/4.11 RADIOACTIVE EFFLUENTS j
3/4.11.1 LIQUID EFFLUENTS CONCENTRATION LIMITING CONDITION FOR OPERATION 3.11.1.1 The concentration of radioactive material released in liquid effluents to UNRESTRICTED AREAS (see Figure 5.1-3) shall be limited to the concentrations specified in 10 CFR Part 20, Appendix 8, 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 microcuries/ml total 1
j
- activity, i
APPLICABILITY: At all times.
ACTION:
a.
With the concentration of radioactive material released in liquid effluents to UNRESTRICTED AREAS exceeding the above limits, without delay restore the concentration to within the above limits.
b.
The provisions of Specification 6.9.1.9.b are not applicable.
SURVEILLANCE REQUIREMENTS t
4.11.1.1.1 Radioactive liquid wastes shall be sampled and analyzed according to the sampling and analysis program of Table 4.11-1.
4.11.1.1.2 The results of the radioactivity analyses shall be used in accordance with the methodology and parameters in the 00CM to. assure that the concentrations at the point of release are maintained within the limits of Specification 3.11.1.1.
l l
i BWR-STS-I PWR-STS-I 3/4 11-1 9/3/82
. - ~,,,. _ -.,,,,, _ -,
.-,y____.,
, - _ ~ -.. - _,, - - - -,
,.-,--__,.m
.--,r
.e o
bb TABLE 4.11-1 l
RADIOACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAM d
Lower Limit l~
Liquid Release Sampling Analysis Type of Activity (LLD)
Minimum ofDetect}on i
Type Frequency Frequency Analysis (pC1/ml)
A. Batch Waste P
P
~7 Releage Each Batch Each Batch Principa} Gamma 5x10 Tanks Emitters
-6 I-131 1x10
-5 P
M Dissolved and 1x10 One Batch /M Entrained Gases (Gamma Emitters)
-5 P
M H-3 1x10 d
Each Batch Composite g
Gross Alpha 1x10
-8 P
Q Sr-89, Sr-90 5x10 d
Each Batch Composite l
B.Continuogs f
f Principa} Gamma 5x10"7 W
Releases Continuous Composite Emitters i
-6 I-131 1x10
-5 M
M Dissolved and 1x10 Grab Sample Entrained Gases (Gamma Emitters)
-5 M
H-3 1x10 Continuous #
Composite #
_7 Gross Alpha 1x10 a
-8 Q
Sr-89, Sr-90
'5x10 f
f Continuous Composite
-6 Fe-55 1x10 1
i BWR-STS-I PWR-STS-I' 3/4 11-2 9/3/82
=
k I
TABLE 4.11-1 (Continued)
TABLE NOTATION "The LLD is defined, for purposes of these specifications, as the smallest concentration of radioactive material in a sample that will yield a net count, above system background, that will be detected with 95% probability with only 5% probability of falsely concluding that a blank cbservation i
represents a "real" signal.
For a particular measurement system, which may include radiochemical separation:
4*00 'b g,
E V
2.22 x 108 Y
exp (-AAt) 4 Where:
I LLD is the "a priori" lower limit of detection as defined above, as microcuries per unit mass or volume, i
s is the standard deviation of the background counting rate or of b
tne counting rate of a blank sample as appropriate, as counts per
- minute, E is the counting efficiency, as counts per disintegration, V is the sample size in units of mass or volume, 2.22 x 10e is the number of disintegrations per minute per microcurie, Y is the. fractional radiochemical yield, when applicable, A is the radioactive decay constant for the particular radionuclide, and At for plant effluents is the elapsed time between the midpoint of l-sample collection and time of counting.
('
Typical values of E, V, Y, and at should be used in the calculation.
It should be recognized that the LLO is defined as an a priori (before the fact) limit representing the capability of a measurement system and l
not as an a posteriori (after the fact) limit for a particular measurement.
bA batch release is the discharge of liquid wastes of a discrete volume.
Prior to sampling for analyses, each batch shall be isolated, and then thoroughly mixed to usure representative sampling, i
BWR-STS-I PWR-STS-I 3/4 11-3 9/3/82 i
,,s...
..,,.---___m
M W il TABLE 4.11-1 (Continued)
TABLE NOTATION cThe principal gamma emitters for which the LLD specification applies exclusively are the following radionuclides: Mn-54, Fe-09, 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 considered.
Othar gamma peaks that are identifiable, together with those of the above nuclides, shall also be analyzed and reported in the Semiannual Radioactive Effluent Release Report pursuant to Specification 6.9.1.12.
dA composite 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 that is representative of the liquids released.
'A continuous release is the discharge of liquid wastes of a nondiscrete volume, e.g., from a volume of a system that has an input flow during the continuous release.
To be representative of the quantities and concentrations of radioactive materials in liquid effluents, samples shall be collected continuously in proportion to the rate of flow of the effluent stream.
Prior to analyses, all samples taken for the composite shall be thoroughly mixed in order for the composite sample to be representative of the effluent release.
.i
'b O 'M BWR-STS-I PWR-STS-I 3/4 11-4 9/3/82
)
i bhb[b)$[
l RADIOACTIVE EFFLUENTS DOSE LIMITING CONDITION FOR OPERATION i
3.11.1.2 The dose or dose commitment to a MEMBER OF THE PUBLIC from radio-active materials in liquid effluents released, from each reactor unit, to UNRESTRICTED AREAS (see Figure 5.1-3) shall be limited:
a.
During any calendar quarter to less than or equal to 1.5 mrems to the total body and to less than or equal to 5 mress to any organ, and b.
During any calendar year to less than or equal to 3 mrems to the total body and to less than or equal to 10 mrems to any nrgan.
APPLICABILITY: At all times.
ACTION:
a.
With the calculated dose from the release of radioactive materials in liquid effluents exceeding any of the above limits, in lieu of a Licensee Event Report, prepare and submit to the Commission within 30 days, pursuant to Specification 6.9.2, a Special Report that identifies the cause(s) for exceeding the limit (s) and defines the corrective actions that have been taken to reduce the releases and the proposed corrective actions to be taken to assure that subsequent releases will be in compliance with the above limits.
This Special Report shall also include (1) the results of radiological analyses of the drinking water source and (2) the radiological impact on finished drinking water supplies with regard to the requirements of 40 CFR Part 141.*
b.
The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.
SURVEILLANCE REQUIREMENTS 2
4.11.1.2 Cumulative dose contributions from liquid effluents for the current calendar quarter and the current calendar year shall be determined in accordance with the methodology and parameters in the ODCM at least once per 31 days.
~
- Applicable only if drinking water supply is taken from the receiving water body within 3 miles of the plant discharge.
In the case of river sited plants this is 3 miles downstream only.
BWR-STS-I PWR-STS-I 3/4 11-5 9/3/82
LMFD' RADIOACTIVE EFFLUENTS LIQUID RADWASTE TREATMENT SYSTEM LIMITING CONDITION FOR OPERATION 3.11.1.3 The liquid radwaste treatment system shall be used to reduce the radioactive materials in liquid wastes prior to their discharge when the projected doses due to the liquid effluent, from each reactor unit, to UNRESTRICTED AREAS (see Figure 5.1-3) would exceed 0.06 mrem to the total body or 0.2 mrem to any organ in a 31 day period.
APPLICABILITY: At all times.
ACTION:
With radioactive liquid waste being discharged without treatment and a.
in excess of the above limits, in Ifeu of a Licensee Event Report, prepare and submit to the Commission within 30 days pursuant to Specification 6.9.2 a Special Report that includes the following information:
1.
Explanation of why liquid radwaste was being discharged without treatment, identification of any inoperable equipment or subsystems, and the reason for the inoperability, 2.
Action (s) taken to restore the inoperable equipment to OPERABLE i
status, and 3.
Summary description of action (s) taken to prevent a recurrence.
b.
The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.
SURVEILLANCE REQUIREMENTS 4.11.1.3 Doses due to liquid releases from each reactor unit to UNRESTRICTED AREAS shall be projected at least once per 31 days in accordance with the methodology and parameters in the ODCM.
BWR-STS-I PWR-STS-!
3/4 11-6 9/3/82
@MN RADI0 ACTIVE EFFLUENTS l
LIQUID HOLDUP TANKS *
(Appropriate alternatives to the ACTIONS and SURVEILLANCE
{
REQUIREMENTS below can be accepted if they provide reasonable assurance that in the event of an uncontrolled release of the tanks' contents, the resulting concentrations would be less than the limits of 10 CFR Part 20, Appendix B, 1
Table II, Column 2, at the nearest potable water supply and the nearest i
surface water supply in an UNRESTRICTED AREA.)
l LIMITING CONDITION FOR OPERATION 3.11.1.4 The quantity of radioactive material contained in each of the following j
unprotected outdoor tanks shall be limited to less than or equal to
- curies, excluding tritium and dissolved or entrained noble gases.
a.
b.
c.
d.
Outside temporary tank APPLICABILITY: At all times.
ACTION:
1 With the quantity of radioactive material in any of the above listed a.
tanks exceeding the above Ifmit, immediately suspend all additions of radioactive material to the tank, within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> reduce the tank contents to within the Ifmit, and describe the events leading to this condition in the next Semiannual Radioactive Effluent Release Report.
b.
The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.
SURVEILLANCE REQUIREMENTS 4.11.1.4 The quantity of radioactive material contained in each of the above listed tanks shall be determined to be within the above limit by analyzing a representative sample of the tank's contents at least once per 7 days when radioactive materials are being added to the tank.
Tanks included'in this specification are those outdoor tanks that are not surrounded by liners, dikes, or walls capable of holding the tank contents and that do not have tank overflows and surrounding area drains connected to the liquid radwaste treatment system.
BWR-STS-1 PWR-STS-I 3/4 11-7 9/3/82
i 4
bb RADI0 ACTIVE EFFLUENTS l
3/4.11.2 GASEOUS EFFLUENTS i
DOSE RATE
?
j LIMITING CONDITION FOR OPERATION i
3.11.2.1 The dose rate due to radioactive materials released in gaseous effluents from the site to areas at and beyond the SITE 80UNDARY (see Figure 5.1-3) shall be limited to the following:
i a.
For noble gases:
Less than or equal to 500 mress/yr to the total i
l body and less than or equal to 3000 mress/yr to the skin, and 4.g iodine -IO, b.
For iodine-131,,for tritium, and for all radionuclides in particulate j
form with half Tives greater than 8 days:
Less than or equal to 2
1500 mrems/yr to any organ.
APPLICABILITY:
At all times.
ACTION:
a.
With the dose rate (s) exceeding the above limits, without delay restore the release rate to within the above limit (s).
i b.
The provisions of Specification 6.9.1.9.b are not applicable.
SURVEILLANCE REQUIREMENTS 2
4.11.2.1.1 The dose rate due to noble gases in gaseous effluents shall be determined to be within the above limits in accordance with the metnodology j
and parameters in the 00CM.
us.a-t es, particulate form with half lives greater than, tritium, and all radionuclides in 4.11.2.1.2 The dose rate due to iodine-131, 8 days in gaseous effluents shall l
be determined to be within the above limits in accordance with the methodology l
and parameters in the 00CM by obtaining representative samples and performing analyses in accordance with the sampling and analysis program specified in Table 4.11-2.
i
~.-
j i
4 BWR-STS-I PWR-STS-I 3/4 11-8 9/3/82
i
?
TABLE 4.11-2 7:
RA010 ACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS PROGRAM UU TT Minimum Lower Limit of Sampling Analysis Type of Detection (LLO)"
Gaseous Release Type Frequency Frequency Activity Analysis (pCi/ml) b
-4 A.
Offgas Treatment M
M Principal Gamma Emitters 1x10 System (Pretreat-Grab ment)*
Sampi.e_
C c
b
-4 B.
Containment PURGE Eac PURGE Each PURGE Principal Gamma Emitters 1x10 Grab
-6 Sample H-3 1x10 C.
(List other release M**d'*
M' Principal Gamma Emitters 1x10 D
-4 points tshere gas-Grab w
eous effluents are Sample
-6 1
discharged from the H-3 1x10 facility)
D.
All Release Types Continuous #
W I-131 1x10 9
-12 l
as listed in A, B, Charcoal l
C above.
Sample Continuous #
W9 D
-U Principal Gamma Eiaitters 1x10 f
Particulate (I-131, Others)
Sample Continuous #
M Gross Alpha 1x10~U Composite Particulate Sample Continuous #
Q Sr-89, Sr -90 1x10 "
Composite Particulate g
Sample D"
Continuous #
Noble Gas Noble Gases 1x10'6 E3
{
Monitor Gross Reta or -
r "If the plant uses stcrage tanks, each tank shall be sampled prior to release and the sample analyzed
~
2'!,
prior to release.
e e
.o
@MMT TABLE 4.11-2 (Continued)
TABLE NOTATION
- The LLD is defined, for purposes of these specifications, as the smallest concentration of radioactive material in a sample that will yield a net count, above system background, that will be detected with 95% probability with only 5% probability of falsely concluding that a blank observation represents a "real" signal.
For a particular measurement system, which may include radiochemical separation:
4" LLD =
D E
V 2.22 x 108 Y
exp (-Aat)
Where:
LLD is the "a priori" lower limit of detection as defined above, as microcuries per unit mass or volume, t
is the standard deviation of the background counting rate or of sb tne counting rate of a blank sample as appropriate, as counts per
- minute, E is the counting efficiency, as counts per disintegration, V is the sample size in units of mass or volume, 2.22 x 108 is the number of disintegrations per minute per microcurie, Y is the, fractional radiochemical yield, when applicable, A is the radioactive decay constant for the particular radionuclide, and at for plant effluents is the elapsed time between the midpoint of sample collection and time of counting.
Typical values of E, V, Y, and At should be used in the calculation.
It should be recognized that the LLD is defined as an a priori (before the fact) limit representing the capability of a measurement system and not as an a posteriori (after the fact) limit for a particular measurement.
BWR-STS-1 O
PWR-STS-I 3/4 11-10 9/3/82
1 i
l TABLE 4.11-2 (Continued) i TABLE NOTATION DThe principal gamma emitters for which the LLD specification applies exclusively are the following radionuclides:
Kr-87, Kr-88, Xe-133, Xe-133m, Xe-135, and 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 emissions. This list does not mean that only these nuclides are to be considered. Other gamma peaks that are identifiable, together i
with those of the above nuclides, shall also be analyzed and reported in i
i the Semiannual Radioactive Effluent Release Report pursuant to
{
Specification 6.9.1.12.
cSampling and analysis shall also be performed following shutdown, startup, or a THERMAL POWER change exceeding 15 percent of RATED THERMAL POWER l
within one hour unless (1) analysis shows that the DOSE EQUIVALENT I-131 concentration in the primary coolant has not increased more than a factor of 3; and (2) the noble gas activity monitor shows that effluent activity has not increased by more than a factor or 3.
d Not Applicable.
' Tritium grab samples shall be taken at least once per 7 days from the i.
ventilation exhaust from the spent fuel pool area, whenever spent fuel is
}
in the spent fuel pool.
IThe 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 j
made in accordance with Specifications 3.11.2.1, 3.11.2.2 and 3.11.2.3.
U Samples shall be changed at least once per 7 days and analyses shall be 1
completed within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> after changing, or after removal from sampler.
Sampling shall also be performed at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> for at least 7 days following each shutdown, startup or THERMAL POWER change exceeding 15 percent of RATED THERMAL POWER in one hour and analyses shall be completed within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> of changing. 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 LLDs may be increased by a factor of 10.
This requirement does not apply if (1) analysis shows that the DOSE EQUIVALENT I-131 concentration in the primary coolant has not increased more than a factor of 3; and (2) the noble gas monitor shows that i
effluent activity has not increased more than a factor of 3.
r f
i i
BWR-STS-I PWR-STS-I 3/4 11-11 9/3/82
D 8
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i RADI0 ACTIVE EFFLUENTS DOSE - NOBLE GASES I
LIMITING CONDITION FOR OPERATION i
}
3.11.2.2 The air dose due to noble gases released in gaseous effluents, from i
each reactor unit, to areas at and beyond the SITE BOUNDARY (see Figure 5.1-3) shall be limited to the following:
a.
During any calendar quarter:
Less than or equal to 5 mrads for gamma radiation and less than or equal to 10 mrads for beta radiation and, b.
During any calendar year:
Less than or equal to 10 mrads for gamma l
radiation and less than or equal to 20 mrads for beta radiation.
4 APPLICABILITY: At all times.
1 ACTION With the calculated air dose from radioactive noble gases in gaseous a.
effluents exceeding any of the above limits, in lieu of a Licensee I
Event Report, prepare and submit to the Commission within 30 days, pursuant to Specification 6.9.2, a Special Report that identifies the cause(s) for exceeding the limit (s) and defines the corrective actions that have been taken to reduce the releases and the proposed corrective actions to be taken to assure that subsequent releases will be in compliance with the above limits.
b.
The provisions of Specifications ~ 3.0.3 and 3.0.4 are not applicable.
)
SURVEILLANCE REQUIREMENTS i
4.11.2.2 Cumulative dose contributions for the current calendar quarter and current calendar year for noble gases shall be determined in accordance with the nethodology and parameters in the 00CM at least once per 31 days.
)
m ss e w i,
O BWR-STS-I PWR-STS-I 3/4 11-12 9/3/82
N RADIOACTIVE EFFLUENTS
- g449, DOSE - 10 DINE-131,(TRITIUM, AND RADIONUCLIDES IN PARTICULATE FORM LIMITING CONDITION FOR OPERATION imu.s-183 3.11.2.3 The dose to a MEMBER OF THE PUBLIC from iodine-131, all radionuclides in particulate form with half-lives greater, tritium, and than 8 days in gaseous effluents released, from each reactor unit, to areas at and beyond the SITE BOUNDARY (see Figure 5.1-3) shall be limited to the following:
s a.
During any calendar quarter:
Less than or equal to 7.5 mrems to any organ and, b.
During any calendar year:
Less than or equal to 15 mrems to any organ.
APPLICABILITY: At all times.
ACTION:
imss,e.* H, With the calculated dose from the release of iodine-131,, tritium, a.
and radionuclides in particulate form with half lives greater than 8 days, in gaseous effluents exceeding any of the above limits, in lieu of a Licensee Event Report, prepare and submit to the Commission within 30 days, pursuant to Specification 6.9.2, a Special Report that identifies the cause(s) for exceeding the limit and defines the corrective actions that have been taken to reduce the releases and l
the proposed corrective actions to be taken to assure that subvaquent releases will be in compliance with the above limits.
b.
The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.
SURVEILLANCE REQUIREMENTS ledi
- all, 4.11.2.3 Cumulative dose contributions for he current calcndar quarter and current calendar year for iodine-131,, ritium, and radionuclides in particulate form with half lives greater than 8 days shall be determined in accordance with the methodology and parameters in the 00CM at least once per 31 days.
BWR-STS-1 O
PWR-STS-I 3/4 11-13
'I 9/3/82 e
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1 RADI0 ACTIVE EFFLUENTS i
GASE0US RADWASTE TREATMENT I
LIMITING CONDITION FOR OPERATION i
3.11.2.4 The GASEOUS RADWASTE TREATMENT SYSTEM shall be in operation.
APPLICABILITY: Whenever the main condenser air ejector (evacuation) system is in operation.
ACTION:
a.
With gaseous radwaste from the main condenser air ejector system being discharged without treatment for more than 7 days in lieu of a Licensee Event Report, prepare and submit totbeCommissionwithin30 days,pursuanttoSpecification 6.9.2, a Special Report that includes the following information:
- 1. Identification of the inoperable equipment or subsystems and the reason for inoperability, i
i
- 2. Action (s) taken to restore the inoperable equipnent to OPERABLE status, and
- 3. Summary description of action (s) taken to prevent a recurrence.
b.
The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.
h.
3 SURVEILLANCE REQUIREMENTS i
/%
4.11.2.4 The readings cf the relevant l'nstruments shall be checked every 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> when the main condenser air ejector is in use to ensure that the gaseous radwaste treatment system is functioning.
L 1
3 am se a BWR-STS-1 3/4 11 14 3/12/82 l
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RADI0 ACTIVE EFFLUENTS 267 VENTILATION EXHAUST TREATMENT 7
I LIMITIM COPSITION FOR OPERATION
- 4 4
3.11.2.5 ff
- The VENTILA-yg.
..j.
TION EXHAUST TREATMENT SYSTEM shall be used to reduce radioactive materials in j.Q 0
gaseous waste prior to their 'ischarge when the projected doses nue to gaseous l!yn~
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effluent releases, from each reactor unit, to areas at and beyond the SITE
/.
BOUNDARY (see Figure 5. i.3-l) would exceed 0.3 mrem to any organ in a 31 day 4'
period.
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APPLICABILITY:
At all times other than when the VENTILATION EXHAUST TREATMENT
),(
system is undergiong routine maintenance.
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ACTION:
6" a
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=% r With gaseous waste being discharged without treatment and in excess
[.(
a.
n (a
of the above limits, in lieu of a Licensee Event Report, prepare and A. :
submit to the Commission within 30 days, pursuant to Specification 6.9.2, h.s a Special Report that includes the following information:
Q.<.
?b 1.
Explanation of why gaseous radwaste was being discharged without Q' i f treatment, identification of any inoperable equipment or LP
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subsystems, and the reason for the inoperability,
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2.
Action (s) taken to restore the inoperable equipment to OPERABLE 3.e s
status, and 1.y 3.
Sum:rary description of action (s) taken to prevent a recurrence.
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b.
The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.
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'N SURVEILLANCE REQUIREMENTS
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4.11.2.5.1 Doses due to gaseous releases from the site shall be projected at Wh least once per 31 days in accordance with the ODCM, a s
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RADIOACTIVE EFFLUENTS y
EXPLOSIVE GAS MIXTURE (Systems designed to withstand a hydrogen explosion)
Appropriate alternatives to the ACTIONS below can be accepted if they provide incentive for timely repair of monitors and for compliance with GDC 3 (Fire Protection).
2 LIMITING CONDITION FOR OPERATION
?L 3.11.2.6 The concentration of hydrogen or oxygen in the main condenser offgas treatment system shall be limited to less than or equal to 4% by volume.
[
APPLICABILITY:
At all times.
4 ACTION:
a.
With the concentration of hydrogen or oxygen in the main condenser
=
offgas treatment system exceeding the limit, restore the concentration to within the limit within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />.
3
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b.
With continuous monitors inoperable, utilize grab sampling procedures j
for a period not to exceed 30 days.
[
c.
The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.
=
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SURVEILLANCE REQUIREMENTS 4.11.2.6 The concentration of hydrogen or oxygen in the main condenser offgas treatment system shall be determined to be within the above limits by con-tinuously monitoring the waste gases in the main condenser offgas treatment systemnwith the hydrogen or oxygen monitors required OPERABLE by Table 3.3.7.12"1 of Specification 3.3.7.12.
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RADIOACTIVE EFFLUENTS EXPLOSIVE GAS MIXTURE (Systems not designed to withstand a hydrogen explosion)
Appropriate alternatives to the ACTIONS below can be accepted if they provide incentive for timely repair to monitors and for comliance with GDC 3 (Fire Protection).
LIMITING CONDITION FOR OPERATION 3.11.2.6A The concentration of hydrogen and/or oxygen in the main condenser offgas treatment system shall be limited to less than or equal to 2% by volume.
APPLICABILITY: At all times.
ACTION:
a.
With the concentration of hydrogen and/or oxygen in the main condenser offgas treatment system greater than 2% by volume but less than or equal to 4% by volume, restore the concentration of hydrogen and/or j
oxygen to within the limit within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />.
b.
With the concentration of hydrogen and/or oxygen in the main condenser offgas treatment system greater than 4% by volume, immediately suspend all additions of waste gases to the system and reduce the concentration of hydrogen and/or oxygen to less than or equal to 2%
within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />.
c.
With continuous monitors inoperable, utilize grab sampling precedures for a period not to exceed 30 days.
d.
The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.
j SURVEILLANCE REQUIREMENTS q
i 4.ll.2.6A The concentrations of hydrogen and/or oxygen in the main condenser offgas treatment system shall be determined to be within the above limits by 1
continuously monitoring the waste gases in the main condenser offgas treatment systentwith the hydrogen and/or oxygen monitors required OPERABLE by Table 3.3.7.12-1 of Specification 3.3.7.12.
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BWR-STS-I 3/4 11-18 3/12/82 T
USJ RADIOACTIVE EFFLUENTS MAIN CONDENSER LIMITING CONDITION FOR OPERATION 3.11.2.7 The gross radioactivity (beta and/or gamma) rate of noble gases
- measured at the main condenser air ejector shall be limited to less than or equal to 100 microcuries/sec per HW (after 30 minutes decay).
t APPLICABILITY: At all times.
ACTION:
With the gross radioactivity (beta and/or gamma) rate of noble gases at the main condenser air ejector exceeding 100 microcuries/sec per MW 30 minutes decay), restore the gross radioactivity rate to withib(after its limit within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or be in at least HOT STANDBY within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
SURVEILLANCE REQUIREMENTS 4.11.2.7.1 The radioactivity rate of noble gases at (near) the outlet of the main condenser air ejector shall be continuously monitored in accordance with Specification 3.3.7.12.
4.11.2.7.2 The gross radioactivity (beta and/or gamma) rate of noble gases
- from the main condenser air ejector shall be determined to be within the limits of Specification 3.11.2.7 at the following frequencies by performing an isotopic analysis of a representative sample of gases taken at the discharge (prior to dilution and/or discharge) of the main condenser air ejector:
a.
At least once per 31 days.
b.
Within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> following an increase, as indicated by the Condenser Air Ejector Noble Gas Activity Monitor, of greater than 50%, after factoring out increases due'to changes in THERMAL POWER level, in the nominal steady state fission gas release from the primary coolant.
Plants using gamma scintillation detector (s) to measure the Kr-85m, 87, 88 and Xe-133, 135, 138 contribution after 30 minutes decay may substitute the words
" release rate of the sum of the activities from the noble gases" for the words
" gross radioactivity rate of noble gases" in this specification.
BWR-STS-I 3/4 11-19 3/12/82
- / -
-- ---.i
N blb]?$
RADI0 ACTIVE EFFLUENTS MARK I or II CONTAINMENT LIMITING CONDITION FOR OPERATION 3.11.2.8 VENTING or PURGING of the Mark I or II containment drywell shall be i
through the Standby Gas Treatment System.
APPLICABILITY: Whenever the drywell is vented or purged.
ACTION:
With the requirements of the above specification not satisfied, a.
suspend all VENTING and PURGING of the drywell.
b.
The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.
l SURVEILLANCE REQUIRMENTS 4.11.2.8 The containment drywell shall be determined to be aligned for VENTING or PURGING through the Standby Gas Treatment System within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> prior to start of and at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> during VENTING or PURGING of the drywell.
t I
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l-BWR-STS-I 3/4 11-20 3/12/82
bbN RADI0 ACTIVE EFFLUENTS 3/4.11.3 SOLID RADIOACTIVE WASTE LIMITING CONDITION FOR OPERATION 3.11.3 The solid radwaste system shall be used in accordance with a PROCESS CONTROL PROGRAM to process wet radioactive wastes to meet shipping and burial ground requirements.
APPLICABILITY:
At all times.
l ACTION:
With the provisions of the PROCESS CONTROL PROGRAM not satisfied, a.
suspend shipments of defectively processed or defectively packagad solid radioactive wastes from the site.
b.
The provisions of Specifications 3.0.3, 3.0.4, and 6.9.1.9.b are not applicable.
SURVEILLANCE REQUIREMENTS 4.11.3 THE PROCESS CONTROL PROGRAM shall be used to verify the SOLIDIFICATION of at least one representative test specimen from at least every tenth batch of each type of wet radice:tive waste (e.g., filter sludges, spenc resins, evaporator bottoms, boric acid solutions, and sodium sulfate solutions).
If any test specimen fails to verify SOLIDIFICATION, the SOLIDIFICATION a.
of the batch under test shall be suspended until such time as addi-tional test specimens can be obtained, alternative SOLIDIFICATION parameters can be determined in accordance with the PROCESS CONTROL PROGRAM, and a subsequent test verifies SOLIDIFICATION.
SOLIDIFI-CATION of the batch may then be resumed using the alternative SOLIDIFICATI0d parameters determined by the PROCESS CONTROL PROGRAM.
b.
If the initial test specimen from a batch of waste fails to verify SOLIDIFICATION, the PROCESS CONTROL PROGRAM shall provide for the collection and testing of representative test specimens from each consecutive batch of the same type of wet waste until at least 3 consecutive initial test specimens demonstrate SOLIDIFICATION.
The PROCESS CONTROL PROGRAM shall be modified as required, as provided in Specification 6.13, to assure SOLIDIFICATION of subsequent batches of waste.
BWR-STS-I PWR-STS-I 3/4 11-19 9/3/82
m.. -
$iblAN RADI0 ACTIVE EFFLUENTS 3/4.11.4 TOTAL DOSE LIMITING CONDITION FOR OPERATION 3.11.4 The annual (calendar year) dose or dose commitment to any MEMBER OF THE PUBLIC due to releases of radioactivity and to radiation from uranium fuel cycle sources shall be limited to less than or equal to 25 mrems to the total body or any organ, except the thyroid, which shall be limited to less than or equal to 75 mrems.
APPLICABILITY: At all times.
ACTION:
With the calculated doses from the release of radioactive materials a.
in liquid or gaseous effluents exceeding twice the limits of Specifica-tion 3.11.1.2.a. 3.11.1.2.b, 3.11.2.2.a, 3.11.2.2.b, 3.11.2.3.a. or 3.11.2.3.b, calculations should be made including direct radiation contributions from the reactor units and from outside storage tanks to determine whether the above limits of Specification 3.11.4 have been exceeded.
If such is the case in lieu of a Licensee Event Report, prepare and submit to the Commission within 30 days, pursuant to Specification 6.9.2, a Special Report that defines the corrective action to be taken to reduce subsequent releases to prevent recur-rence of exceeding the above limits and includes the schedule for achieving conformance with the above limits. This Special Report, as defined in 10 CFR Part 20.405c, shall include an analysis that estimates the radiation exposure (dose) to a MEMBER OF THE PUBLIC from uranium fuel cycle sources, including all effluent pathways and direct radiation, for the calendar year that includes the release (s) covered by this report.
It shall also describe levels of radiation and concentrations of radioactive material involved, and the cause of the exposure levels or concentrations.
If the estimated dose (s) exceeds the above limits, and if the release condition resulting in violation of 40 CFR Part 190 has not already been corrected, the Special Report shall include a request for a variance in accordance with the provisions of 40 CFR Part 190.
Submittal of the report is considered a timely request, and a variance is granted until staff acticn on the request is complete.
b.
The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.
SURVEILLANCE REQUIREMENTS 4.11.4.1 Cumulative dose contributions from liquid and gaseous effluents shall be determined in accordance with Specifications.4,_11.1.2, 4.11.2.2, and 4.11.2.3, and in accordance with the methodology and parameters in the 00CM.
4.11.4.2 Cumulative dose contributions from direct radiation from the reactor units and from radwaste storage tanks shall be determined in accordance with the methodology and parameters in the ODCM.
This requirement is applicable only under conditions set forth in Specification 3.11.4.a.
BWR-STS-I PWR-STS-I 3/4 11-20 9/3/82
~
4.
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 conducted as specified in Table 3.12-1.
APPLICABILITY: At all times.
ACTION:
With the radiological environmental monitoring program not being a.
h conducted as specified in Table 3.12-1, in lieu of a Licensee Event Report, prepare and submit to the Commission, in the Annual Radio-
' e logical Environmental Operating Report required by Specification 6.9.1.11, a description of the reasons for not conducting the program as required and the plans for preventing a recurrence.
b.
With the level of radioactivity as the result of plant effluents in an environmental sampling medium at a specified location exceeding the reporting levels of Table 3.12-2 when averaged over any calendar quarter, in lieu of a Licensee Event Report, prepare and submit to the Commission within 30 days, pursuant to Specification 6.9.2, a Special Report that identifies the cause(s) for exceeding the limit (s) and defines th2 corrective actions to be taken to reduce radioactive effluents so that the potential annual dose
- to A MEMBER OF THE PUBLIC is less than the calendar year limits of Specifications 3.11.1.2,
~1 3.11.2.2, and 3.11.2.3.
When more than one of the radionuclides in Table 3.12-2 are detected in the sampling medium, this report shall be submitted if:
concentration (1) concentration (2)
+ ***> 1.0 reporting level (1) reporting level (2)
When radionuclides other than those in Table 3.12-2 are detected and are the result of plant effluents, this report shall be submitted if the potential annual dose
- to A MEMBER OF THE PUBLIC is equal to or greater than the calendar year limits of Specifications 3.11.1.2, 3.11.2.2 and 3.11.2.3.
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.
With milk or fresh leafy vegetable samples unavailable from one or c.
more of the sample locations required-by Table 3.12-1, identify locations for obtaining replacement samples and add them to the radio-logical environmental monitoring program within 30 days. The specific-
- The methodology and parameters used to estimate the potential annual dose to a MEMBER OF THE PUBLIC shall be indicated in this report.
~
BWR-STS-I PWR-STS-I 3/4 12-1 9/3/82
,s T
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$YW RADIOLOGICAL ENVIRONMENTAL MONITORING locations from which samples were unavailable may then be deleted from the monitoring program.
In lieu of a Licensee Event Report and pursuant to Specification 6.9.1.12, identify the cause of the unavail-l ability of samples and identify the new location (s) for obtaining replacement samples in the next Semiannual Radioactive Effluent Release Report and also include in the report a revised figure (s) and table for the ODCM reflecting the new location (s),
d.
The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.
SURVEILLANCE REQUIREMENTS 4.12.1 The radiological environmental monitoring samples shall be collected pursuant to Table 3.12-1 from the specific locations given in the table and figure (s) in the ODCM, and shall be analyzed pursuant to the requirements of Table 3.12-1 and the detection capabilities required by Table 4.12-1.
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BWR-STS-I' PWR-STS-I 3/4-12-2 9/3/82
O t
2 jE TABLE 3.12-1
??
Ej El RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM *
.Y T 4
-4 Number of Representative Exposure Pathway Samp1 s and Sampling and Type and frequency 9
and/or Sample Sample Locations
- Collection Frequency of Analysis l
1.
DIRECT RADIATION 40 routine monitoring stations Quarterly Gamma dose quarterly.
(DR1-DR40) either with two or i
more dosimeters or with one instrument for measuring and recording dose rate continuously, placed as follows:
an inner ring of stations, one in each meteorological sector in the u,
3 general area of the SITE BOUNDARY g
(DR1-DR16);
i an outer ring of stations, one in each meteorological sector in j
the 6-to 8-km range from the site (DR17-DR32);
2 the balance of the stations (DR33-DR40) to be placed in special interest areas such I
as population centers, nearby residences, schools, and in 1 or 2 areas to serve as control stations.
R t'
- The number, media, frequency, and location of samples may vary from site to site This table presents an 2
acceptable minimum program for a site at which each entry is applicable.
Local site characteristics must be examined to determine if pathways not covered by this table may significantly contribute to an EED individual's dose and should be included in the sampling program. The code letters in parentheses, e.g.
Es9 DR1, A1, provide one way of defining generic sample locations in this specification that can be used to
(('
identify the specific locations in the map (s) and table in the ODCH.
c=d
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i l
t TABLE 3.12-1 (Continued) gg RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Ea Number of dd Representative 44 Exposure Pathway Samples and Sampling and Type and Frequency and/or Sample Sample Locations' Collection Frequency of Analysis 2.
AIRBORNE Radiciodine and Samples from 5 locations (Al-AS):
Continuous sampler Radiciodine Cannister:
Particulates operation with sample I-131 analysis weekly.
3 samples (Al-A3) from close collection weekly, or to the 3 SITE BOUNDARY locations, more frequently if l
in different sectors, of the required by dust Particulate Sampler i
highest calculated annual average loading.
Gross beta radioactivity i
l groundlevel D/Q.
analysisfolloging filter change; I sample (A4) from the vicinity Gamma isotopic analysis' of a community having the highest of composite (by calculated annual average ground-location) quarterly.
w 1
level D/Q.
M 1 sample (AS) from a control 4
location, as for example 15-30 km distant and in the ast preva-lent wind direction 3.
WATERBORNE Surface #
1 sample upstream (Wal)
Compositesampfeover Gamma isotopic analysis' a.
I sample downstream (Wa2) 1-month period monthly.
Composite for tritium analysis quarterly.
b.
Ground Samples from 1 or 2 sources Quarterly Gamma isotopic
- and tritium (Wbl,Wbg),onlyiflikelytobe analysis quarterly.
affected e
c.
Drinking I sample of each of 1 to 3 (Wcl -
Composite sample I-131 analysis on each D
Wc3) of the nearest water over 2-week period composite when the dose 9
D supplies that could be when I-131 analysis calculated for the consump-affected by its discharge.
is performed, monthly tion of the water is composite otherwise than 1 arem per year. greater Com-EE9 1 sample from a control positeforgrossbetaagd h
location (Wc4).
gamma isotopic analyses monthly.
Composite for tritim analysis quarterly, i
TABLE 3.12-1 (Continued)
.7 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM o
N$
m m 44 Number of Representative Exposure Pathway Samples and Sampling and Type and Frequency a
and/or Sample Sample Locations Collection Frequency of Analysis d.
Sediment I sample from downstream area Semiannually Gamma isotopic analysis' from with existing or potential semiannually.
shoreline recreational value (Wdl).
4.
INGESTION
- a. ' Milk Samples from milking animals Semimonthly when Gamma isotopic
- and I-131 in 3 locations (Ia1 - Ia3) within animals are on analysis seminenthly when 5 km distance having the highest pasture, monthly at animals are on pasture; dose potential.
If there are other times monthly at other times.
none, then, 1 sample from milking if animals in each of 3 areas (Ia1 -
Ia3) between 5 to 8 km distant M
where doses are calculated to be j
J, greater than 1 arem per yr 1 sample from milking animals at a control location (Ia4),
)
i 15-30 km distant and in the least prevalent wind direction.
b.
Fish and 1 sample of each commercially Sample in season, or Gamma isotopic analysis' Inverte-and recreationally important semiannually if they on edible portions, brates species in vicinity of plant are not seasonal discharge area.
(Ib1 - Ib_ ).
I sample of same species in areas not influenced by plant dis-R charge (Ib10 - Ib_).
s" J
Gamma isotopic analyses
- c.
Food 1 sample of each principal class At time of harvest N
Products of food products from any area on edible portion.
that is irrigated by water in g
which liquid plant wastes have eg,j been discharged (Ic1 - Ic
).
E.
I 2E TABLE 3.12-1 (Continued) 7T RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM TT Number of Representative Exposure Pathway Samples and Sampling and Type and Frequency and/or Sample Sample Locations
- Collection Frequency
.f Analysis c.
Food Samples of 3 different kinds Monthly when Gamma isotopic
- and I-131 Products of broad leaf vegetation grown available analysis.
(cont'd) nearest each of two different i
offsite locations of highest predicted annual average ground-level D/Q if milk sampling is not performed (Ic10 - Ic13).
I sample of each of the similar Monthly when Gamma isotopic" and I-131 w) broad leaf vegetation grown available analysis.
15-30 km distant in the least prevalent wind direction if. milk sampling is not performed (Ic20 - Ic23).
l
$R R
e n
l 25 7UU TABLE 3.12-1 (Continued)
L 4' T TABLE NOIATION
" Specific parameters of distance and direction sector from the centerline of one reactor, and additional description where pertinent, shall be provided for each and every sample location in Table 3.12-1 in a table and figure (s) in the ODCM.
Refer to NUREG-0133, " Preparation of Radiological Effluent Technical Specifications for Nuclear Power Plants," October 1978, and to Radiclogical Assessment Branch Technical Position, Revision 1 November 1979. Deviations are permitted from the required sampling schedule if specimens are unobtainable due to hazardous conditions, seasonal unavailability, malfunction of automatic sampling equipment and other legitimate reasons.
If specimens are unobtainable due to sampling equipment malfunction, every effort shall be made to complete corrective action prior to the end of the next sampling period. All deviations from the sampling schedule shall be documented in the Annual Radiological Environ-menta) Operating Report pursuant to Specification 6.9.1.11.
It is recognized that, at times, it may not be possible or practicable to continue to obtain samples of the media of choice at the most desired location or time.
In these instances suitable alternative media and locations may be chosen for the particular pathway in question and appropriate substitutions made within 30 days in the radiological environmental w) monitoring program.
In lieu of a Licensee Event Report and pursuant to Specification 6.9.1.12, identify g
the cause of the unavailability of samples for that pathway and identify the new location (s) for obtaining replacemept samples in the next Semiannual Radioactive Effluent Release Report and also include in the report a revised figure (s) and table for the ODCM reflecting the new location (s).
b one or more instruments, such as a pressurized ion chamber, for measuring and recording dose rate continucusly may be used in place of, or in addition to, integrating dosimeters.
For the purposes of this table, a thermoluminescent dosimeter (TLD) is considered to be one phosphor; two or more phosphors in a packet are considered as two or more dosimeters.
Film badges shall not be used as dosimeters for measuring direct radiation. The 40 stations is not an absolute number.
The number of direct radiation monitoring stations may be reduced according to geographical limitations; e.g., at an ocean site, some sectors will be over water so that the number of dosimeters may be reduced accordingly.
The freqency of analysis or readout for TLD systems will depend upon the characteristics of the specific system used and should be selected to obtain optimum dose information with minimal fading.
C R
The purpose of this sample is to obtain background information.
If it is not practical to establish t'
control locations in accordance with the distance and wind direction criteria, other sites that provide 2
valid background data may be substituted.
Esl Ea
TABLE 3.12-1 (Continued)
{y TABLE NOTATION d
Airborne particulate sample filters shall be analyzed for gross beta radioactivity 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or more after sampling to allow for radon and thoron daughter decay.
If gross beta activity in air particulate samples is greater than ten times the yearly mean of control samples, gamma isotopic analysis shall be performed on the individual samples.
' Gamma isotopic analysis means the identification and quantification of gamma-emitting radionuclides that may be attributable to the effluents from the facility.
IThe " upstream sample" shall be taken at a distance beyond significant. influence of the discharge. The
" downstream" sample shall be taken in an area beyond but near the mixing zone.
" Upstream" samples in an estuary must be taken far enough upstream to be beyond the plant influence.
Salt water shall be sampled only when the receiving water is utilized for recreational activities.
UA composite sample is one in which the quantity (aliquot) of liquid sampled is proportional to the quantity R
of flowing liquid end in which the method of sampling employed results in a specimen that is representative of the liquid flow.
In this program composite sample aliquots shall be collected at time intervals that are M
very short (e.g., hourly) relative to the compositing period (e.g., monthly) in order to assure obtaining e's a representative sample.
Groundwater samples shall be taken when this source is tapped for drinking or irrigation purposes in areas where the; hydraulic gradient or recharge properties are suitable for contamination.
IThe dose shall be calculated for the maximum organ and age group, using the methodology and parameters in the 00CM.
3If harvest occurs more than once a year, sampling shall be performed during each discrete harvest.
If harvest occurs continuously, sampling shall be monthly. Attention shall be paid to including samples of tuborous and root food products.
R R-2 EsM s%
o o
1 gE TABLE 3.12-2
.?
REPORTING LEVELS FOR RADIOACTIVITY CONCENTRATIONS IN ENVIRONMENTAL SAMPLES TT Reporting Levels i
Water Airborne Particulate Fish Milk Food Products 3
Analysis (pC1/1) or Gases (pCi/m )
(pCi/kg, wet)
(pCi/1)
(pCi/kg, wet)
H-3 20,000*
Mn-54 1,000 30,000 i
Fe-59 400 10,000 Co-58 1,000 30,000 l
l il'.
Co-60 300 10,000 g
Zn-65 300 20,000 E
I Zr-Nb-95 400 I-131 2
0.9 3
100 Cs-134 30 10 1,000 60 1,000 Cs-137 50 20 2,000 70 2,000 Ba-La-140 200 300
- For drinking water samples.
This is 40 CFR Part 141 value.
If no drinking water pathway exists, a
)
value of 30,000 pC1/2 may be used.
.Ds
~
b E
s..
0 h
g jE TABLE 4.12-1 bh,v, DETECTION CAPABILITIES FOR ENVIRONMENTAL SAMPLE ANALYSIS" u
LDWER LIMIT OF DETECTION (LLD)b,c Water Airborne Particulate Fish Milk Food Products Sediment Analysis (pCi/1) or Gas (pCi/m )
(pCi/kg, wet)
(pCi/2)
(pCi/kg, wet)
(pCi/kg dry) 8 gross beta 4
0.01 H-3 2000*
Mn-54 15 130 Fe-59 30 260 Co-58,60 15 130 w)
Zn-65 30 260 g
7 i
Ej Zr-Nb-95 15 d
{
I-131 I
0.07 1
60 Cs-134 15 0.05 130 15 60 150 Cs-137 18 0.06 150 18 80 180 Ba-La-140 15 15
- If no drinking water pathway exists, a value of 3000 pCi/l may be used.
m 5
b5S as E'
s LS c
Mb TABLE 4.12-1 (Continued)
TABLE NOTATION
'This list does not mean that only these nuclides are to be considered.
Other peaks that are identifiable, together with those of the above nuclides, shall also be analyzed and reported in the Annual Radiological Environmental Operating Report pursuant to 5pecification 6.9.1.11.
bRequired detection capabilities for thermoluminescent dosimeters used for environmental measurements are given in Regulatory Guide 4.13.
cThe LLD is defined, for purposes of these specifications, as the smallest concentration of radioactive material in a sample that will yield a net count, above system background, that will be detected with 95% probability with only 5% probability of falsely concluding that a blank observation represents a "real" signal.
For a particular measurement system, which may include radiochemical separation:
4' 8 b LLD =
E V
2.22 Y
exp(-AAt) l Where:
LLD is the "a priori" lower limit of detection as defined above, as picocuries per unit mass or volume, u is the standard deviation of the background counting rate or of s
tMe counting rate of a blank sample as appropriate, as counts per
- minute, E is the counting efficiency, as counts per disintegration, V is the sample size in units of mass or volume, l
2.22 is the number of disintegrations per minute per picocurie, Y is the fractional radiochemical yield, when applicable, A is the radioactive decay constant for the particular radionuclide, and At for environmental' samples is the elapsed time between sample collection, or and of the sample collection period, and time of counting Typical values of E, V, Y, and at should be used in the calculation.
BWR-STS-1 PWR-STS-I 3/4 12-11 9/3/82
~
b E
TABLE 4.12-1 (Continued)
TABLE NOTATION It should be recognized that the LLD is defined as an a priori (before the fact) limit representing the capability of a measurement system and not as an a posteriori (after the fact) limit for a particular measurement.
Analyses shall be performed in such a manner that the stated LLDs will be achieved under routine conditions. Occasionally background fluctuations,
~
unavoidable small sample sizes, the presence of interfering nuclides, or other uncontrollable circumstances may render these LLDs unachievable.
In such cases, the contributing factors shall be identified and described in the Annual Radiological Environmental Operating Report pursuant to Specification 6.9.1.11.
dLLD for drinking water samples.
If no drinking water pathway exists, the LLD of gamma isotopic analysis may be used.
S h
eggM BWR-STS-I C
PWR-STS-I 3/4 12-12 9/3/82
UuJb[i[
RADIOLOGICAL ENVIRONMENTAL MONITORING b
3/4.12.2 LAND USE CENSUS LIMITING CONDITION FOR OPERATION 3.12.2 A land use census shall be conducted and shall identify within a distance of 8 km (5 miles) t:1e location in each of the 16 meteorological sectors of the nearest milk animal, the nearest residence and the nearest garden
- of greater than 50 m2 (500 ft2) producing broad leaf vegetatica.
(For elevated releases as defined in Regulatory Guide 1.111, Revision 1, July 1977, the land use census shall also identify within a distance of 5 km (3 miles) the locations in each of the 16 meteorological sectors of all milk animals and j
all gardens of greater than 50 m2 producing broad leaf vegetation.)
APPLICABILITY: At all times.
ACTION:
~
With a land use census identifying a location (s) that yields a calcu-a.
lated dose or dose commitment greater than the values currently being calculated in Specification 4.11.2.3, in lieu of a Licensee Event Report, identify the new location (s) in the next Semiannual Radioactive Effluent j
Release Report, pursuant to Specification 6.9.1.12.
b.
With a land use census identifying a location (s) that yields a calculated dose or dose commitment (via the same exposure pathway) 20 percent greater than at a location from which samples are cur-rently being obtained in accordance with Specification 3.12.1, add the new location (s) to the radiological environmental monitoring program within 30 days. The sampling location (s), excluding the control station location, having the icwest calculated dose or dose commitment (s), via the same exposure pathway, may be de!ated from this monitoring program after (October 31) of the year in which this land use <ensus was conducted.
In lieu of a Licensee Event Report t
and pursuant to Specification 6.9.1.12, identify the new location (s) in the next Semiannual Radioactive Effluent Release Report and also include in the report a revised figure (s) and table for the ODCM reflecting the new location (s).
The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.
c.
6 SURVEILLANCE REQUIREMENTS 4.12.2 The land use census shall be conducted during the growing season at least once per 12 months using that information that will provide the best results, such as by a door-to-door survey, aerial survey, or by consulting local agriculture authorities. The results of the land use census shall be included in the Annual Radiological Environmental Operating Report pursuant to Specification 6.9.1.11.
[
- Broad leaf vegetation sampling of at least three different kinds of vegetation may be yarformed at the site boundary in each of two different direction sectors A
with th a highest predicted D/Qs in lieu of the garden census.
Specifications for brtad leaf vegetation sampling in Table 3.12-1.4c shall be followed, including analysis of control samples.
BWR-STS-I PWR-STS-I 3/4 12-13 9/3/82
LOM AT RADIOLOGICAL ENVIRONMENTAL MONITORING 3/4.12.3 INTERLABORATORY COMPARISON PROGRAM LIMITING CONDITION FOR OPERATION 3.12.3 Analyses shall be performed on radioactive materials supplied as part of an Interlaboratory Comparison Program that has been approved by the Commission.
i APPLICABILITY: At all times.
ACTION:
With analyses not being performed as required above, report the a.
corrective actions taken to prevent a recurrence to the Commission in the Annual Radiological Environmental Operating Report pursuant to Specification 6.9.1.11.
b.
The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.
l SURVEILLANCE REQUIREMENTS 4.12.3 The Interlaboratory Comparison Program shall be described in the 00CM.
A summary of the results obtained as part of the above required Interlaboratory Comparison Program shall be included in the Annual Radiological Environmental Operating Report pursuant to Specification 6.9.1.11.
C BWR-STS-I PWR-STS-I 3/4 12-14 9/3/82
b$!b[$
INSTRUMENTATION BASES 3/4.3.3.10 RADI0 ACTIVE LIQUID EFFLUENT MONITORING 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 and adjusted in accordance with the methodology and parameters in the ODCM to ensure that the alarm / trip will occur prior to exceeding the limits of 10 CFR 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.
The purpose of tank level indicating devices is to assure the detection and control of leaks that if not controlled could potentially result in the transport of radioactive materials to UNRESTRICTED AREAS.
3/4.3.3.11 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION 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 and adjusted in accordance with the methodology and parameters in the ODCM to ensure that the alarm / trip will occur prior to exceeding the limits of 10 CFR Part 20.
This instrumentation also includes provisions for monitoring (and controlling) the concentrations of potentially explosive gas mixtures in the waste gas holdup 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.
h me e em BWR-STS-1 9
PWR-STS-I 8 3/4 3-5 9/3/82
.ansammmamuunnnummmmmmam bN 3/4.11 RADIOACTIVE EFFLUENTS BASES 3/4.11.1 LIQUID EFFLUENTS 3/4.11.1.1 CONCENTRATION This specification is provided to ensure that the concentration of radioactive materials released in liquid waste effluents to UNRESTRICTED AREAS will be less than the concentration levels specified in 10 CFR Part 20, Appen-dix B, Table II, Column 2.
This limitation provides additional assurance that the levels of radioactive materials in bodies of water in UNRESTRICTED AREAS will result in exposures within (1) the Section II. A design objectives of Appen-dix 1, 10 CFR Part 50, to a MEMBER OF THE PUBLIC and (2) the limits of 10 CFR Part 20.106(e) to the population.
The concentration limit for dissolved or entrained noble gases is based upon the assumption that Xe-135 is the control-ling radioisotope and its MPC in air (submersion) was converted to an equivalent concentration in water using the methods described in International Commission on Radiological Protection (ICRP) Pubitcation 2.
This specification applies to the release of liquid effluents from all reactors at the site.
The required detection capabilities for radioactive materials in liquid waste samples are tabulated in terms of the lower limits of detection (LLDs).
1 Detailed discussion of the LLD, and other detection limits can be found in HASL Procedures Manual, HASL-300 (revised annually), Currie, L. A., " Limits
^
for Qualitative Detection and Quantitative Determination - Application to Radiochemistry," Anal. Chem. 40, 586-93 (1968), and Hartwell, J. K., " Detection Limits for Radioanalytical Counting Techniques," Atlantic Richfield Hanford Company Report APH-SA-215 (June 1975).
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 IV. A of Appen-dix I to assure that the releases of radioactive material in liquid effluents to UNRESTRICTED AREAS will be kept "as low as is reasonably achievable."
- Also, for fresh water sites with drinking water supplies that can be potentially affected by plant operations, there is reasonable 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 Part 141. The dose calculation methodology and parameters-in the-0DCM implement the require-ments in Section III. A of Appendix I that conformance with the guides of
. I Appendix I be shown by calculational proceoures based on models and data, such that the actual exposure of a MEMBER OF THE PUBLIC through appropriate pathways is unlikely to be substantially underestimated.
The equations specified in the 00CM for calculating the doses due to the actual release rates of radioactive materials in liquid effluants are consistent with the methodology provided in BWR-STS-I PWR-STS-I B 3/4 11-1 9/3/82
DMR RADIOACTIVE EFFLUENTS BASES 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 1," 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.
This specification applies to the release of ifquid effluents from each reactor at the site.
7ne units with shared radwaste treatment systems, the liquid effluents from the shared system are proportioned among the units sharing that system.
3/4.11.1.3 LIQUID RADWASTE TREATMENT SYSTEM The requirement that the appropriate portions of this system be used, when specified, provides assurance that the releases of radioactive materials in ifquid effluents will be kept "as low as is reasonably achievable".
This specification implements the requirements of 10 CFR Part 50.36a, General Design Criterion 60 of Appendix A to 10 CFR Part 50 and the design objective given in Section II.D of Appendix I to 10 CFR Part 50.
The specified ifmits governing the use of appropriate portions of the liquid radwaste treatment system were specified as a suitable fraction of the dose design objectives set forth in Section II.A of Appendix I,10 CFR Part 50, for liquid effluents.
This specification applies to the release of liquid effluents from each reactor at the site.
For units with shared radwaste treatment systems, the liquid effluents from the shared system are proportioned among the units sharing that system.
3/4.11.1.4 LIOUID HOLDUP TANKS The tanks listed in this Specification include all those outdoor tanks that are not surrounded by liners, dikes, or walls capable of holding the tank contents and that do not have tank overflows and surrounding area drains connected to the liquid radwaste treatment system.
Restricting the quantity of radioactive material contained in the specified tanks provides assurance that in the event of an uncontrolled release of the tanks' contents, the resulting concentrations would be less than the limits of 10 CFR Pcrt 20, Appendix B, Table II, Column 2, at the nearest potable water supply and the nearest surface water supply in an UNRESTRICTED AREA.
3/4.11.2 GASEOUS EFFLUENTS 3/4.11.2.1 DOSE RATE This specification is provided to ensure that the dose'at any time at and beyond the SITE BOUNDARY from gaseous effluents from all units on the site will be within the annual dose limits of 10 CFR Part 20 to UNRESTRICTED AREAS.
The annual dose limits are the doses' associated with the concentrations of 10 CFR Part 20, Appendix B, Table II, Column 1.
These limits provide reasonable BWR-STS-I PWR-STS-I B 3/4 11-2 9/3/82
b RADI0 ACTIVE EFFLUENTS BASES
- )
assurance that radioactive material discharged in gaseous effluents will not result in the exposure of a MEMBER OF THE PUBLIC in an UNRESTRICTED AREA, either within or outside the SITE 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 MEMBERS OF THE PUBLIC who may at times be within the SITE BOUNDARY, the occupancy of that MEMBER OF THE PUBLIC will usually be 7 i sufficiently low to compensate for any increase in the atmospheric diffusion factor above that for the SITE BOUNDARY.
Examples of calculations for such MEMBERS OF THE PUBLIC, with the appropriate occupancy factors, snall be given in the ODCM.
The specified release rate limits restrict, at all times, the corresponding gamma and beta dose rates above background to a MEMBER OF THE PUBLIC at or beyond the SITE BOUNDARY to less than or equal to 500 mrems/ year to the total 'oody or to less than or equal to 3000 mrems/ year to the skin.
These release rate limits also restrict, at all times, the corresponding thyroid dose rate above background to a child via the inhalation pathway to
~
less than or equal to 1500 mrems/ year.
This specification applies to the release of gaseous effluents from all
~
reactors at the site.
The required detection capabilities for radioactive materials in gaseous waste samples are tabulated in terms of the lower limits of detection (LL0s).
Detailed discussion of the LLO, and other detection limits can be found in HASL Procedures Manual, HASL-300 (revised annually), Currie, L.
A., " Limits for Qualitative Detection and Quantitative Determination - Application to Radio-chemistry," Anal. Chem. 40, 586-93 (1968), and Hartwell, J.
K., " Detection a
Limits for Radioanalytical Counting Techniques," Atlantic Richfield Hanford Company Report ARH-SA-215 (June 1975).
3/4.11.2.2 DOSE - NOBLE GASES 2
This specification is provided to implement the requirements of Sections II.8, 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.B 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 Appendix I to assure that the releases of radioactive material in gareous effluents to UNRESTRICTED AREAS will be kept "as low as is reasonably achievable."
The Sur-veillarce Requirements implement the requi ements in Section III.A of Appendix I that conformance with the guides of Appendix I be shewn by calculational proce-
.y dures based on models and data such that the actual exposure of a MEMBER OF THE PUBLIC through appropriate pathways is unlikely to be substantially under-estimated.
The dose calculation methodology and parameters established in the 3
00CM for calculating the doses due to the actual release rates of radioactive noble gases in gaseous effluents are 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 Effluents in Routine Releases from Light-Water Cooled Reactors," Revision 1, July 1977.
BwR-STS-I i
PWR-STS-I B 3/4 11-3 9/3/82
~
~
RADIOACTIVE EFFLUENTS BASES The ODCM equations provided for determining the air doses at and beyond the SITE BOUNDARY are based upon the historical average atmospheric conditions.
This specification applies to the release of gaseous effluents from each reactor at the site.
For units with shared radwaste treatment systems, the gaseous affluents from the shared system are proportioned among the units sharing that system.
gg, 3/4.11.2.3 DOSE - IODINE-131, TRITIUM, AND RADIONUCLIOES IN PARTICULATE FORM 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 Appendix I to assure that the releases of radioactive materials in gaseous effluents to UNRESTRICTED i
AREAS will be kept "as low as is reasonably achievable." The ODCM calculational methods specified in the Surveillance 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 a MEMBER OF THE PUBLIC through appropriate pathways is I
unlikely to be substantially underestimated.
The ODCM calculational methodology and parameters for calculating the doses due to the actual release rates of j
the subject materials are consistent with the methodology provided in Regulatory Guide 1.109, " Calculation of Annual Doses to Man from Routine Releases of Reactor Effluent. 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 Effluents in Routine Releases from Light-Water-Cooled Reactors," Revision 1, July 1977.
These equa-tions also provide for determining the actual doses based upon the historical average atmospheric conditions.
tritium, and radionuclides in particulate form with half lives greater thanThe rel j
8 days are dependent upon the existing radionuclide pathways to man, in the-i areas at and beyond the SITE BOUNDARY. The pathways that were examined in the development of these calculations were:
- 1) individual inhalation of airborne radionuclides, 2) deposition of radionuclides onto green leafy vegetation with subsequent consumption by man, 3) deposition ont.o grassy areas where milk animals and meat producing animals graze with consumption of the milk and meat by man, and 4) deposition on the ground with subsequent exposure of man.
This specification applies to the release of gaseous effluents from each reactor at the site. For units with shared radwaste treatment systems, the gaseous effluents from the shared system are proportioned among the units sharing that system.
3/4.11.2.4 AND 3/4.11.2.5 GASE0US RADWASTE TREATMENT AND VENTILATION EXHAUST TREATMENT The OPERABILITY of the GASEOUS RADWASTE TREATMENT SYSTEM and the VENTILATION EX,HAUST TREATMENT SYSTEM ensures that the systems will be available 1
BWR-STS-I PWR-STS-I 8 3/4 11-4 9/3/82
'* rs'
%l~.. Y.; M. b b ' j.J....
J O ?.l l
- W h, ? Y.l V A (; N. N Y b : b'N 5e 7 2. ) r.% +, M.
- . v ^ < w r
r g
% ;.. ~.
. [f,
Au RADI0 ACTIVE ErFLUENTS
- q Q.]
,. ~...
BASES
. g 4.. :
for use whenever gaseous effluents require treatment prior to release to the
.., ? ' s
..v..
environment.
The requirement that the appropriate portiocs of these systems R O.
3 be used, when specified, provides reasonable assurance that the releases of
@ s'
,y radioactive materials in gaseous effluents will be kept "as low as is reasonably achievable" This specification implements the requirements of 10 CFR j gi.
V l
Part 50.'16a, General Design Criterion 60 of Appendix A to 10 CFR Part 50, and S. 's the design objectives given in Section II.D of Appendix I to 10 CFR Part 50.
"y 9 The specified limits governing the use of appropriate portions of the systems were specified as a suitable fraction of the dose design objectives set forth Q..-
t
-Q ' '
y in Sections 11.8 and II.C of Appendix I, 10 CFR Part 30, for gaseous effluents.
. D.h
.-y gl' r
g.
3/4.11.2.5 EXPLOSIVE GAS MIXTURE w^'
h 3![,;
9 This spec 1fication is provided to ensure that the concentration of
/.
p.c potentially explosive gas mixtures contained in the waste gas holdup system is (3 ",
1, maintained below the flammability limits of hydrogen and oxygen.
(Automatic
..g..f control features are included in the system to prevent the hydrogen and oxygen 3-concentrations from reaching these flammability limits.
These automatic control i.!
features include isolation of the source of hydrogen and/or oxygen, automatic j"'M' y
diversion to recombiners, or injection of dilutants to reduce the concentration
% 4 '.,
i.;
below the flammability limits.) Maintaining the concentration of hydrogen and
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oxygen below their flammability limits provides assurance that the releases of f*,
i radioactive materials will be controlled in conformance with the requirements l,.7.l 4.
of General Design Criterion 60 of Appendix A to 10 CFR Part 50.
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%.Q 3/4.11.2.7 MAIN CONDENSER A
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Restricting the gross radioactivity rate of noble gases from the main hl-M condenser provides reasonable assurance that the total body exposure to an 3
1 individual at the exclusion area boundary will not exceed a small fraction of M ;,].
y2 g
the limits of 10 CFR Part 100 in the event this effluent is inadvertently g.; T discharged directl; to the environment without treatment.
This specification 41 implements the requirements of General Design Criteria 60 and 64 of Appendix A f
. [. f 9
to 10 CFR Part 50.
m 3/4.11.2.8 MARK I CONTAINMENT v..?
a.k This specification provides reasonable assurance that releases from i
7 drywell pruging operations will not exceed the annual dose limits of 10 CFR M. ;.,
Va Part 20 for unrestricted areas.
f f
pp 3/4.11.3 SOLID RADIOACTIVE WASTE
- 7. ;* /
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j This specificaticn implements the requirements of 10 CFR Part 50.36a and 5E
~J General Design Criterion 60 of Appendix A to 10 CFR Part 50.
The process a4 e-T, parameters included in establishing the PROCESS CONTPOL PROGRAM may include, but are not limited to waste type, waste pH, waste / liquid / solidification agent /
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,6 catalyst ratios, waste oil content, waste principal chemical constituents, and yJ.
<4 mixing and curing times.
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3/4.11.4 TO ML DOSE This specification is provided to meet the dose limitations of 40 CFR Part 190 that have been incorporated into 10 CFR Part 20 by 46 FR 18525.
The specification requires the preparation and submittal of a Special Report
?
whenever the calculated doses from plant generated radioactive affluents l$
and direct radiation exceed 25 mrems to the total body or any organ, except i,-
the thyroid, which shall be limited to less than or equal to 75 mrems.
For sites containing up to 4 reactors, it is highly unlikely that the resultant
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dose to a MEMBER OF THE PUBLIC will exceed the dose limits of 40 CFR Part 190 t
a if the individual reactors remain within twice the dose design objectives of Appendix I, and if direct radiation doses from the reactor units and outside y
3 storage tanks are kept small.
The Special Report will describe a course of f
action that should result in the limitation of the annual dose to a MEMBER OF THE PUBLIC to within the 40 CFR Part 190 limits.
For the purposes of the Special Report, it may be assumed that the dose commitment to the MEMBER OF THE PUBLIC from other uranium fuel cycle sources is negligible, with the exception that dose contributions from other nuclear fuel cycle facilities at
, 7
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the same site or within a radius of 8 km must be considered.
If the dose to any MEMBER OF THE PUBLIC is estimated to exceed the requirements of 40 CFR
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Part 190, the Special Report with a request for a variance (provided the i
release conditions resulting in violation of 40 CFR Part 190 have not already a
been corrected), in accordance with the provisions of 40 CFR Part 190.11 and 5
10 CFR Part 20.405c, is considerad to be a timely request and fulfills the 7
requirements of 40 CFR Part 190 until NRC staff action is completed. The 2
variance only relates to the limits of 40 CFR Part 190, and does not apply in any way to the other requirements for dose limitation of 10 CFR Part 20, as addressed in Specifications 3.11.1.1 and 3.11.2.1.
An individual is not 4
considered a MEMBER OF THE PUBLIC during any period in which he/she is engaged "i
d in carrying out any operation tht is pr.rt of the nuclear fuel cycle.
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Elifd 3/4.12 RADIOLOGICAL ENVIRONMENTAL MONITORING
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BASES
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3]4.12.1 MONITORING PROGRAM
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The radiological environmental monitoring program required by this v ' [
specification provides representative measurements of radiation and of radio-active materials in those exposure pathways and for those radionuclides that
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lead to the highest potential radiation exposures of MEMBERS OF THE PUBLIC
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5 x 2 resulting from the station operation.
This monitcring program implements
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Section IV.B.2 of Appendix I to 10 CFR Part 50 and thereby supplements the
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radiological effluent monitoring program by verifying that the measurable
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l concentrations of radioactive materials and levels of radiation are not higher than expected on the basis of the effluent measurements and the modeling of f
the environmental exposure pathways. Guidance for this monitoring program is provided by the Radiological Assessment branch Technical Position on Environ-
- R mental Monitoring.
The initially specified monitoring program will be ef fective for at least the first three years of commercial operation.
Following this period, program changes may be initiated based on operational experience.
4 The required detection capabilities for environmental sample analyses are tabulated in terms of the lower limits of detection (LLDs).
The LL0s required by Table 4.12-1 are considered optimum for routine environmental y
t measurements in industrial laboratories.
It should be recognized that the f
LLD is defined as an a priori (before the fact) limit representing the capa-y bility of a measurement system and not as an a posteriori (after the fact) i M
P..
limit for a particular measurement.
n, Detailed discussion of the LLD, and other detection limits, can be found s*
'R in HASL Procedures Manual, HASL-300 (revised annually), Currie, L.
A., " Limits i
if for Qualitative Detection and Quantitative Determination - Application to Radiochemistry," Anal. Chem. 40, 586-93 (1968), and Hartwell, J. K., " Detection 9
Limits for Radioanalytical Counting Techniques," Atlar. tic Richfield Hanford R
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Company Report ARH-SA-215 (June 1975).
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3/4.12 RADIOLOGICAL ENVIRONMENTAL MONITORING BASES 3/4.12.2 LAND USE CENSUS This specification is provided to ensure that changes in the use of areas at and beyond the SITE BOUNDARY are identified and that modifications to the radiological environmental monitoring program are made if required by the results of this census. The best information from the door-to-door survey, from aerial survey or from consulting with local agricultural authorities shall be used.
This census satisfies the requirements of Section IV.B.3 of Appen-dix I to 10 CFR Part 50.
Restricting the census to gardens of greater than 50 m2 provides assurance that significant exposure pathways via leafy vege-tables will be identified and monitored since a garden of this size is the minimum required to produce the quantity (26 kg/ year) of leafy vegetables assumed in Regulatory Guide 1.109 for consumption by a child. To determine this minimum garden size, the following assumptions were made:
- 1) 20% of the garden was used for growing broad leaf vegetation (i.e., similar to lettuce l
and cabbage), and 2) a vegetation yield of 2 kg/m,
2 3/4.12/3 INTERLABORATORY COMPARISON PROGRAM The requirement for participation in an approved Interlaboratory Comparison Program is provided to ensure that independent checks on the precision and accu-racy of the measurerents of radioactive matorial in environmental sample matrices are performed as part of the quality assurance program for environ-mental monitoring in order to deuonstrate that the results are valid for the i
purposes of Section IV.B.2 of Appendix I to 10 CFR Part 50.
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BWR-STS-1 PWR-STS-I B 3/4 12-2 9/3/82
bbN 5.0 DESIGN FEATURES 5.1 SITE MAP DEFINING UNRESTRICTED AREAS FOR RADIOACTIVE GASEOUS AND LIQUID EFFLUENTS 5.1. 3 Information regarding radioactive gaseous and liquid effluents, which will allow identification of structures and release points as well as defini-tion of UNRESTRICTED AREAS within the SITE BOUNDARY that are accessible to MEMBERS OF THE PUBLIC, shall be as shown in Figure 5.1-3.
The definition of UNRESTRICTED AREA used in implementing the Radiological Effluent Technical Specifications has been expanded over that in 10 CFR 20.3 (a)(17). The UNRESTRICTED AREA boundary may coincide with the exclusion (fenced) area boundary, as defined in 10 CFR 100.3(a), but the UNRESTRICTED AREA does not include areas over water bodies.
The concept of UNRESTRICTED AREAS, established at or beyond the SITE BOUNDARY, is utilized in the LIMITING CONDITIONS FOR OPERATION to keep levels of radioactive materials in liquid and gaseous effluents as low as is reasonably achievable, pursuant to 10 CFR 50.36a.
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BWR-STS-I
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PWR-STS-I 5-1 9/3/82
DM77 This figure shall consist of a map of the site area showing the SITE BOUNDARY and locating points within the SITE BOUNDARY where radioactive gaseous and liquid affluents are released, as well as where radioactive liquid effluents leave the site.
If onsite areas sub-ject to radioactive materials in gaseous or ~ iquid eff'luents are utilized by the public for recreational or other purposes, these areas shall be outlined on the map and identified by occupancy factors and the licensee's mathod of occupancy control (if any).
The figure shall oe sufficiently detailed to allow identi-fication of structures and release point locations and elevations, as well as definition of UNRESTRICTED AREAS within the SITE BOUNDARY that are accessible to MEMBERS OF THE PUBLIC. The map scale shall be on the order of 2-3"/ mile. See NUREG-0133 for additional guidance.
MAP DEFINING UNRESTRICTED AREAS FOR RADIOACTIVE GASEOUS AND LIQUID EFFLUENTS FIGURE 5.1-3
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PWR-STS-I 5-2 9/3/82
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$?.h 6.0 ADMINISTRATIVE CONTROLS 6.5.1 UNIT REVIEW GROUP (URG)
RESPONSIBILITIES
- 6. 5.1. 6 The URG shall be responsible for:
k.
Review of any accidental, unplanned or uncontrolled radioactive release including the preparation of reports covering evaluation, recommendations and disposition of the corrective action to prevent recurrence and the forwarding of these reports to tha (Superintendent of Power Plants) and to the (Company Nuclear Review and Audit Group).
1.
Review of changes to the PROCESS CONTROL PROGRAM and the OFFSITE DOSE CALCULATION MANUAL.
6.5.2 COMPANY NUCLEAR REVIEW AND AUDIT GROUP (CNPAG)
AUDITS 6.5.2.8 Audits of unit activities shall be performed under the cognizance of the (CNRAG). These audits shall encompass:
k.
The radiological environmental mo'nitoring program and the results thereof at least once per 12 months.
1.
The OFFSITE DOSE CALCULATION MANUAL and implementing procedures at least once per 24 months.
The PROCESS CONTROL PROGRAM and implementing procedures for processing m.
and packaging of radioactive wastes at least once per 24 months.
The performance of activities required by the Quality Assurance n.
Program to meet the provisions of Regulatory Guide 1.21, Revision 1, June 1974 and Regulatory Guide 4.1, Revision 1, April 1975 at least once per 12 months.
6.8 PROCEDURES AND PROGRAMS 6.8.1 Written. procedures shall be established, implemented and maintained covering the activities referenced below:
g.
PROCESS CONTROL PROGRAM implementation.
h.
CFFSITE DOSE CALCULATION MANUAL implementation.
1.
Quality Assurance Pr'ogram for effluent and environmental monitoring, using the guidance in Regulatory G~uide"1l21, Revision 1, June 1974 and Regulatory Guide 4.1, Revision 1, April 1975.
BWR-STS-I PWR-STS-I 6-1 9/3/82
o DMR ADMINISTRATIVE CONTROLS 6.9 REPORTING REQUIREMENTS ROUTINE REPORTS AND REPORTABLE OCCURRENCES 6.9.1 In addition to the applicable reporting requirements of Title 10, Code of Federal Regulations, the following reports shall be submitted to the Director of-the Regional Office of Inspection and Enforcement unless otherwise noted.
THIRTY DAY WRITTEN REPORTS 6.9.1.9 The types of events listed below shall be the subject of written reports to the Director of the Regional Office within thirty days of occur-rence of the event. The written report shall include, as a minimum, a completed copy of a licensee event report form.
Information provided on the licensee event report form shall be supplemented, as needed, by additional narrative material to provide complete explanation of the circumstances surrounding the event.
a.
Reacter protection system or engineered safety feature instrument l
settings which are found to be less conservative than those established by the Technical Specifications but which do not prevent the fulfillment of the functional requirements of affected systems.
b.
Conditions leading to operation in a degraded mode permitted by a Limiting Condition for Operation or plant shutdown required by a Limiting Condition for Operation.
c.
Observed inadequacies in the implementation of administrative or procedural controls which threaten to cause reduction of degree of L
redundancy provided in reactor protection systems or engineered safety feature systems.
l d.
Abnormal degradation of systems other than those specified in 6.9.1.8.c above designed to contain radioactive material resulting from the fission process.
BWR-STS-I PWR-STS-I 6-2 9/3/82
bhY ADMINISTRATIVE CONTROLS ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT
- 6.9.1.11 Routine Radiological Environmental Operating Reports covering the operation of the unit during the previous calendar year shall be submitted prior to May 1 of each year.
The initial report shall be submitted prior to May 1 of the year following initial criticality.
The Annual Radiological Environmental Operating Reports shall include summaries, interpretations, and an analysis of trends of the results of the radiological environmental surveillance activities for the report period, including a compar-ison with preoperational studies, with operational controls at appropriate, and with previous environmental surveillance reports, and an assessment of the observed impacts of the plant operation on the environment. The reports shall also include the results of land use censuses required by Specification 3.12.2.
The Annual Radiological Environmental Operating Reports shall include the results of analysis of all radiological environmental samples and of all environmental radiation measurements taken during the period pursuant to the locations speci-fied in the Table and Figures in the ODCM, as well as summarized and tabulated results of these analyses and measurements in the format of the table in the Radiological Assessment Branch Technical Position, Revision 1, November 1979.
In the event that some individual results are not available for inclusion with the report, the report shall be submitted noting and explaining the reasons for the missing results. 'he missing data shall be submitted as soon as possible in a supplementary report.
The reports shall also include the following:
a sumcary description of the radiological er.vironmental monitoring program; at least two legible maps **
covering all sampling locations keyed to a table giving distances and directions from the centerline of one reactor; the results of licensee participation in the Interlaboratory Comparison Program, required by Specification 3.12.3; discussion af all deviations from the sampling schedule of Tabic 3.12-1; and discussion of all analyses in which the LLD required by Table 4.12-1 was not achievable.
"A single submittal may be made for a multiple unit station.
- 0ne map shall cover stations near the site boundary; a second shall include the more distant stations.
BWR-STS-I PWR-STS-I 6-3 9/3/82
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Lf ADMINIs rqATIVE CONTROLS
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l je SEMIANNUAL RADI0 ACTIVE EFFLUENT RELEASE REPORT
- l g-6 9.1.12 Routine Radioactive Effluent Release Reports covering the operation 1
of the unit during the previous 6 months of operation shall be submitted within qp 60 days after January I and July 1 of each year.
The period of the first report shall begin with the date of initial criticality.
The Radioactive Effluent Release Reports shall include a summary of the quantities of radioactive liquid and gaseous effluents and solid waste released from the unit as outlined in Regulatory Guide 1.21, " Measuring, Evaluating, and Reporting Radioactivity in Solid Wastes and Releases of Radio-active Materials in Liquid and Gaseous Effluents from Light-Water-Cooled Nuclear Power Plants," Revision 1, June 1974, with data summarized on a o"arte-ly basis following the format of Appendix B thereof.
x The Radioactive Effluent Release Report to be submitted within 60 days after Januury 1 of each year shall include an annual summary of hourly meteorological data collected over the prev')as year.
This annual summary may be either in the form of an hour-by-hour listing on magnetic tape of wind speed, wind direction, atmospheric stability, and precipitation (if measured), or in the form of joint frequency distributions of wind speed, wind direction, and atmospheric sta-bility.**
This same report shall include an assessment of the radiation doses due to the radioactive liquid and gaseous effluents released from the unit or station during the previous calendar year.
This same report shall also include an assessment of the radiation doses from radioactive liquid and gaseous effluents to MEMBERS OF THE PUBLIC due to their activities inside the SITE BOUNDARY (Figure 5.1-3) during the report period.
All assumptions used in making these assessments, i.e., specific activity, exposure time and location, shall be included ir. these reports.
The meteorological conditions concurrent with the time of release of radioactive materials in gaseous effluents, as determined by sampling frequency and measurement, shall be used for determining the gaseous pathway doses.
[For ors:
approximate and conservative approximate methods are acceptable.] The assessment of radiation doses shall be performed in accordance with the methodology and parameters in the OFFSITE DOSE CALCULATION MANUAL (ODCM).
The Radioactive Effluent Release Report to be submitted 60 days after January 1 of each year shal! also include an assessment of radiation doses to the likely most exposed MEMBER OF THE PUBLIC from reactor releases and other nearby uranium fuel cycle sources, including doses from primary effluent pathways and direct radiation, for the previous calendar year to show conformance with 40 CFR Part 190, Environmental Radiation Protection Standards for Nuclear Power
- A single submittal may be made for a multiple unit station.
The submittal should combine those sections that are common to all units at the station; however, for units with separate radwaste systems. the submittal shall specify the releases of radioactive material from each unit.
- In lieu of submission with the first half year Radioactive Effluent Release f
Report, the licensee has the option of retaining this summary of required meteorological data on site in a file that shall be provided 12 the NRC upon request.
BWR-STS-I PWR-STS-I 6-4 9/3/82
bb ADMINISTRATIVE CONTROLS Operation. Acceptable methods for calculating the dose contribution from liquid and gaseous effluents are given in Regulatory Guide 1.109, Rev. 1, October 1977.
The Radioactive Effluent Release Reports shall include the following information for each class of solid waste (as defined by 10 CFR Part 61) shipped offsite during the report period:
a.
Container volume, b.
Total curie quantity (specify whether determined by measurement or estimate),
Principal radionuclides (specify whether determined by measurement c.
or estimate),
d.
Source of waste and processing employed (e.g., dewatered spent resin, compacted dry waste, evaporator bottoms),
Type of container (e.g., LSA, Type A, Type 8, Large Quantity), and e.
f.
Solidification agent or absorbent (e.g., cement, urea formaldehyde).
The Radioactive Effluent Release Reports shall include a list and description of unplanned releases from the site to UNRESTRICTED AREAS of radioactive materials in gaseous and liquid effluents made during the reporting period.
The Radioactive Effluent Release Reports shall include any changes made during the reporting period to' the PROCESS CONTROL PROGRAM (PCP) and to the OFFSITE DOSE CALCULATION MANUAL (00CM), as well as a listing of new locations for dose calculations and/or environmental monitoring identified by the land use census pursuant to Specification 3.12.2.
SPECIAL REPORTS 1-Special reports may be required covering inspections, test and maintenance activities. These special reports are determined on an individual basis for each unit and their preparation and submittal are designated in the Technical Specifications.
6.9.2 Special reports shall be submitted to the Director of the NRC Regional Office listed in Appendix 0, 10 CFR Part 20, with a copy to the Director, Office of Inspection and Enforcement, U.S. Nuclear Regulatory Commission, Washington, D.C.
20555 within the time period specified for each report.
6.10 RECORD RETENTION 6.10.2 The following records shall be ret.afned for the duration of the Unit Operating License:
Records of analyses required by the radiological environmental n.
monitoring program that would permit evaluation of the accuracy of the analysis at a later date. This should include procedures effective at specified times and QA records showing that these procedures were followed.
BWR-STS-I PWR-STS-I 6-5 9/3/82
C hhk ADMINISfRATIVE CONTROLS 6.13 PROCESS CONTROL PROGRAM (PCP) 6.13.1 The PCP shall be approved by the Commission prior to implementation.
6.13.2 Licensee initiated changes to the PCP:
1.
Shall be submitted to the Commission in the Semiannual Radioactive Effluent Release Report for the period in which the change (s) was made. This submittal shall contain:
a.
Sufficiently detailed information to totally suport the rationale for the change without benefit of additional or supplemental information; i
b.
A determination that the change did not reduce the overall conformance of the solidified waste product to existing criteria for solid wastes; and c.
Documentation of the fact that the change has been reviewed and found acceptable by the (URG).
2.
Shall become effective upon review and acceptance by the (URG).
6 14 0FFSITE DOSE CALCULATION MANUAL (ODCM) 3 6.14.1 The ODCM shall be approved by the Commission prior to implementation.
6.14.2 Licensee initiated changes to the ODCM:
1.
Shall be submitted to the Commission in the Semiannual Radioactive Effluent-Release Report for the period in which the change (s) *Is made affective.
This submittal shall contain:
i a.
Sufficiently detailed information to totally support the rationale for the change without benefit of additional or supple-mental infarmation.
Information submitted should consist of a package of those pages of the 00CM to be changed with each page numbered and provided with an approval and date box, together with appropriate analyses or evaluations justifying the change (s);
b.
A determination that the change will not reduce the accuracy or reliability of dose calculations or setpoint determinations; and c.
Documentation of the fact that the change hss been reviewed and found acceptable by the (URG).
2.
Shall become effective upon review and acceptance by the (URG).
BWR-STS-I PWR-STS-I 6-6 9/3/82
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ADMINISTRATIVE CONTROLS 6.15 MAJOR CHANGES TO RADI0 ACTIVE LIQUID, GASEOUS AND SOLID WASTE TREATMENT SYSTEMS
- 6.15.1 Licensee initiated major changes to the radioactive waste systems (liquid, gaseous and solid):
1.
Shall be reported to the Commission in the Semiannual Radioactive Effluent Release Report for the period in which the evaluation was reviewed by the (Unit Review Group).
The discussion of each change shall contain:
A summary of the evaluation that led to the determination that a.
the change could be made in accordance with 10 CFR Part 50.59.
b.
Sufficient detailed information to totally support the reason for the change without benefit of additional or supplemental information; A detailed descriptian of the equipment, components and processes c.
involved and the interfaces with other plant systems; d.
An evaluation of the change, which shows the predicted releases of radioactive materials in liquid and gaseous effluents and/or quantity of solid waste that differ from those previously predicted in the license application and amendments thereto; An evaluation of the change, which shows the expected maximum e.
exposures to individual in the UNRESTRICTED AREA and to the general population that differ from those previously estimated in the license application and amendments thereto; f.
A comparison of the predicted releases of radioactive materials, in liquid and gaseous effluents and in solid waste, to the actual releases for the period prior to when the changes are to be made; g.
An estimate of the exposure to plant operating personnel as a result of the change; and h.
Documentation of the fac'. that the change was reviewed and found acceptable by the (URG).
2.
Shall become effectiva upon review and acceptance by the (URG).
- Licensees may chose to submit the information called for in this Specificaticn
~
as part of the annual FSAR update.
BWR-STS-I PWR-STS-I 5-7 9/3/82
s Date ROUTING AND TRANSMITTAL SUP April 19,1985
~
TO: (Neme, office symbol, room number, initials l Date building, Agency / Post) l
~~
- 3. Steve Scott, Chief Document Management Branch n.
DTIDC ocaa ur art 2dl.
St -
5.
j Action File Note and Return Approval For Clearance Per Conversation i
As Requested For Correction Prepare Reply Circulate For Your information See Me Comment investigate Signature Coordination Justify af. MARKS r.
{
Please send the attached document to the i
Public Document Room.
i f
N'JREG-0473, Revisten 3, Draft 7"
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.j Do NoT use this form as a RECORD of approvals, concurrences, disposals.
clearances, and similar actions FROM: (Name, org. s3'nbol, Agency / Post)
Room No.-Bldg.
Williani P. Gammill, Chief Meterology 'n (fluent Treatment Brarsene No.
DSI/NRR
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