ML19323G477
| ML19323G477 | |
| Person / Time | |
|---|---|
| Site: | San Onofre  |
| Issue date: | 02/01/1980 |
| From: | NRC COMMISSION (OCM) |
| To: | |
| Shared Package | |
| ML13311B051 | List: |
| References | |
| NUREG-0472, NUREG-472, NUDOCS 8006020559 | |
| Download: ML19323G477 (80) | |
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NUREG-0472 REVISION 2 1-e 4
i RADIOLOGICAL EFFLUENT TECHNICAL SPECIFICATIONS FOR PWR'S JULY 197C JAN 1 1980 1
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1 INDEX DEFINITIONS SECTION PAGE 1.0 DEFINITIONS Channel Calibration................................................
1-1 Channel Check......................................................
1-1 Channel Functional Test............................................
1-1 Dose Equivalent I-131..............................................
1-1 Source Check...........................................
1-1 Process Control Program (PCP).............................
1-1 Solidification..............................................
1-7 Offsite Dose Calculation Manual (0DCM).............................
1-7 Gaseous Radwaste Treatment System..................................
1-7 i
Ventilation Exhaust Treatment System...............................
1-7 Purge-Purging.................................................
1-7 Venting............................................................
1-7 NOTE:
Add 3/4.3.3.9 and 3/4.3.3.10 with appropriate page numbers to Index section for Monitoring Instrumentation and its Bases; also add 5.1.3 and 5.1.4 to Section 5.0 Index.
PWR-STS-I I
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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 3/4 11.2 GASEOUS EFFLUENTS Dose Rate................................................
3/4 11-8 Dose-Noble Gases................
3/4 11-12 Dose-Radioiodines, Particulate, and Radionuclides Other than Noble Gases...................
3/4 11-13 Gaseous Waste Treatment..................................
3/4 11-14 Explosive Gas Mixture..........................
3/4 11-15 Gas Storage Tanks........................................
3/4 11-18 3/4 11.3 SOLID RADIOACTIVE WASTE..................................
3/4 11-19 3/4 11.4 TOTAL 00SE...............................................
3/4 11-21 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 12-10 3/4.12.3 INTERLABORATORY COMPARISON..............................
3/4 12-11 PWR-STS-I II
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INDEX BASES SECTION PA6d 3/4.11 RADI0 ACTIVE EFFLUENTS 3/4.11.1 LIQUID EFFLUENTS........................................
B 3/4 11-1 3/4.11.2 GASEOUS EFFLUENTS.......................................
8 3/4 11-2 3/4.11.3 SOLIO RADI0 ACTIVE WASTE.................................
B 3/4 11-5 3/4.11.4 TOTAL 00SE..............................................
B 5/4 11-5 3/4.12 RADI0 ACTIVE ENVIRONMENTAL MONITORING 3/4.12.1 MONITORING PR0 GRAM................................
8 3/4 12-1 3/4.12.2 LAND USE CENSUS.........................................
8 3/4 12-1 3/4.12.3 INTERLABORATRY COMPARISON PR0 GRAM.......................
8 3/4 12-1 i
i PWR-STS-I III l
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1.0 DEFINITIONS CHANNEL CALIBRATION 1.9 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 1.10 A CHANNEL CHECK shall be the qualitative assessment of channel behavior during operation by observation. This determination shall include, where pessible, comparison of the channel indication and/or status with other indica-tions and/or status derived from independent instrumentation channels measuring
)
the same parameter.
i CHANNEL FUNCTIONAL TEST 1.11 A CHANNEL FUNCTIONAL TEST shall be:
Analog channels - the injection of a simulated signal into the a.
channel as close to the sensor as practicable to verify OPERABILITY including alarm and/or trip functions.
b.
Bistable channels - the injection of a simulated signal into the l
sensor to verify OPERABILITY including alarm and/or trip functions.
DOSE EQUIVALENT I 131 1.19 The DOSE EQUIVALENT I-131 shall be that concentration of I-131 (microcurie /
gram) which alone would procuce the same thyroid dose as the quantity and isotopic mixture of I-131, 1-132, 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-14G44, " Calculation of Distance Factors for Power and Test Reactor Sites."
SOURCE CHECK 1.29 A SOURCE CHECK shall be the qualitative assessment of channel response when the channel sensor is exposed to a radioactive source.
PROCESS CONTROL PROGRAM (PCP) 1.30 The PROCESS CONTROL PROGRAM shall contain the sampling, analysis, and formulation determination by which SOLIDIFICATION of radioactive wastes from liquid systems is assured.
PWR-STS-I l-1
1 1.0 DEFINITIONS (Continued) i SOLIDIFICATION 1.31 SOLIDIFICATION shall be the conversion of radioactive wastes from liquid >
l systems to a homogenecus (uniformly distributed), monolithic, immobilized i
solid with definite volume and shape, bounded by a stable surface of distinct outline on all sides (free-standing).
OFFSITE DOSE CALCULATION MANUAL (ODCM) 1.32 The OFFSITE DOSE CALCULATION MANUAL shall con *.ain the methodology and parameters used in the calculation of offsite dose; due to radioactive gaseous and liquid effluents and in the calculation of of gaseous and liquid effluent monitoring alarm / trip setpoints.
GASEOUS RADWASTE TREATMENT SYSTEM 1.33 A GASEOUS RADWASTE TREATMENT SYSTEM is any system designed and installed to reduce radioactive gaseous effluents by collecting primary coolant system offgases ' rom the primary system and providing for delay or holdup for the purpose of reducing the total radioactivity prior to release to the environment.
VENTILATION EXHAUST TREATMENT SYSTEM 1.34 A VENTILATION EXHAUST TREATMENT SYSTEM is any system designed and installed to reduce gaseous radioiodine 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.
PURGE - PURGING 1.35 PURGE or PURGING is the controlled process of 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.
VENTING 1.36 VENTING is the controlled process of 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 not provided or required during VENTING. Vent, used in system names, does not imply a VENTING process.
PWR-STS-I 1-7
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l TABLE 1.2 l
l FREQUENCY NOTATION 1
NOTATION FPrQUENCY 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 />.
O At least cnce 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 sta,rtup.
P Completed prior to each release.
N.A.
Not applicable.
PWR-STS-I l-8
i INSTRUMENTATION RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATICN LIMITING CONDITION FOR OPERATION 3.3.3.9 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 setpoints of these channels shall be determined in accordance with the OFFSITE DOSE CALPULATION MANUAL (00CM).
APPLICABILITY: At all times.
ACTION:
a.
With a radioactive liquid effluent monitoring instrumentation channel alarm / trip setpoint less conservative than required by the above specification, immediately suspend the release of radioactive liquid effluents monitored by the affected channel or declare the channel inoperable.
b.
With less than the minimum number of radioactive liquid effluent monitoring instrumentation channels OPERABLE, take the ACTION shown in Table 3.3-12.
c.
The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.
SURVEILLANCE REQUIREMENTS 4.3.3.9 Each radioactive liquid effluent monitoring instrumentation channel shall be demonstrated C?ERABLE by performance of the CHANNEL CHECK, SOURCE CHECK, CHANNEL CALIBRATION and CHANNEL FUNCTIONAL TEST operations at the frequencies shewn in Table 4.3-12.
PWR-STS-I 3/4 3-65
g TABLE 3.3-12 RADI0 ACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION HINIMUM CHANNELS INSTRUMENT OPERABLE ACTION 1.
GROSS RADI0 ACTIVITY MONITORS PROVIDING AUTOMATIC TERMINATION OF RELEASE a.
Liquid Radwaste Effluent Line (1) 28 r.
b.
Steam Generator Blowdown Ef fluent Line (1) 29 c.
Turbine Building (Floor Drains) Sumps Effluent Line (1) 30 2.
GROSS RADI0 ACTIVITY MONIf0RS NOT PROVIDING AUTOMATIC m2 TERMINATION OF RELEASE a.
Service Water System Effluent Line (1) 30 b.
Component Cooling Water System Effluent Line (1) 30 3.
CONTINUOUS COMPOSITE SAMPLERS AND SAMPLER FLOW HONITOR a.
Steam Generator Blowdown Effluent Line (1) 29 b.
Turbine Building Sumps Effluent Line (1) 30 4.
FLOW RATE MEASUREMENT DEVICES a.
Liquid Radwaste Effluent Line (1) 31 b.
Discharge Canal (1) 31 c.
Steam Generator Blowdown Effluent Lines (1) 31
TABLE 3.3-12 (Continued)
N J,
RADI0 ACTIVE LIQUID EFFLUENT HONITORING INSTRUMENTATION wT
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MINIMUM CHANNELS INSTRUMENT OPERABLE ACTION 5.
RADI0 ACTIVITY RECORDERS (*)
.a.
Liquid Radwaste Effluent Line (1) 33 b.
Steam Generator Blowdown Effluent Line (1) 34 6.
TANK LEVEL INDICATING DEVICES (for tanks outside plant buildings)
R a.
(1) 32 a
g>
b.
(1) 32 o,
c.
(1) 32 d.
(1) 32
{3 Required only if alarm / trip set point is based on recorder-controller)
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TABLE 3.3-12 (Continued)
TABLE NOTATION ACTION 28 -
With the number of channels OPERA 8LE less than required by the Minimum Channels OPERA 8LE requirement, effluent releases may-continue for up to 14 days 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 29 -
With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue for up to 30 days provided grab samples are analyzed for gross radig9ctivity (beta or gamma) at a limit of detection of at least 10 microcuries/ gram:
a.
At least once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> when the specific activity of the secondary coolant is greater than 0.01 microcuries/ gram DOSE EQUIVALENT I-131.
b.
At least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> when the specific activity of the secondary coolant is less than or equal to 0.01 micro-curies / gram DOSE EQUIVALENT I-131.
ACTION 30 -
With the mJmber of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue for up to 30 days provided that, at least once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />, grab ccmples are collected and analyzed for gross radig9ctivity (beta or gamma) at a limit of detection of at least 10 microcuries/ml.
ACTION 31 -
With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue for up to 30 days provided the flow rate is estimated at least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> during actual releases. Pump curves may be used to estimate flow.
ACTION 32 -
With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, liquid additions to this tank may continue for up to 30 days provided the tank liquid level is estimated during all liquid additions to the tank.
d PWR-STS-I 3/4 3-68
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TABLE 3.3-12 (Continued)
TABLE NOTATION ACTION 33 -
With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via the affected pathway may continue for up to 14 days 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.
ACTION 34 -
With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via the affected pathway may continue for up to 30 days 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 release.
PWR-STS-I 3/4 3-69 1
4 TABLE 4.3-12 Iy RADI0 ACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS M
vs O
CHANNEL CHANNEL SOURCE CHANNEL FUNCTIONAL INSTRUMENT CHECK CHECK CALIBRATION TEST 1.
GROSS BETA OR GAMMA RADI0 ACTIVITY MONITORS PROVIDING ALARM AND AUTOMATIC TERMINATION OF RELEASE
- a. Liquid Radwaste Effluents Line D
P R(3)
Q(1)
- b. Steam Generator Blowdown Effluent Line D
M R(3)
. Q(1)
- c. Turbine Building (Floor Drains) Sumps Effluent Line D
M R(3)
Q(1) 1 Y
2.
GROSS BETA OR GAMMMA RADI0 ACTIVITY MONITORS U
PROVIDING ALARM BUT NOT PROVIDING AUTOMATIC TERMINATION OF RELEASE a.
Service Water System Effluent Line D
M R(3)
Q(2) b.
Component Cooling Water System Effluent 4Line D
M R(3),
Q(2) 3.
CONTINUOUS COMPOSITE SAMPLERS AND SAMPLER FLOW MONITOR a.
Steam Generator Blowdown Effluent Line D
N.A.
R Q
b.
Turbine Building Sumps. Effluent Line D
N.A.
R Q
A TABLE 4.3-12 (Continued)
RADI0 ACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS n
mO CHANNEL CHANNEL SOURCE CHANNEL FUNCTIONAL INSTRUHFNT CHECK CHECK CALIBRATION TEST 4.
FLOW RATE HEASUREMENT DEVICES a.
Liquid Radwaste Effluent Line D(4)
N.A.
R Q
b.
Steam Generator Blowdown Effluent Line D(4)
N.A.
R Q
c.
Discharge Canal 0(4)
N.A.
R Q
5.
RADI0 ACTIVITY RECORDERS a.
Steam Generator Blowdown Effluent Line D
N.A.
R Q
U b.
Liquid Radwaste Effluent Line D
N.A.
R Q
6.
LANK LEVEL INDICATING DEVICES (for tanks outside the building) a.
D*
N.A.
R Q
b.
D*
N.A.
R Q
c.
D*
N.A.
R Q
d.
D*
N.A.
R Q
a
's l
TABLE 4.3-12 (Continued)
TABLE NOTATION During liquid additions to the tank.
(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 2 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 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 N85. 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 intial calibration shall be used.
(Operating plants may substitute previously established calftration 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 on which continuous, periodic, or batch releases are made.
l 9
l PWR-STS-I 3/4 3-72
l INSTRUMENTATION RADI0 ACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.3.10 The radioactivt 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 are not exceeded.
The alarm / trip setpoints of these channels shall be determined in accordance with the ODCM.
APPLICABILITY: As shown in Table 3.3-13 ACTION:
a.
With a radioactive gaseous effluent monitoring instrumentation channel alarm / trip setpoint less conservative than required by the above Specification, immediately suspend the release of radioactive gaseous effluents monitored by the affected channel or declare the channel inoperable.
b.
With less than the minimum number of radioactive gaseous effluent monitoring instrumentation channels OPERABLE, take the ACTION shown in Table 3.3-13.
c.
The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.
SURVEILLANCE REQUIREMENTS 4.3.3.10 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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PWR-STS-I 3/4 3-73
TABLE 3.3-13 RADI0 ACTIVE GASE0US EFFLUENT HONITORING INSTRUMENTATION 4
m d4 MINIMUM CilANNELS INSTRUMENT OPERABLE APPLICABILITY ACTION 1.
WASTE GAS Il0LDUP SYSTEM a.
Noble Gas Activity Monitor - Providing Alarm and Automatic Termination of Release (1) 35
~*
b.
Iodine Sampler (1) 41 c.
Particulate Sampler (1) 41 d.
Effluent System Flow Rate Measuring Device (1) 36
}{
e.
Sampler Flow Rate Heasuring Device (1) 36 Yif 2A.
WASTE GAS Il0LDUP SYSTEM EXPLOSIVE GAS HONITORING SYSTEM (for systems designed to withstand the effects of a hydrogen explosion) a.
liydrogen Monitor (1) 39 b.
Ilydrogen or Oxygen Monitor (1) 39 28.
WASTE GAS HOLDUP SYSTEM EXPLOSIVE GAS MONITORING SYSTEM (for systems not designed to withstand the effects of a hydrogen explosion) a.
ilydrogen Monitor (2) 40 40 b.
ilydrogen or Cxygen Monitor (2)
TABLE 3.3-13 (Continued) h!
RADI0 ACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION ad J.
MINIMUM CHANNELS INSlRUMENT OPERABLE APPLICABILITY ACTION 3.
CONDENSER EVACUATION SYSTEM a.
Noble Gas Activity Monitor (1) 37 b.
Iodine Sampler (1) 41 c.
Particulate Sampler (1) 41 36 d.
Flow Rate Monitor (1) e.
Sampler Flow Rate Monitor (1) 36 R
u
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4.
VENT llEADER SYSTEM M
a.
Noble Gas Activity Monitor (1) 37 b.
Iodine Sampler (1) 41 c.
Particulate Sampler (1) 41 d.
Flow Rate Monitor (1) 36 e.
Sampler Flow Rate Monitor (1) 36 5.
CONTAINMENT PURGE SYSTEM a.
Noble Gas Activity Monitor - Providing 38 Alarm and Automatic Termination of Release (1) b.
Iodine Sampler (1) 41 c.
Particulate Sampler (1) 41
TABLE 3.3-13 (Continued)
,c RADI0 ACTIVE GASEOUS EFFLU:NT MONITORING INSTRUMENTATION T
MINIMUM CHANNELS INSTRUMENT OPERABLE APPLICABILITY ACTION 5.
CONTAINMENT PURGE SYSTEM (Continued) 36 e.
Flow Rate Monitor (1) 36 f.
Sampler Flow Rate Monitor (1) 6.
AUXILIARY BUILDING VENTIt.ATION SYSTEM a.
Noble Gas Activity Monitor (1) 37
{
b.
Iodine Sanpler (1-)
41 m
c.
Particulate Sampler (1) 41 36 d.
Flow Rate Monitor (1) e.
Sampler Flow Rate Monitor (1) 36 7.
FUEL STORAGE AREA VENTILATION SYSTEM 37 a.
Noble Gas Activity Monitor (1) b.
ILdine Sampler (1) 41 c.
Particulate SampYer (1) 41 36 d.
Flow Rate Monitor (1) 36 e.
Sampler Flow Rate Monitor (1)
m
~w-a na TABLE 3.3-13 (Continued) yx
[
RADI0 ACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION 9
~
MINIMUM CHANNELS INSTRUMENT OPERABLE APPLICABILITY ACTION 8.
RADWASTE AREA VENTILATION SYSTEM a.
Noble Gas Activity Monitor (1) 37 41 b -
Iodine Sampler (1) c.
Particulate Sampler (1) 41 d.
Flow Rate Monitor (1) 36 e.
Sampler Flow Rate Monitor (1) 36 Y
D 9.
STEAM GENERATOR BLOWDOWN VENT SYSTEM a.
Noble Gas Activity Monitor (1) 37 b.
Iodine Sampler (1) 41 c.
Particulate Sampler (1) 41 36 d.
Flow Rate Monitor (1) 36 e.
Sampler Flow Rate Monitor (1)
e i
TABLE 3.3-13 (Continued)
TABLE NOTATION t
At all times.
- During waste gas holdup system operation (treatment for primary system offgases).
ACTION 35 -
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 14 days provided that prior to initiating the release:
a.
At least two independent samples of the tank's contents are analyzed, and b.
At least two technically qualified members of the Facility Staff independently verify the release rate calculations and discharge valve lineup; Otherwise, suspend release of radioactive effluents via this pathway.
ACTION 36 -
With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue for up to 30 days provided the flow rate is estimated at least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.
ACTION 37 -
With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE require;nent, effluent releases via this pathway may continue for up to 30 days provided grab samples are taken at least once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> and these samples are analyzed for gross activity within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
ACTION 38 -
With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, immediately suspend PURGING of radioactive effluents via this pathway.
ACTION 39 -
With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, operation of this waste gas holdup system may continue for up to 30 days 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 40 -
With the number of channnels OPERABLE one less than required by the Minimum Channels OPERABLE requirement, operation of this system may continue for up to 14 days. With (two) channels inoperable, be in at least HOT STANDBY within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
ACTION 41 -
With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via the affected pathway may continue for up to 30 days provided samples are continuously collected with auxiliary sampling equipment as required in Table 4.11-2.
PWR-STS I 3/4 3-78
TABLE 4.3-13 RAOI0 ACTIVE GASE0US EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS; x
n m1 CHANNEL MODES IN WHICH CilANNEL SOURCE CHANNEL FUNCTIONAL SURVEILLANCE INSTRUMENT CHECK CHECK CALIBRATION TEST REQUIRED 1.
WASTE GAS tl0LDUP SYSTEM
- a. Noble Gas Activity Monitor -
Providing Alarm and Automatic Termination of Release P
P R(3)
Q(1)
^
- b. Iodine Sastpler W
N.A.
N.A.
N.A.
- c. Particulate Sampler W
N.A.
N.A.
.N. A.
{
- d. Flow Rate Monitor P
N.A.
R Q
^
- e. Sampler Flow Rate Monitor D
N.A.
R Q
2.
WASTE GAS Il0LDUP SYSTEM EXPLOSIVE GAS MONITORING SYSTEM
- a. Ilydrogen Monitor D
N.A.
Q(4)
M
- b. ilydrogen Monitor (alternate)
D N.A.
Q(4)
M
- c. Oxygen Monitor D
N.A.
Q(5)
M
- d. Oxygen Monitor (alternate)
D N.A.
Q(5)
M
TABLE 4.3-13 (Continued) mc
[
RADI0 ACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE RE0UIREMENTS eT CHANNEL MODES IN WlCH CHANNEL SOURCE CHANNEL FUNCTIONAL SURVEILLA'lCE INSTRUMENT CHECK CilECK CALIBRATION TEST RFQUIRED 3.
CONDENSER EVACUATION 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
mx
[
Sampler Flow Rate Monitor D
N.A.
R Q
4.
VENT llEADER 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
O TABLE 4.3-13 (Continued)
RADI0 ACTIVE GASEQUS EFFLUENT HONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS b
sni CHANNEL MODES IN WHICH CHANNEL SOURCE CHANNEL FUNCTIONAL SURVEILLANCE INSTRUMENI
_ HECK CHECK CALIBRATION TEST REQUIRED C
5.
CONTAINMENT PURGE SYSTEM
- a. Noble Gas Activity Monitor -
Providing Alarm and Automatic Termination of Release D
P R(3)
Q(1)
- b. Iodine Sampler W
N.A.
N.A.
N.A.
- c. Particulate Sampler W
N.A.
N.A.
N.A.
j{
- d. Flow Rate Monitor D
N.A.
R Q
i'
- e. Sampler Flow Rate Monitor D
N.A.
R Q
B 6.
AUXILIARY BUILDING VENTILATION SYSTEM
- d. Noble Gas Actvity 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 0
l n$
~
1ABLE 4.3-13 (Continued)
RADI0 ACTIVE GASE0US EFFLUENT HONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS
$1 m
.L CHANNEL MODES IN WHICH CHANNEL SOURCE CilANNEL FUNCTIONAL SURVEILLANCE INSTRUMENT CHECK CilECK CALIBRATION TEST REQUIRED 7.
FUEL STORAGE AREA VENTILATION SYSTEM
- a. Noble Gas Activity Monitor D
H R(3)
Q(2)
- b. Iodine Sampler W
H.A.
N.A.
N.A.
- c. Part.iculate Sampler W
N.A.
N.A.
N.A.
^
- d. Flow Rate Monitor D
N.A.
R Q
{
- e. Sampler Flow Rate Monitor D
N.A.
R Q
Y$
8.
RADWASTE AREA VENTILATION 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
eP TABLE 4.3-13 (Continued) h-RADI0 ACTIVE GASEQUS EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS b
snI.
CHANNEL MODES IN WHICH CHANNEL SOURCE CHANNEL FUNCTIONAL SURVEILLANCE INSTRUMENT CHECK CHECK CALIBRATION TEST REQUIRED 9.
STEAM GENERATOR BLOWOOWN VENT
- 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
W i
t-.
s TABLE 4.3-13 (Continued)
TABLE NOTATION At all times.
1 During waste gas holdup system operation (treatment for primary system offgases).
(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 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 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.
)
PWR-STS-I 3/4 3-84 i
I l
l i
~
3/4.11 RADIOACTIVE EFFLUENTS 3/4.11.1 LIQUID EFFLUENTS CONCENTRATION LIMITING CONDITION FOR OPERATION 3.11.1.1 The concentration of radioactive material released from the site (see Figure 5.1-4) shall be limited to the concentrations specified in 10 CFR Part 20, Appendix B, Table II, Column 2 for radionuclides other than dissolved or entrained noble gases.
For dissolved _gr entrained noble gases, the concentration shall be limited to 2 x 10 microcuries/ml total activity.
APPLICA8ILIT : At all times.
ACTION:
With the concentration of radioactive material released from the site exceeding the above limits, immediately restore the concentration to within the above limits.
SURVEILLANCE REQUIREMENTS 4.11.1.1.1 The radioactiv.ty content of each batch of radioactive liquid waste shall be determined prior to release by sampling and analysis in accordance with Table 4.11-1.
The results of pre-release analyses shall be used with the calculational methods in the ODCM to assure that the concentration at the point of release is maintained within the limits of Specification 3.11.1.1.
4.11.1.1.2 Post-release analyses of samples composited from batch releases shall be performed in accordance with Table 4.11-1.
The results of the previous post-release analyses shall be used with the calculational methods in the ODCM to assure that the concentrations at the point of release were maintained within the limits of Specification 3.11.1.1.
i 4.11.1.1.3 The radioactivity concentration of liquids discharged from continuous release points shall be determined by collection and analysis of samples in accordance with Table 4.11-1.
The results of the analyses shall be used with the calculational methods in the ODCM to assure that the concentrations at the point of release are maintained within the limits of Specification 3.11.1.1.
l l
PWR-STS-I 3/4 11-1
s TABLE 4.11-1 RADI0 ACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAM Lower Limit Minimum of Detection Liquid Release Sampling Analysis Type of Activity (LLD)
Type Frequency Frequency Analysis (pCi/ml)a A. Batch Waste P
P
-7 Release Each Batch Each Batch Principa) Gama 5x10 d
Tanks Emitters i
-6 I-131 1x10
-5 P
M Dissolved and 1x10 One Batch /M Entrained Gases (Gama emitters)
-5 P
M H-3 lx10 Each Batch Composite"
_7 Gross Alpha lx10
-6 P-32 lx10
-8 P
Q Sr-89, Sr-90 5x10 b
Each Batch Composite
-6 Fe-55 1x10
-7
'B.
Continuous
- W Principa} Gama 5x10 e
c Releases Continuous Composite Emitters
-6 I-131 1x10
-5 M
M Dissolved and 1x10 Grab Sample Entrained Gases (Gama Emitters)
-5 M
H-3 1x10 e
c Continuous Composite Gross Alpha lx10,
-6 P-32 lx10
-8 Q
Sr-89, Sr-90 5x10 e
c Continuous Composite
-6 Fe 55 1x10 i
PWR-STS-I 3/4 11-2 l
~
s l
TABLE 4.11-1 (Continued)
TABLE NOTATION a.
The LLD is the smallest concentration of radioactive material in a sample that will be detected with 95% probability with 5% probability of falsely concluding that a blank observation represents a "real" signal.
For a particular measurement system (which may include radiochemical separation):
4.66 s b D=
E V
2.22 x 106 Y
exp (-Mt)
Where:
LLO is the "a priori" lower limit of detection as defined ahve (as microcurie per unit mass or volume),
s is the standard deviation of the background counting rate or of htne counting rate of a blank sample as appropriate (as counts per minute),
E is the counting efficiency (as counts per transformation),
V is the sample size (in units of mass or volume),
2.22 x 108 is the number of transformations per minute per microcurie, Y is the fractional radiochemical yield (when applicable),
A is the radinactive decay constant for the particular radionuclide, and At is the elapsed time between midpoint of sample collection and time of counting (for plant effluents, not environmental samples).
The value of s used in the calculation of the LLD for a detection s
system shall bM based on the actual observed variance of the background counting rate or of the counting rate of the blank samples (as appropriate) rather than on an unverified theoretically predicted variance. Typical values of E, V, Y, and at shall be used in the calculation.
PWR-STS-I 3/4 11-3 i
l
TABLE 4.11-1 (Continued)
TABLE NOTATION b.
A 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 which is representative of the liquids released.
c.
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 throughly mixed in order for the colgosite sample to be representative of the effluent release.
d.
A 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, by a method described in the ODCM, to assure representative sampling.
e.
A continuous release is the discharge of liquid wastes of a nondiscrete volume; e.g., from a volume of system that has an input flow during the continuous release.
f.
The principal gamma emitters for which the LLD specification applias exclusively are the following radionuclides: Mn-54, Fe-59, Co-58, i
Co-60, Zn-65, Mo-99, Cs-134, Cs-137, Ce-141, and Ce-144. This list l
does not mean that only these nuclides are to be detected and reported.
Other peaks which are measurable and identifiable, together with the above nuclides, shall also be identified and reported.
PWR-STS-I 3/4 11-4
s RADI0 ACTIVE EFFLUENTS DOSE LIMITING CONDITION FOR OPERATION 3.11.1.2 The dose or dose commitment to an individual from radioactive materials in liquid effluents released, from each reactor unit, from the site (see Figure 5.1-4) shall be limited:
a.
During any calendar quarter to less than or equal to 1.5 mrem to the total body and to less than or equal to 5 mrem to any organ, and b.
During any calendar year to less than or equal to 3 mrem to the total body and to less than or equal to 10 mrem to any organ.
APPLICABILITY: At all times.
ACTION:
i a.
With the calculated dose from the release of radioactive materials in liquid effluents exceeding any of the above limits, in lieu of any other report required by Specification 6.9.1, prepare and submit to the Commission within 30 days, pursuant to Specification 6.9.2, a Special Report which identifies the cause(s) for exceeding the limit (s) and defines the corrective actions to be taken to reduce the releases of radioactive materials in liquid effluents during the remainder of the current calendar quarter and during the subsequent three calendar quarters, so that the cumulative dose or dose commitment to an individual from these releases is within 3 mrem to the total body and 10 mrem to any organ.
(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 141, Safe Drinking Water Act.")
b.
The provisions of specifications 3.0.3 and 3.0.4 are not applicable.
SURVEILLANCE REQUIREMENTS 4.11.1.2 Dose Calculations.
Cumulative dose contributions from liquid effluents shall be determined in accordance with the ODCM at least once per 31 days.
" Applicable only if drinking water supply is taken from the receiving water body.
PWR-STS-I 3/4 11-5
s RADIOACTIVE EFFLUENTS tTQUID WASTE TREATMENT LIMITING CONDITION FOR OPERATION 3.11.1.3 The liquid radwaste treatment system shall be OPERABLE. The appro-priate portions of the 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 the site (see Figure 5.1-4) when averaged over 31 days, would exceed 0.06 mrem to the total body or 0.2 mrem to any organ.
APPLICABILITY: At all times.
ACTION:
a.
With the liquid radwaste treatment system inoperable for more than 31 days or with radioactive liquid waste being disenarged without treatment and in excess of the above limits, in lieu of any other report required by Specification 6.9.1, prepare and submit to the Commission within 30 days pursuant to Specification 6.9.2 a Special Report which includes the following information:
1.
Identification of the inoperable equipment or subsystems and the reason for inoperability, 2.
Action (s) taken to restore the inoperable equipn.ent to OPERABLE status, and 3.
Summary description of action (s) taken to prevent e recurrence.
b.
The provisions of Specifications 3.0.3 and 3.0.4 are not aoplicable.
SURVEILLANCE REQUIREMENTS 4.11.1.3.1 Doses due to liquid releases shall be projected at least once per 31 days, in accordance with the ODCM.
4.11.1.3.2 The liquid radwaste treatment system shall be demonstrated OPERABLE by operating the liquid radwaste treatment system equipment for at least minutes at least once per 92 days unless the liquid radwaste system has been utilized to process radioactive liquid effluents during the previous 92 days.
PWR-STS-I 3/4 11-6 i
r
~
RADIOACTIVE EFFLUENTS LIQUID HOLOUP TANKS
- l LIMITING CONDITION FOR OPERATION 3.11.1.4 The quantity of radioactive material contained in each of the following i
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:
a.
With the quantity of radioactive material in any of the above listed tanks exceeding the above limit, immediately suspend all additions of radioactive material to the tank and 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 limit.
b.
The provisions of Specificati,&cs 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.
PWR-STS-I 3/4 11-7
RADIOACTIVE EFFLUENTS 3/4.11.2 GASEOUS EFFLUENTS DOSE RATE LIMITING CONDITION FOR OPERATION 3.11.2.1 The dose rate due to radioactive materials released in gaseous effluents from the site (see Figure 5.1-3) shall be limited to the following:
a.
For noble gases:
Less than or equal to 500 mrem /yr to the total body and less than or equal to 3000 mrem /yr to the skin, and b.
For all radioiodines and for all radioactive materials in particul-te form and radionuclides (other than noble gases) with half lives greater than 8 days:
Less than or equal to 1500 mrem /yr to any organ.
APPLIC/.BILITY: At all times.
ACTION:
With the dose rate (s) exceeding the above limits, immediately decrease the release rate to within the above limit (s).
SURVEILLANCE REQUIREMENTS 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 methods and procedures of the ODCM.
4.11.2.1.2 The dose rate due to radioactive materials, other than noble gases, in gaseous effluents shall be determined to be within the above limits in accordance with the methods and procedures of the ODCM by obtaining representative samples and performing analyses in accordance with the sampling and analysis program specified in Table 4.11-2.
l PWR-STS-I 3/4 11-8 l
u
$5 TABLE 4.11-2 RJDI0 ACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS PROGRAM Minimum Lower Limit of Saepling Analysis Type of Detection (gtD)
Gaseous Release Type Frequency frequency Activity Analysis (pCi/ml)
P P
~4 9
1x10 A.
Waste Gas Storage Each Tank Each Tank Principal Gamma Emitters Tank Grab Sample b
b 9
~4 B.
Containment Purge Each Purge Each Purge Principal Gamma Emitters 1x10 Grab
-6 Sample H-3 1x10 b
b 9
~4 w
C.
(List other release M,c.e M
Principal Gamma Emitters 1x10 A
points where gas-Grab
-6 3
eous effluents are Sample 11-3 1x10 discharged from the i*
facility)
I d
-12 0.
All Release Types Continuous W
I-131 1x10 as listed in A, B, Charcoal
-10 C above.
Sample I-133 1x10 I
d 9
1x10 '
~
Continuous W
Principal Gamma Emitters Particulate (I-131, Others)
Sample Continuous H
Gross Alpha 1x10"II I
Composite Particulate Sample I
~II Continuous Q
Sr-89, Sr-90 1x10 Composite Particulate Sample
-6 Continuous #
Noble Gas Noble Gases 1x10 Honitor Gross Beta & Gamma
h I
TABLE 4.11-2 (Continued)
TABLE NOTATION a.
The LLO is the smallest concentration of radioactive material in a sample that will be detected with 95% probability wich 5% probability of falsely concluding that a blank observation represents a real" signal.
For a particular measurement system (which may include radiochemical separation):
4'
$ D LLO =
E V
2.22 x 10*
Y exp (-Aat)
Where:
LLO is the "a priori" lower limit of detection as defined above (as microcurie per unit mass or volume),
s is the standard deviation of the background counting rate or of htne counting rate of a blank sample as appropriate (as counts per minute),
E is the counting efficiency (as counts per transformation),
V is the sample size (in units of mass or volume),
2.22 x 108 is the number of transformations per minute per microcurie, Y is the fractional radiochemical yield (when applicable),
A is the radioactive decay constant for the particular radionuclide, and at is the elapsed time between midpoint of sample collection and time of counting (for plant effluents, not environmental samples).
The value of s used in the calculation of the LLO for a detection h
system shall be based on the actual observed variance of the background counting rate or of the counting rate of the blank samples (as appropriate) rather than on an unverified theoretically predicted variance. Typical values of E, V, Y, and at shall be used in the calculation.
PWR-STS-I 3/4 11-10 I
1
S 1
TABLE 4.11-2 (Continued)
TABLE NOTATION b.
Analyses shall also be performed following shutdown, startup, or a THERMAL POWER change exceeding 15 percent of the RATED THERMAL POWER within a one hour period.
c.
Tritium grab samples shall be taken at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> when the refueling canal is flooded.
d.
Samples shall be changed at least once per 7 days 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 /> 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 /> sre analyzed, the corresponding LLD's may be increased by a factor of 10.
Tritium grab samples shall be taken at least once per 7 days from e.
the ventilation exhaust from the spent fuel pool area, whenever spent fuel is in the spent fuel pool.
I f.
The ratio of the sample flow rate to the sampled stream flow rate shall be known for the time period covered by each dose or dose rate calculation made in accordance with Specifications 3.11.2.1, 3.11.2.2 and 3.11.2.3.
g.
The 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, Ca-141 and Ce-144 for particulate emissions. This list does not mean that only these nuclides are to be detected and reported. Other peaks which are measureable and identifiable, together with the above nuclides, shall also be identified and reported.
S PWR-STS-I 3/4 11-11
s RAD.10 ACTIVE EFFLUENTS DOSE - NOBLE GASES LIMITING CONDITION FOR OPERATION 3.11.2.2 The air dose due to noble gases released in gaseous effluents, from each reactor unit, from the site (see Figure 5.1-3) shall be limited to the following:
a.
During any calendar quarter:
Less than or equal to 5 mrad for gamma radiation and less than or equal to 10 mrad for beta radiation and, b.
During any calendar year:
Less than or equal to 10 mrad for gamma radiation and less than or equal to 20 mrad for beta raciation.
y (The dose design objectives shall be reduced based on predicted 1
i noble gas releases from the turbine building if effluent sampling is not provided.
The dose design objectives shall also be reduced based on expected public occupancy of areas, e.g., beaches and visitor centers within the site boundary.)
APPLICABILITY: At all times.
ACTION a.
With the calculated air dose from radioactive noble gases in gaseous effluents exceeding any of the above limits, in lieu of any other report required by Specification 6.9.1, prepare and submit to the Commission within 30 days, pursuant to Specification 6.9.2, a Special Report which identifies the cause(s) for exceeding the limit (s) and defines the corrective actions to be taken to reduce the releases of radioactive noble gases in gaseous effluents during the remainder of the current calendar quarter and during the subsequent three calendar quarters, so that the cumulative dose is within (10) mrad for gamma radiation and (20) mrad for beta radiation.
b.
The provisions of Specifications 3.0.3 and 3.0.4 are r.at applicable.
SURVEILLANCE RE0VIREMENTS 4.11.2.2 Dose Calculations Cumulative dose contributions for the current calendar quarter and current calendar year shall be determined in accordance with the ODCM at least once per 31 days.
PWR*STS-I 3/4 11-12
4
.s RADI0 ACTIVE EFFLUENTS DOSE - RADIOI0 DINES, RADI0 ACTIVE MATERIALS IN PARTICULATE FORM, AND RADIONUCLIDES OTHER THAN NOBLE GASES LIMITING CONDITION FOR OPERATION 3.11.2.3 The dose '.o an individual from radioiodines and radioactive materials in particulate form, and radionuclides (other than noble gases) with half-lives greater than 8 days in gaseous effluents released, from each reactor unit, from l
the site (see Figure 5.1-3) shall be limited to the following:
a.
During any calendar quarter:
Less than or equal to 7.5 mrem to any organ and, b.
During any calendar year:
Less than or equal to 15 mrem to any organ.
APPLICABILITY: At all times.
ACTION:
a.
With the calculated dose from the release of radioiodines, radioactive materials in particulate form, or radionuclides (other than noble gases) with half l'ses greater than 8 days, in gaseous effluents t
exceeding an3 or the above limits, in lieu of any other report required by Specification 6.9.1, prepare and submit to the Commission within 30 days, pursuant to Specification 6.9.2, a Special Report which identifies the cause(s) for exceeding the limit and defines the corrective actions to be taken to reduce the releases of radio-iodines and radioactive materials in particulate form, and radio-nuclides (other than nobles gases) with half-lives greater than 8 days in gaseous effluents during the remainder of the current j
calendar quarter and during the subsequent three calendar quarters, so that the cumulative dose or dose commitment to an individual from these releases is within (15) mrem to any organ.
b.
The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.
I SURVEILLANCE REOUIREMENTS
'4.11.2.3 Dose Calculations Cumulative dose contributions for the current calendar quarter and current calendar year shall De determined in accordance with the ODCM at least once per 31 days.
PWR-STS-I 3/4 11-13 l
s RADI0 ACTIVE EFFLUENTS GASEOUS RA0 WASTE TREATMENT i
LIMITING CONDITION FOR OPERATION 3.11.2.4 The GASEOUS RADWASTE TRtATHENT SYSTEM and the VENTILATION EXHAUST TREATMENT SYSTEM shall be OPERABLE. The appropriate nortions of the GASEGUS RA0 WASTE TREATMENT SYSTEM shall be used to reduce rauicactive materials in gascous waste prior to their discharge when the projected gaseous effluent air doses due to gaseous Effluent releases from the site (see Figure 5.1-3), when averaged over 31 days, would exceed 0.2 mrad for gamina radiation and 0.4 mrad for beta radiation. The appropriate portions of the VENTILATION EXHAUST TREATMENT SYSTEM shall be used to reduce radioactive materials in gaseous waste prior to their discharge when the projected doses due to gaseous effluent releases from the site (see Figure 5.1-3) when averaged over 31 days would exceed 0.3 mrem to any organ.
APPLICABILITY: At all times.
ACTION:
a.
With the GASEOUS RA0 WASTE TREATMENT SYSTEM and/or the VENTILATION EXHAUST TREATMENT SYSTEM inoperable for more than " days or with gaseous waste being discharged without treatment i.id in excess of the above limits, in lieu of any other report required by Specifica-tion 6.9.1, prepare and submit to the Commission within 30 days, pursuant to Specification 6.9.2, a Special Report which includes the following information:
1.
Identification of the inoperable equipment or subsystems and the reason for inoperability, 2.
Action (s) taken to restore the inoperable equipment to OPERABLE status, and 3.
Summary description of action (s) taken to prevent a recurrence.
b.
The provisions of Specificatior.s 3.0.3 and 3.0.4 are not applicable.
SURVEILLANCE REQUIREMENTS 4.11.2.4.1 Doses due to gaseous releases from the site shall be projected at least once per 31 days, in accordance with the 00CM.
4.11.2.4.2 The GASEOUS RADWASTE TREATMENT SYSTEM and VENTILATION EXHAUST TREATMENT SYSTEM shall be demonstrated OPERABLE by operating the GASEOUS RADWASTE TREATMENT SYSTEM equipment and VENTILATION EXHAUST TREATMENT SYSTEM equipment for at least minutes, at least once per 92 days unless the appropriate system has been utilized to process radioactive gaseous effluents during the previous 92 days.
l PWR-STS-I 3/4 11-14 1
RADIOACTIVE EFFLUENTS EXPLOSIVE GAS MIXTURE (Systems designed to withstand a hydrogen explosion)
LIMITING CONDITION FOR OPERATION 3.11.2.5 The concentration of hydrogen or oxygen in the waste gas holdup system shall be limited to less than or equal to 4% by volume.
APPLICABILITY: At all times.
ACTION:
a.
With the concentration of hydrogen or oxygen in the waste gas holdup 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 />.
b.'
The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.
SURVEILLANCE REQUIREMENTS 4.11.2.5 The concentration of hydrocan or oxygen in the waste gas holdup system shall be determined to be within the above limits by continuously monitoring the waste gases in the waste gas holdup system with the hydrogen or oxygen monitors required OPERABLE by Table 3.3-13 of Specification 3.3.3.10.
PWR-STS-I 3/4 11-15
RADIDACTIVE EFFLUENTS EXPLOSIVE GAS MIXTURE (Systems not designed to withstand a hydrogen explosion)
LIMITING CONDITION FOR OPERATION 3.ll.2.5A The concentration of hydrogen and/or oxygen in the waste gas holdup 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 waste gas holdup system greater than 2% by volume but less than or equal to 4%
by volume, restore the concentration of hydrogen and/or 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 waste gas holdup 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 one hour.
c.
The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.
SURVEILLANCE REQUIREMENTS 4.ll.2.5A The concentrations of hydrogen and/or oxygen in the waste gas holdup system shall be determined to be within the above limits by continuously monitoring the waste gases in the waste gas holdup system with the hydrogen and/or oxygen monitors required OPERABLE by Table 3.3-13 of Specifica-tion 3.3.3.10.
i PWR-STS-I 3/4 11-16'
RADIOACTIVE EFFLUENTS
. EXPLOSIVE GAS MIXTURE (Hydrogen rich syste'ms not designed to withstand a hydrogen explosion) d LIMITING CONDITION FOR OPERATION 3.11.2.5B The concentration of oxygen in the waste gas holdup system shall be limited to less than or equal to 2% by volume whenever the hydrogen concentra-'
tion exceeds 4% by volume.'
APPLICABILITY: At all times.
ACTION:
a.
With the concentration of oxygen in the waste gas holdup system greater than 2% by volume but less than or equal 4% by volume, reduce the oxygen concentration to the above limits 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 oxygen in the waste gas holdup system greater than 4% by volume and the hydrogen concentration greater than 2% by volume, immediately suspend all additions of waste gases to the system and reduce the concentration of oxygen to less than or equal to 2% by volume within one hour.
c.
The provisions of Spcifications 3.0.3 and 3.0.4 are not applicable.
SURVEILLANCE REQUIREMENTS 4.11.2.58 The concentrations of hydrogen and oxygen in the waste gas holdup system shall be determined to be within tt.e above limits by continuously monitoring the waste gases in the waste gas holdup system with the hydrogen and oxygen monitors required OPERABLE by Table 3.3-13 of Specification 3.3.3.10.
l PWR-STS-I 3/4 11-17 l
1
5 RADIOACTIVE EFFLUENTS GAS STORAGE TANKS LIMITING CONDITION FOR OPERATION 3.11.2.6 The quantity of radioactivity contained in each gas storage tank shall be limited to less than or equal to curies noble gases (considered as Xe-133).
APPLICABILITY: At all times.
ACTION:
a.
With the quantity of radioactive material in any gas storage tank exceeding the above limit, immediately suspend all additions of radioactive material to the tank and 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 limit.
b.
The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.
SURVEILLANCE REOUIREMENTS 4.11.2.6 The quantity of radioactive material contained in each gas storage tank shall be determined to be within the above limit at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> when radioactive materials are being added to the tank.
PWR-STS-I-3/4 11-18
RADIOF,TIVE EFFLUENTS 3/4.11.3 SOLIO RADIOACTIVE WASTE LIMITING CONDITION.FOR OPERATION 3.11.3 The solid radwaste system shall be OPERABLE and used, as applicable in accordance with a PROCESS CONTROL PROGRAM, for the SOLIDIFICATION and packaging of radioactive wastes to ensure meeting the requirements of 10 CFR Part 20 and of 10 CFR Part 71 prior to shipment of radioactive wastes from the site.
APPLICABILITY: At all times.
ACTION:
a.
With the packaging requirements of 10 CFR Part 20 and/or 10 CFR Part 71 not satisfied, suspend shipments of defectively packaged solid radioactive wastes from the site.
b.
With the solid radwaste system inoperable for more than 31 days, in lieu of any other report required by Specification 6.9.1, prepare and submit to the Commission within 30 days pursuant to Specification 6.9.2 a Special Report which includes the following information:
1.
Identification of the inoperable equipment or subsystems and the reason for inoperability, 2.
Action (s) taken to restore the inoperable equipment to OPERABLE status, 3.
A description of the alternative used for SOLIDIFCATION and packaging of radioactive wastes, and 4.
Summary description of action (s) taken to prevent a recurrence.
c.
The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.
SURVEILLANCE REQUIREMENTS 4.11.3.1 The solid radwaste system shall be demonstrated OPERABLE at least once per 92 days by:
[
a.
Operating the solid radwaste system at least once in the previous 92 days in accordance with the PROCESS CONTROL PROGRAM, or b.
Verification of the existence of a valid contract for SOLIDIFICATION to be performed by a~ contractor in accordance with a PROCESS CONTROL PROGRAM.
_PWR-STS-I_
3/4 11-19
s RADIOACTIVE EFFLUENTS SURVEILLANCE REQUIREMENTS (Continued) 4.11.3.2 THE PROCESS CONTROL PROGRAM shall be used to verify the SOLIDIFICA-TION of at least one representative test specimen from at least every tenth batch of each type of wet radioactive waste (e.g., filter:51udges, spent resins, evaporator bottoms, boric acid solutions, and sodium sulfate solutions).
a.
If any test specimen fails to verify SOLIDIFICATION, the SOLIDIFICA-TION of the batch under test shall be suspended until such time as additior,al test specimens can be obtained, alternative SOLIDIFICATION parameters can be determined in accordance with the PROCESS CONTROL PROGRAM, and a subsequent test verifies SOLIDIFICATION.
SOLIDIFICATION of the batch may then be resumed using the alternative SOLIDIFICATION parameters determined by the PROCESS CONTROL PROGRAM.
4 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.
t 1
PWR-STS-I 3/4 11-20 i
RADI0 ACTIVE EFFLUENTS 3/4.11.4 TOTAL DOSE LIMITING CONDITION FOR OPERATION 3.11.4 The dose or dose commitment to any member of the public, due to releases of radioactivity and radiation, from uranium fuel cycle sources shall be limited to less than or equal to 25 mrem to the total body or any organ (except the thyroid, which shall be limited to less than or equal to 75 mrem) over 12 consecutive months.
APPLICABILITY: At all times.
ACTION:
a.
With the calculated doses from the release of radioactive materials in liquid or gaseous effluents exceeding twice the limits of Specifica-tion 3.ll.1.2.a, 3.ll.1.2.b, 3.11.2.2.a, 3.11.2.2.b, 3.11.2.3.a, or 3.11.2.3.b, in lieu of any other report required by Specification 6.9.1, prepare and submit a Special Report to the Director, Nuclear Reactor Regulation, U.S. Nuclear Regulatory Commission, Washington, D.C.
20555, within 30 days, which defines the corrective action to be taken to reduce subsequent releases to prevent recurrence of exceeding the limits of Specification 3.11.4.
This Special Report shall include an analysis which estimates the radiation exposure (dose) to a member of the public from uranium fuel cycle sources (including all effluent pathways and direct radiation) for a 12 consecutive month period that includes the release (s) covered by this report.
If the estimated dose (s) exceeds the limits of Specification 3.11.4, and if the release condition resulting in violation of 40 CFR 190 has not already been corrected, the Special Report shall include a request for a variance in accordance with the provisions of 40 CFR 190 and including the specified information of 9 190.11(b). Submittal of the report is considered a timely request, and a variance is granted until staff action on the request is complete.
The variance only relates to the limits of 40 CFR 190, and does not apply in any way to the requirements for dose limitation of 10 CFR Part 20, as addressed in other sections of this technical specification.
b.
The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.
SURVEILLANCE REOUIREMENTS 4.11.4 Dose Calc :lations Cumulative dose contributions from liquid and gaseous effluents snall be determined in accordance with Specifications 4.11.1.2, 4.11.2.2, and 4.11.2.3, and in accordance with the ODCM.
i i
PWR-STS-I 3/4 11-21
1
.+
e 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:
a.
With the radiological environmental monitoring program not being conducted as specified in Table 3.12-1, in lieu of any other report required by Specification 6.9.1, prepare and submit to the Commission, in the Annual Radiological Operating Report, a description of the reasons for not conducting the program as required and the plans for preventing a recurrence, b.
With the level of radioactivity in an environmental sampling medium exceeding the reporting levels of Table 3.12-2 when averaged over any calendar quarter, in lieu of any otner report required by Specification 6.9.1, prepare and submit to the Commission within 30 days from the end of the affected calendar quarter a Report pursuant to Specification 6.9.1.13.
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 limit level (1) limit 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 an individual 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.
c.
With milk or fresh leafy vegetable samples unavailable from one or more of the sample locations required by Table 3.12-1, in lieu of any other report required by Specification 6.9.1, prepare and submit to the Commission within 30 days, pursuant to Specification 6.9.2, a Special Report which identifies the cause of the unavailability of samples and identifies locations for obtaining replacement samples.
The locations from which samples were unavailable may then be deleted from those required by Table 3.12-1, provided the locations from which the replacement samples were obtained are added to the environmental monitoring program as replacement locations.
d.
The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.
i PWR-STS-I 3/4 12-1
RADIOLOGICAL ENVIR0tNENTAL NGNITORING SURVEILLANCE REQUIREMENTS 4.12.1 The radiological environmental monitoring samples shall be collected pursuant to Table 3.12-1 from the locations given in the table and figure in the 00CM and shall be analyzed pursuant to the requirements of Tables 3.12-1 and 4.12-1.
L PWR-STS-I 3/4 12-2
TABLE 3.12-1
,.c
[
RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM d.
~
Number of Samples Exposure Pathway and Sampling and Type and frequency and/or Sample Sample Locations **
Collection Frequency of Analysis 1.
AIRBORNE Radioiodine and (Locations 1-5)
Continuous operation of Radiofodine canister.
Particulates sampler with sample col-Analyze at least once lectica as required by per 7 days for I-131.
dust loading but at least once per 7 days.
Particulate sampler.
Analyze for gross beta radioactivity > 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> following filter change.
w D
Perform gamma isotopic analysis on each sample 7
ross beta activity when g'10 times the yearly is >
mean of control samples.
Perform gamma isotopic analysis on composite (by location) sample at least once per 92 days.
2.
DIRECT RADIATION (Locations 6-45)
At least once per 31 days.
Gamma dose. At least
> 2 dosimeters or > 1 once per 31 days.
gp Instrument for con; or tinuously measuring At least once per 92 days.
Gamma dose. At least and recording dose (Read-out frequencies are once per 92 days.
rate at each determined by type of dosi-location.
meters selected.)
^^ Sample locations are given on the figure and table in the ODCH.
TABLE 3.12-1 (Continued)
E
?'
RADIOLOGICAL ENVIRONMENTAL HONITORING PROGRAM U
T Number of Samples Exposure Pathway and Sampling and Type and frequency and/or Sample Sample Locations **
Collection Frequency of Analysis 3.
WATERBORNE a.
Surface (Locations 46 and 47)
Composite
- sample collected Gamma isotopic analysis over a period of 5 31 days.
of each composite sample.
Tritium analysis of com-posite sample at least once per 92 days.
b.
Ground (Locations 48 and 49)
At least once per 92 days.
Gamma isotopic and tritium analyses of each ca);
sample.
55 c.
Drinking (Locations 50-52)
Composite
- sample collected I-131 analysis of each over a period of < 14 days, composite sample; if I-131 analysis is and performed; or Composite
- sample collected Gross beta and gamma over a period of 5 31 days.
isotopic analysis of each compcsite sample.
Tritium analysis of composite sample at least once per 92 days.
d.
Sediment from (Locations 53)
At least once per 184 days.
Gamma isotopic analysis Shoreline of each sample.
- Composite samples shall be collected by collecting an aliquot at intervals not exceeding 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.
- Sample locations are shown on the figure in the 00CH.
r
~
an f
TABLE 3.12-1 (Continued) m5 03 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM d'
Number of Samples Exposure Pathway and Sampling and Type and frequency and/or Sample Sample Locations **
Collection Frequency of Analysis 4.
INGESTION a.
Milk (Locations 54-57)
At least once per 15 days Gamma isotopic and when animals are on pasture; I-131 analysis at least once per 31 days of each sample.
at other tirnes.
b.
Fish and (Locations 58 and 59)
One sample in season, or at Gamma isotopic analysis Invertebrates least once per 184 days if on edible portions.
40 not seasonal. One sample of each or the following species:
N di 1.
2.
c.
Food Products (Locations 60-62)
At time of harvest. One Gamma isotopic analysis sample of each of the fol-on edible portion.
lowing classes of food products:
1.
2.
3.
(Location 63)
At time of harvest. One I-131 analysis.
sample of broad leaf vegetation.
- Sample Incations are shown on the figure in the ODCM.
a*
TABLE 3.12-2 7i' REPORTING LEVELS FOR RADI0 ACTIVITY CONCENTRATIONS IN ENVIRONNENTAL SAMPLES wd B~
Reporting Levels Water Airborne Particulate Fish Milk Food Products Analysis (pCi/1) or Gases (pCi/m )
(pCi/Kg, wet)
(pCi/1)
(pCi/Kg, wet) 3 4( }
H-3 2 x 10 3
4 Mn-54 1 x 10 3 x 10 2
4 Fe-59 4 x 10 1 x 10 3
4 Co-58 1 x 10 3 x 10 2
4 Co-60 3 x 10 1 x 10 h
Zn-65 3 x 10 2 x 10 2
4 2
Zr-Nb-95 4 x 10 2
I-131 2
0.9 3
1 x 10 3
3 Cs-134 30 10 1 x 10 60 1 x 10 3
3 Cs-137 50 20 2 x 10 70 2 x 10 2
2 Ba-La-140 2 x 10 3 x 10 (a) For drinking water samples. This is 40 CFR Part 141 value.
TABLE 4.12-1 MAXIMUM VALUES FOR Tile LOWER LIMITS OF DETECTION (LLD)a,c a
.L Airborne Particulate Water or Ga3 Fish Milk Food Products Sediment Analysis (pCi/1)
(pCi/m )
(pCi/kg, wet)
(pCi/1)
(pCi/kg, wet)
(pCi/kg, dry)
-2 gross beta 4
1 X 10 ll-3 2000 Hn-54 15 130 Fe-59 30 260 Co-58, 60 15 130 Zn-65 30 260 h
Zr-95 30 y
Nb-95 15 b
-2 I-131 l
7 X 10 1
60
-2 Cs-134 15 5 X 10 130 15 60 150
-2 Cs-137 18 6.X 10 150 18 80 180
't Ba-140 60 60 La-140 15 15 1
TABLE 4.12-1 (Continued)
TABLE NOTATION a.
The LLD is the smallest concentration of radioactive material in a sample that will be detected with 95% probability with 5% probability of falsely concluding that a blank observation represents a "real" signal.
For a particular measurement system (which may include raciochemical,
separation):
4.66 s b LLD = E V
2.22 Y
exp(-Aat)
Where:
LLD is the "a priori" lower limit of detection as defined above (as picocurie per unit mass or volume),
s is the standard deviation of the background counting rate or of btne colmting rate of a blank sample as appropriate (as counts per minute),
E is the counting efficiency (as counts per transformation),
V is the sample size (in units of mass or volume),
2.22 is the number of transformation per minute per picocurie, Y is the fractional radiochemical yield (when applicable),
A is the radioactive decay constant for the particular radionuclide, and at is the elapsed time between sample collection (or end of the sample collection period) and time of counting (for environmental samples, not plant effluent samples).
The value of s used in the calculation of the LLD for a detection systen.
b shall be based on the actual observed variance of the background counting rate or of the counting rate of the blank samples (as appropriate) rather than on an unverified theoretically predicted variance.
In calculating the LLD for a radionuclide determined by gamma-ray spectrometry, the background shall include the typical contributions of other radionuclides normally present in the samples (e.g., potassium-40 in milk samples).
Typical values of E, V, Y and at shall be used in the calec'ations.
PWR-STS-I 3/4 12-8
t s
TABLE 4.12-1 (Continued)
TABLE NOTATION b.
LLD for drinking water.
c.
Other peaks which are measurable and identifiable, together with the radionuclides in Table 4.12-1, shall be identified and reported.
4 4
i e
i t
PWR-STS-I
-3/4 12-9
's RADIOLOGICAL ENVIRONMENTAL MONITORING 3/4.12.2 LAND USE CENSUS LIMITING CONDITION FOR OPERATION 3.12.2 A land use census shall be conducted and shall identify the location of the nearest milk animal, the nearest residence and the nearest garden
- of greater than 500 square feet producing fresh leafy vegetables in each of the 16 meteorological sectors within a distance of five miles.
(For elevated releases as defined in Regulatory Guide 1.111, Revision 1, July 1977, the land use census shall also identify the locations of all milk animals and all gardens of greater than 500 square feet producing fresh leafy vegetables in each of the 16 meteorological sectors within a distance of three miles.)
APPLICABILITY: At all times.
ACTION:
With a land use census identifying a location (s) which yields a a.
calculated dose or dose commitment greater than the values currently being calculated in Specification 4.11.2.3, in lieu of any other report required by Specification 6.9.1., prepa.re and submit to the Commission within 30 days, pursuant to Specification 6.9.2, a Special Report which identifies the new location (s).
b.
With a land use census identifying a location (s) which yields a calculated dose or dose commitment (via the same exposure pathway) 20 percent greater than at a location from which samples are currently being obtained in accordance with Specification 3.12.1, in lieu of any other report required by Specification 6.9.1, prepare and submit to the Commission within 30 days, pursuant to Specification 6.9.2, a Special Report which identifies the new location. The new location shall be added to the radiological environmental monitoring program within 30 days. The sampling location, excluding the control station location, having the lowest calculated dose or dose commitment (via the same exposure pathway) may be deleted from this monitoring program after (October 31) of the year in which this land use census was conducted.
The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.
c.
SURVEILLANCE REQUIREMENTS 4.12.2 The land use census shall be educted at least once per 12 months between the dates of (June 1 and Octooer 1) using that information which will provide the best results, such as by a door-to-door survey, aerial survey, or by consulting local agriculture authorities.
" Broad leaf vegetation sampling may be performed at the site boundary in the direction sector with the highest 0/Q in lieu of the garden census.
PWR-STS-I 3/4 12-10
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 i
of an Interlaboratory Comparison Program which has been approved by the Commission.
APPLICABILITY: At all times.
ACTION:
a.
With analyses not being performed as required above, report the corrective actions taken to prevent a recurrence to the Commission in the Annual Radiological Environmental Operating Report.
b.
The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.
SURVEILLANCE REQUIREMENTS I
4.12.3 A summary of the results obtained as part of the above req'; ired Inter-laboratory Comparison Program and in accordance with the ODCM (or participants in the EPA ctosscheck program shall provide the EPA program code designation i
for the unit) shall be included in the Annual Radiological Environmental Operating Report.
1 l
l l
PWR-STS-I 3/4 12-11
INSTRUMENTATION BASES 3/4.3.3.9 RADI0ACTIVELIQUIDEFFLUENTINSTRUMFjlTATION The radioactive liquid effluent instrumentation is provided to monitor and control, as applicable, the releases of radioactive materials in liquid effluents during actual or potential releases of liquid effluents. The alarm /
trip setpoints for these instruments shall be calculated in accordance with the procedures 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.
3/4.3.3.10 RADI0 ACTIVE GASEOUS EFFLUENT INSTRUMENTATION The radf oactive gaseous effluent instrumentation is provided to monitor and control, as applicable, the releases of radioactive materials in gaseous effluents during actual or potential releases of gaseous effluents. The alarm / trip setpoints for these instruments shall be calculated in accordance with the procedures 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 requiraments of General Design Criteria 60, 63 and 64 of Appendix A to 10 CFR Part 50.
PWR-STS-I B 3/4 3-5 l
s S
3/4.11 RADI0 ACTIVE EFFLUENTS BASES 3/4.11.1 LIQUID EFFLUENTS 3/4.11 1.1 CONCENTRATION
'his specification is provided to ensure that the concentration of radio-activi materials released in liquid waste effluents from the site will be less than he concentration levels specified in 10 CFR Part 20, Appendix B, Table II, Cslumn 2.
This limitation provides additional assurance taat the levels of rasicactive materials in bodies of water outside the site will result in expo: Jres within (1) the Section II.A design objectives of Appendix I, 10 CFR 50, 7 o an individual, and (2) the limits of 10 CFR 20.106(e) to the population.
The eoncentration limit for dissolved or entrained noble gases is based upon the issumption that Xe-135 is tne controlling radioisotope and its MPC in air (sut; ersion) was converted to an equivalent concentration in water using the methods described in International Commission on Radiological Protection (ICRP) Publication 2.
3/4.11.1.2 DOSE This specification is provided to implement the requirements of Sections II.A, III.A and IV.A of Appendix I, 10 CFR Part 50.
The Limiting Condition for Operation implements the guides set forth in Section II. A of Appendix I.
The ACTION statements provide the required operating flexibility and at the same time implement the guides set forth in Section IV.A of Appendix I to assure that the releases of radioactive material in liquid effluents will be kept "as low as is reasonably achievable." Alsu, for fresh water sites with drinking water supplies which 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 141.
The dose calculations in the ODCM implement the requirements in Section III.A of Appendix I that conformance with the guides of Appendix I be shown by calculational procedures based on models and data, such that the actual exposure of an individual through appro-priate a Mways is unlikely to be substantially underestimated. The equations specif'.d in the ODCM for calculating the doses due to the actual release rates ef radioactive materials in liquid effluents are consistent with the methodology provided in Regulatory Guide 1.109, " Calculation of Annual Doses to Man from Rou* Ine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I," Revision 1, October 1977 and Regulatory Guide 1.113, " Estimating Aquatic Dispersion of Effluents frem Accidental and Routine Reactor Releases for the Purpose of Implementing Appendix I," April 1977.
This specification applies to the release of liquid effluents from each reactor at the site. For unics with shared radwaste treatment systems, the liquid effluents from the s>.ared system are proportioned among the units sharing that system.
PWR-STS-I B 3/4 11-1
s s
RADIOACTIVE EFFLUENTS BASES 314.11.1.3 LIQUID WASTE TREATMENT The OPERABILITY of the liquid radwaste treatment system ensures that this system will be available for use whenever liquid effluents require treatment prior to release to the environment. The requirement that the appropriate portions of this system be used when specified provides assurance that the releases of radioactive materials in liquid 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 limits 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.
3/4.11.1.4 LIOUID HOLDUP TANKS 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 Part 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 the site boundary from gaseous effluents from all units on the site will be within the annual aose limits of 10 CFR Part 20 for 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 assurance that radioactive material discharged in gaseous effluents will not result in the exposure of an individual in an unrestricted area, either within or outside the site boundary, to annual atarage concentrations exceeding the limits specified in Appendix B, Table II of 10 CFR Part 20 (10 CFR Part 20.106(b)).
For individuals who may at times be within the site boundary, the occupancy of the individual will be sufficiently low to compensate for any increase in the atmospheric diffusion factor above that for the site boundary.
The specified release rate limits restrict, at all times, the corresponding gamma and beta dose rates above background to an individual at or beyond the site boundary to less than or equal to 500 mrem / year to the total body or to less than or equal to 3000 mrem / year to the skin. These release rate limits also restrict, at all times, the corresponding thyroid dose rate above background to an infant via the cow-milk-infant pathway to less than or equal to 1500 mrem /
year for the nearest cow to the plant.
PWR-STS-I B 3/4 11-2
.s RADIOACTIVE EFFLUENTS BASES This specification applies to the release of gaseous effluents from all reactors 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.
3/4.11.2.2 DOSE - NOBLE GASES 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 gaseous effluents will be kept "as low as is reasonably achievable".
T' i Surveillance Requirements implement the requirements in Section III.A of Ap dix I that conformance with the guides of Appendix I be shown by calcul onal procedures based on models and data such that the actual exposure of an individual through appropriatt: pathways is unlikely to be substantially underestimated. The dose calculations established in the ODCM for calculating the doses due to the actual release rates of radioactive noble gases in gaseous effluents 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. The 00CM equations provided for determining the air doses at the site boundary are based upon the historical average atmospheric conditions.
3/4.11.2.3 DOSE - RADI0 IODINES, RADIOACTIVE MATERIALS IN PARTICULATE FORM AND RADIONUCLIDES OTHER THAN NOBLE GASES This specification is provided to implement the requirements of Sections II.C, III. A and I'.'. A of Appendi < I,10 CFR Part 50. The Limiting Conditions for Opera-tion are the guides set forth in Section II.C of Appendix I.
The ACTION state-ments 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 will be kept "as low as is reasonably achievable." The 00CM 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 calcula-tional procedures based on models and oata, such that the actual exposure of an individual through appropriate pathways is unlikely to be substantially underestimated. The ODCM calculational methods for calculating the doses due to the actual release rates of the subject materials are consistent with the methodology provided in Regulatory Guide 1.109, " Calculation of Annual Doses PWR-STS-I B 3/4 11-3
's l
l l
l RADIOACTIVE EFFLUENTS i
BASES l
to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating i
Compliance with 10 CFR Part 50, Appendix I," Revision 1, October 1977 and J
t Regulatory Guide 1.111, " Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light-Water-Cooled Reactors," Revisien 1, July 1977. These equations also provide for determining the actual doses based upon the historical average atmospheric conditions.
The release rate specifications for radiofodines, radioactive materials in i
particulate form and radionuclides other than noble gases are dependent on the existing radionuclide pathways to man, in the unrestricted area.
The pathways I
which were examined in the development of these calculations were:
- 1) individual inhalation of airborne radionuclides, 2) deposition of radionuclides onto I
green leafy vegetation with subsequent consumption by man, 3) deposition onto grassy areas where milk animals and meat producing animals graze with consump-tion of the milk and meat by man, and 4) deposition on the ground with subsequent exposure of man.
3/4.11.2.4 GASEOUS RADWASTE TREATMENT The OPERABILITY of the GASEOUS RADWASTE TREATMENT SYSTEM and the VENTILA-TION EXHAUST TREATMENT SYSTEM ensures that the systems will be available for use whenever gaseous effluents require treatment prior to release to the environment. The ri!quirement that the appropriate portions of these systems i
be used, when specifleid, provides reasonable assurance that the releases of radioactive materials in gaseous 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 objectives given in Section II.D of Appendix I to 10 CFR Part 50. The specified limits governing the use of appropriate portions of the systems were specified as a suitable fraction of the dose design objectives set forth in Sections II.B and II.C of Appendix I, 10 CFR Part 50, for gaseous effluents.
3/4.11.2.5 EXPLOSIVE GAS MIXTURE This specification is provided to ensure that the concentration of potentially explosive gas mixtures contained in the waste gas holdup system is i
maintained below the flammability limits of hydrogen and oxygen.
(Automatic control features are included in the system to prevent the hydrogen and oxygen concentrations from reaching these flammability limits.
These automatic control features include isolation of the source of hydrogen and/or oxygen, automatic diversion to recombiners, or injection of dilutants to reduce the concentration below the flammability limits.) Maintaining the concentration of hydrogen and oxygen below their flammability limits provides assurance that j
the releases of radioactive materials will be controlled in conformance with i
the requirements of General Design Criterion 60 of Appendix A to 10 CFR Part 50.
PWR-STS-I B 3/4 11-4
s RADIOACTIVE EFFLUENTS BASES 3/4.11.2.6 GAS STORAGE TANKS Restricting the quantity of radioactivity contained in each gas storage tank provides assurance that in the event of an uncontrolled release of the tank's contents, the resulting total body exposure to an individual at the nearest exclusion area boundary will not exceed 0.5 rem.
This is consistent with Standard Review Plan 15.7.1, " Waste Gas System Failure".
3/4.11.3 SOLID RADI0 ACTIVE WASTE The OPERABILITY of the solid radwaste sysiem ensures that the system will be available for use whenever solid radwastes require processing and packaging prior to being shipped offsite. This specification implements the requirements of 10 CFR Part 50.36a and General Design Criterion 60 of Appendix A to 10 CFR Part 50.
The process parameters included in establishing the PROCESS CONTROL PROGRAM may include, but are not limited to waste type, waste pH, waste / liquid /
solidification agent / catalyst ratios, waste oil content, waste principal chemical constituents, mixing and curing times.
3/4.11.4 TOTAL DOSE This specification is provided to meet the dose limitations of 40 CFR 190. The specification requires the preparation and submittal of a Special Report whenever the calculated doses from plant radioactive effluents exceed twice the design objective doses of Appendix I.
For sites containing up to 4 reactors, it is highly unlikely that the resultant dose to a member of the public will exceed the dose limits of 40 CFR 190 if the individual reactors remain within the reporting requirement level. The Special Report will describe a course of action which should result in the limitation of dose to a member of the public for 12 consecutive months to within the 40 CFR 190 limits.
For the purposes of the Special Report, it may be assumed that the dose c:nmit-ment 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 the same site or within a radius of 5 miles must be con-sidered.
If the dose to any member of the public is estimated to exceed the requirements of 40 CFR 190, the Special Report with a request for a variance (provided the release conditions resulting in violation of 40 CFR 190 have not already been corrected), in accordance with the provisions of 40 CFR 190.11, is considered to be a timely request and fulfills the requirements of 40 CFR 190 until NRC staff action is completed. An individual is not considered a member of the public during any period in which he/she is engaged in carring out any operation which is part of the nuclear fuel cycle.
PWR-STS-I B 3/4 11-5
3/4.12 RADIOLOGICAL ENVIRONMENTAL MONITORING BASES 3/4.12.1 MONITORING PROGRAM The radiological monitoring program required by this specification provides measurements of radiation and of radioactive materials in those exposure pathways and for those radionuclides, which lead to the highest potential radiation exposures of individuals resulting from the station operation. This monitoring program thereby supplements the radiological effluent monitoring program Dy verifying that the measurable concentrations of radioactive materials and levels of radiation are not higher than expected on the basis of the effluent measurements and modeling of the environmental exposure pathways.
The initially specified monitoring program will be effective for at least the first three years of commercial operation.
Following this period, program changes may be initiated based on operational experience.
The detection capabilities required by Table 4.12-1 are state-of-the-art for routine environmental measurements in industrial laboratories.
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 not as a posteriori (after the fact) limit for a particular measurement. Analyses shall be per-formed in such a manner that the stated LLDs will be achieved under routine conditions. Occasionally background fluctuations, unavoidably small sample sizes, the presence of interferring nuclides, or other uncontrollable circum-stances may render these LLDs unachievable.
In such cases, the contributing factors will be identified and described in the Annual Radiological Environ-mental Operating Report.
3/4.12.2 LAND USE CENSUS This specification is provided to ensure that changes in the use of unrestricted areas are identified and that modifications to the monitoring program are made if required by the results of this census. The best survey information from the door-to-door, aerial or consulting with local agricultural authorities shall be used. This census satisfies the requirements of Section IV.B.3 of Appendix I to 10 CFR Part 50.
Restricting the census to gardens of greater than 500 square feet provides assurance that significant exposure pathways via leafy vegetables 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 used, 1) that 20% of the garden was used for growing broad leaf vegetation (i.e.,
similar to lettuce and cabbage), and 2) a vegetation yield of 2 kg/ square meter.
PWR-STS-I B 3/4 12-1 I
I
RADIOLOGICAL ENVIRONMENTAL MONITORING BASES 3/4.12.3 INTERLABORATORY COMPARISON PROGRAM The requirement for participation in an Interlaboratory Comparison Program is provided to ensure that independent checks on the precision and accuracy of the measurements of radioactive material in environmental sample matrices are performed as part of the quality assurance program for environmental monitoring in order to demonstrate that the results are reasonably valid.
O PWR-STS-I B 3/4 12-2
5.0 DESIGN FEATURES 5.1 SITE EXCLUSION AREA 5.1.1 The exclusion area shall be as shown in Figure 5.1-1.
LOW POPULATION ZONE 5.1.2 The fow population zone shall be as shown in Figure 5.1-2.
SITE BOUNDARY FOR GASEOUS EFFLUENTS 5.1.3 The site boundary for gaseous effluents shall be as shown in Figure 5.1-3.
SITE BOUNDARY FOR LIQUID EFFLUENTS 5.1.4 The site boundary for liquid effluents shall be as shuwn in Figure 5.1-4.
5.2 CONTAINMENT CONFIGURATION 5.2.1 The reactor containment building is a steel lined, reinforced concrete building of cylindrical shape, with a dome roof and ns.4ng the following design features:
a.
Nominal inside diameter =
feet.
b.
Nominal inside height =
feet.
c.
Minimum thickness of concrete walls =
feet.
d.
'4inimum thickness of concrete roof =
- feet, e.
Minimum thickness of concrete ficor pad =
feet.
f.
Nominal thickness of steel liner =
inches.
g.
Net free volume =
cubic feet.
DESIGN PRESSURE AND TEMPERATURE 5.2.2 The reactor containment building is designed and shall be maintained for a maximum internal pressure of psig and a temperature of F.
PWR-STS-I 5-1
4 This figure shall consist of a map of the site area and provide, at a minimum, the information described in Section (2.1.2) of the FSAR and meteorological tower location.
EXCLUSION AREA l
FIGURE 5.1-1 PWR-STS-I 5-2
~
This figure shall consist of a map of the site area showing the Low Population Zone boundary.
Features such as towns, roads and recreational areas sha'l be indicated in sufficient detail to allow identification of significant shifts in population distribution within the LPZ.
LOW POPULATION ZONE FIGURE 5.1-2 Y
PWR-STS-I 5-3 l
h,e
(
l
4 1
This figure shall consist of a map of the site area showing the perimeter of the site and locating the points where gaseous effluents are released.
If on-site land areas subject to radioactive materials in gaseous waste are utilized by the public for recreational or other purposes, then these areas shall be identified by occupancy factors and the licensee's method of occupancy control. The figure shall be sufficiently detailed to allow identification of structures and relecse point elevations, and areas within the site boundary that are accessible by members of the general public.
See NUREG-0133 for additional guidance.
SITE 8000ARY FOR GASEOUS EFFLUENTS FIGURE 5.1-3
{
PWR-STS-I 5-4
This figure shall consist of a map of the site area showing the perimeter of the site and locating the points where liquid effluent leaves the site.
If on-site water areas containing radioactive wastes are utilized by the public for recreational or other purposes, the points of release to these water areas shall be identified. The figure shall be sufficiently detailed to allow identifica-tion of structures near the release points and areas within the site. boundary where ground and surface water is accessible by members of the general publ.
See NUREG-0133 for additional guidance.
SITE BOUNDARY FOR LIQUID EFFLUENTS FIGURE 5.1-4 l
l PWR-STS-I 5-5 i
ALL STS-1 SECTION 6.0' ADMINISIEA
e 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 every unplanned onsite release of radioactive material to the environs including the preparation and forwarding of reports covering evaluation, recommendations and disposition of the corrective action to prevent recurrence to the (Superintendent of Power Plants) and to the (Company Nuclear Review and Audit Group).
1.
Review of changes to the PROCESS CONTROL PROGRAM, OFFSITE DOSE CALCULATION MANUAL, and radwaste treatment systems.
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:
1.
The radiological environmental monitoring program and the results thereof at least once per 12 months.
m.
The OFFSITE DOSE CALCULATION MANUAL and implementing procedures at least once per 24 months.
n.
The PROCESS CONTROL PROGRAM and implementing procedures for solidifica-tion of radioactive wastes at least once per 24 months.
o.
The performance of activities required by the Quality Assurance Program to meet the criteria of Regulatory Guide 4.15, December 1977 at least once per 12 months.
6.8 PROCEDURES 6.8.1 Written procedures shall be established, implemented and maintained j
covering the activities referenced below:
l l
g.
PROCESS CONTROL PROGRAM implementation.
I h.
OFFSITE DOSE CALCULATION MANUAL implementation.
i.
Quality Assurance Program for effluent and environmental monitoring, using the guidance in Regulatory Guide 4.15, December 1977.
ALL STS-I 6-1
f 4
ADMINISTRATIVE CONTROLS ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORTS 6.9.1.6 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.
- 6. 9.1. 7 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 comparison with preoperational studies, operational controls (as appropriate), and 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. If harmful effects or evidence of irreversible damage are detected by the monitoring, the report shall provide an analysis of the problem and a planned course of action to alleviate the problem.
The annual radiological environmental operating reports shall include summarized and tabulated results in the format of Regulatory Guide 4.8, December 1975 of all radiological environmental samples taken during the report period.
In the event that some results are not available for inclusion with the report, the report shall be submitted noting and explaining the reasons for the missing results.
The missing data shall be submitted as soon as possible in a supplementary report.
The reports shall alto include the following:
a summary description of the radiological environmental monitoring program; a map of all sampling locations keyed to a table giving distances and directions from one reactor; and the results of licensee participation in the Interlaboratory Comparison Program, required by Specification 3.12.3.
SEMIANNUAL RADI0 ACTIVE EFFLUENT RELEASE REPORTSI 6.9.1.8 Routine radioactive effluent release reports covering the operation of the unit during the previous 6 months of operation shall be submitted within 60 days after January 1 and July 1 of each year.
The period of the first report shall begin with the date of initial criticality.
3/
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.
ALL STS-I 6-2
,,e 1
ADMINISTRATIVE CONTROLS 6.9.1.9 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 quarterly basis following the format of Appendix B thereof.
l The radioactive effluent release report to be submitted 60 days after January 1
{
of each year shall include an annual summary of hourly meteorological data collected over the previous year. This annual summary may be either in the 4
form of an Sour-by-hour listing of wind speed, wind direction, and atmospheric stability, and precipitation (if measured) on magnetic tape, or in the form of joint frequency distributions of wind speed, wind direction, and atmospheric stability. This same report shall include an assessment of the Odiation doses due to the radioactive liquid and gaeous effluents releaseo 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 (Figures 5.1-3 and 5.1-4) during the report period. All assump-tions used in making these assessments (i.e., specific activity, exposure time and location) shall be included in 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 deter-mining the gaseous pathway doses. The assessment of radiation doses shall be performed in accordance with the OFFSITE DOSE CALCULATION MANUAL (00CM).
I The radioactive effluent release report to be submitted 60 days after January 1 of each year shall 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 12 consecutive months to show conformance with 40 CFR 190, Environmental Radiation Protection Standards for Nuclear Power Operatin. Acceptable methods for calculating the dose contribution from liquid and gaseous effluents are given in Regulatory Guide 1.109, Rev. 1.
The radioactive effluents release shall include the following information for each type of solid waste shipped offsite during the report period:
a.
Container volume, b.
Total curie quantity (specifiy whether determined by measurement or estimate),
c.
Principal radionuclides (specify whether determined by measurement or estimate),
b ALL STS-I 6-3
{
l~
l L
I
ADMINISTRATIVE CONTROLS d.
Type of waste (e.g., spent resin, compacted dry waste, evaporator bottoms),
e.
Type of container (e.g., LSA, Type A, Type B, Large Quantity), and f.
Solidification agent (e.g., cement, urea formaldehyde).
The radioactive effluent release reports shall include unplanned releases from the site tn unrestricted areas of radioactive materials in gaseous and liquid effluents on a quarterly basis.
The radioactive effluent release reports shall include any changes to the PROCESS CONTROL PROGRAM (PCP) made during the reporting period.
MONTHLY REACTOR OPERATING REPORT 6.9.1.10 Routine reports of operating statistics and shutdown experience shall be submitted on a monthly basis to the Director, Office of Management and Program Analysis, U.S. Nuclear Regulatory Commission, Washington, D.C.
20555, with a copy to the Regional Office of Inspection and Enforcement, no later than the 15th of each month following the calendar month covered by the report.
Any changes to the OFFSITE DOSE CALCULATION MANUAL shall be submitted with the Monthly Operating Report within 90 days in which the change (s) was made effective.
In addition, a report of any major changes to the radioactive wa:te treatment systems shall be submitted with the Monthly Operating Report for the period in which the evaluation was reviewed and accepted by the (Unit Review Group).
PROMPT NOTIFICATION WITH WRITTEN FOLLOWUP 6.9.1.12 j.
Offsite releases of radioactive materials in liquid and gaseous
~
effluents which exceed the limits of Specification 3.11.1.1 or 3.11.2.1.
k.
Exceeding the limits in Specification 3.11.1.4 or 3.11.2.6 for the storage of radioactive materials in the listed tanks. The written follow-up report shall include a schedule and a description of activities planned and/or taken to reduce the contents to within the specified limits.
l ALL STS-I 6-4 l
ADMINISTRATIVE CONTROLS THIRTY DAY WRITTEN REPORTS 6.9.1.13 e.
An unplanned offsite release of 1) more than 1 curie of radioactive material in liquid effluents, 2) more than 150 curies of noble gas in gaseous effluents, or 3) more than 0.05 curies of radiciodine in gaseous effluents. The report of an unplanned offsite release of radioactive material shall include the following information:
1.
A description of the event and equipment involved.
2.
Cause(s) for the unplanned release.
3.
Actions taken to prevent recurrence.
4.
Consequences of the unplanned release.
f.
Mtasured levels of radioactivity in an environmental sampling medium determined to exceed the reporting level values of Table 3.12-2 when averaged over any calendar quarter sampling period.
6.10 RECORD RETENTION 6.10.2 1.
Records of analyses required by the radiological environmental monitoring program.
i i
ALL STS-I 6-5
i i
ADMINISTRATIVE 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 semi-annual Radioactive Effluent Release Report for the period in which the change (s) was made.
This submittal shall contain:
a.
Sufficiently detailed information to totally support the rationale for the change without benefit of additional or supplemental information; 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 (00CM) 6.14.1 The ODCM shall be approved by the Commission prior to implementation.
6.14.2 Licensee initiated changes to the 00CM:
1.
Shall be submitted to the Commission in the Monthly Operating Report within 90 days of the date the change (s) was made effective. This submittal shall contain:
a.
Sufficiently detailed information to totally support the rationale for the change without benefit of additional or supplemental information.
Information submitted should consist of a package of those pages of the ODCM 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 has been reviewed and found acceptable by the (URG).
2.
Shall become effective upon review and acceptance by the (URG).
F ALL STS-I 6-6
1, ADMINISTRATIVE CONTROLS 6.15 MAJOR CHANGES TO RADIOACTIVE WASTE TREATMENT SYSTEMS (Liquid, Gaseous and solid) 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 Monthly Operating Report for the period in which the evaluation was reviewed by the (Unit Review Group). The discussion of each change shall contain:
a.
A summary of the evaluation that led to the determination that the change could be made in accordance with 10 CFR 50.59; b.
Sufficient detailed information to totally support the reason for the change without benefit of additional or supplemental information; c.
A detailed description of the equipment, components and processes 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; e.
An evaluation of the change which shows the expected maximum 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 camparison of the predicted releases of radioactive materials, in liquid and gaseous effluents and in solid waste, to the ar tual 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 fact that the change was reviewed and found acceptable by the (URG).
2.
Shall become effective upon review and acceptance by the (URG).
ALL STS-I 6-7 1