ML19249C163
| ML19249C163 | |
| Person / Time | |
|---|---|
| Site: | LaSalle  |
| Issue date: | 07/31/1979 |
| From: | NRC COMMISSION (OCM) |
| To: | |
| Shared Package | |
| ML19249C159 | List: |
| References | |
| NUREG-0473, NUREG-0473-R02, NUREG-473, NUREG-473-R2, NUDOCS 7909070518 | |
| Download: ML19249C163 (84) | |
Text
.
NUREG-0473 Revision 2 RADIOLOGICAL EFFLUENT TECHNICAL SPECIFICATIONS FOR BWR'S July 1979
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INDEX DEFINITIONS SECTION PAGE
_1. ; DEFINITIONS Channel Calibration..
1-2 Channel Check.
1-2 Channel Functional Test..
1-2 Ease Equivalent I-131.
1-2 Lource Check.
1-2 Process Control Program (PCP)..
1-2 Solidification.
1-3 Cffsite Dose Calculation Manual (CDCM)..............
1-3 Gaseous Radwaste Treatm2nt System..
1-3 Ventilation Exhaust Treatment System................
1-3 Purge-Purging.
1-3 Venting.
1-3 c.0 T E.
Aad 3/4.3.3.7.11 and 3/4.3.3.7.12 with appropriate page rumbers to Inaex section for Monitoring Instrumentation and its Bases; also add 5.1.3 and 5.1.4 tc Section 5.0 Index and appropriate additions to Section 6.0 Index.
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INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION PAGE 2/4.11 RADI0 ACTIVE 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 2/4 11.2 GASEOUS EFFLUENTS Dose Rate..
3/4 11-8 Dose-Noble Gases..
3/4 11-12 Cose-Radiciodines, Particulate, and Radionuclide Other than Noble Gases.
3/4 11-13 Gaseous Waste Treatment..
3/4 11-14 Ven:ilation Exhaust Treatment.
3/4 11-15 Explosive Gas Mixture.
3/4 11-16 Main Condenser.
3/4 11-18 Mark I or II Containment.
3/4 11-19 3/4 11.3 SOLID RADICACTIVE WASTE....
3/4 11-20 3/4 11.4 TOTAL DOSE.
3/4 11-22 3/4.12 RADIOLOGICAL ENVIRONMENTAL MONITORING 3/4.12.1 MONITORING PROGRAM.
3/4 12-1 3/4.12.2 LAND USE CENSUS.
3/4 12-10 3.
2._
- NTER_AECRATORY C:MPARISON.
2/4 12-l' D
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INDEX EASES SECTION PAGE
/4.11 RADICACT:VE EFFLUENTS B 3/4 11-1 3/4.11.1 LIQUID EFFLUENTS.
B 3/4 il-2
- /4.11.2 GASEOUS EFFLUENTS.
3/4.11.3 SOLID RADI0 ACTIVE WASTE.
B 3/4 11-5 3/4.11.4 TOTAL DOSE.
B 3/4 11-5
- /4.12 RADIOACTIVE ENVIRONMENTAL MONITORING 3/4.12.1 MONITORING PROGRAM, B 3/4 12-1 B 3/4 12-1 3/4.12.2 LAND USE CENSUS.
B 3/4 12-1 3/4.12.3 INTERLABORATRY COMPARISON PROGRAM.
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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
- rip functions, and shall include the CHANNEL FUNCTIONAL TEST.
The CHANNEL CALIERATION may be performed by any series of sequential, overlapping or total cnannel steps such that the entire channel is calibrated.
CHANNEL CHECK
.10 A CHANNEL CHECK shall be the qualitative assessmert of channel behavior curing cperation by observation.
This detenaination shall include, where possible, ccmparison of the channel irdication and/or status with other indica-tions and/or status derived from independent instrumentation channels measuring the same parameter.
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.
Sistable channels - the injection of a simulated signal into the sensor to verify OPERABILITY including alarm and/or trip functions.
- 0SE ECUIVALENT I-131 1.19 The DOSE EQUIVALENT I-131 shall be that concentration of I-131 (microcurie /
jram) which alone would produce the same thyroid dose as the quantity and isotopic mixture of I-131, I-132, 1-133, I-134 and I-135 actually present.
The thyroid dose conversion factors used for this calculation shall be those listed in Table III of TID-14844, " 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
. hen the cnannel sensor is exposed to a radioactive source.
DRC E55 CCNTROL DROGRAM (PCP) i.:0 e CRCCESS CONTROL PROGRAM shall contain the sampling, analysis, anc "cr uia:"cr determinaticn cy wnicn SOLIDIFICATION of radioactive wastes f rc.?
.ica'a 3;.-sta s is assured.
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.0 CEFINITIONS (Continuec) 50LIDIFICATION
.31 SOLIDIFICATION shall be the conversion of radioactive wastes from liquid systems to a homogeneous (uniformly distributed), monolithic, immobilited solid with definite volume and shape, bounded by a stable surface of distinct cutline on all sides (free-standing).
?FFSITE DCSE CALCULATION MANUAL (CDCM)
.32 The OFFSITE DOSE CALCULATION MANUAL shall contain the retnodolc;y and
'arameters used in the calculation of offsite deses due to radioactise gaseous
_nd liquid ef fluents and in the calculation of of gaseous and liquid ef fluent monitoring alarm / trip setpoints.
3ASECUS RACWASTE TREATMENT SYSTEM
.33 A GASEOUS RADWASTE TREATMENT SYSTEM is any system designed and installed
.o reduce radioactive gaseous ef fluents by collecting primary coolant system
- f fgases frem the primary system and providing for delay or holdup for the Jurpose of reducing the total radioactivity prior to release to the environment.
.ENTILATION EXHAUST TREATMENT SYSTEM
.3A A VENTILATION EXHAUST TREATMENT SYSTEM is any system designec and installed to reduce gaseous radiciodine or radioactive material in particulate form in af fluents by passing ventilation or vent exhaust gases through cnarccal adsorbers and/or HEPA filters for the purpose of removing iodines or particulates from
- he gaseous exhaust stream prior to the release to the environment (such a
- ystem is not considered to have any effect on noble gas effluents).
Engineered 5afety Feature (ESF) atmospheric cleanup systems are not censiderec to be JENTILATION EXHAUST TREATMENT SYSTFM components.
- URGE - 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.
/ENTING
.36
.ENTING is tne controlled process of discharging air or gas fr m a
- c-t ement to maintain temperature, pressure, humidity, cor:entrati:n or e- ;cerat'ng condition, in sucn a manner that replacement air or gas is not rov'ced cr ecuired cu-ing VENTING.
Vent, used in system -ares, c:es not
':', 3 /ENTINS process.
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TABLE i.2 FREOUENCY NOTATION NOTATION FRE0UENCY At least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
D At least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
W At least once per 7 days.
M At least once per 31 days.
Q At least once per 92 days.
~
SA At least once per 18' days.
R At least once per 18 months.
S/U Prior to each reactor startup.
P Completed prior to each release.
N.A.
Not applicable.
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.sTRUMENTATION
- JICACTIVE LIQL"O EFFLUENT MONITORING INSTRUMENTATION
.:MITING CONDITICN FOR OPERATICN
'. 3. 7.11 The radioactive liquid e?i, ent monitoring instrumentaticn channels acon in Taoie 3.3.7.11-1 shall be OPERABLE with their alarm / trip setpoints set
- ensure that the limits of Specification 3.11.1.1 are not exceeded.
The alarm /
ip setpoints of these channels shall be determined in accordance with the Uffsite Dose Calculation Manual (ODCM).
3PLICABILITY:
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 one or more radioactive liquid effluent monitoring instrumenta-tion cnannels inoperable, take the ACTION shown in Table 3.3.7.11-1.
c.
The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.
EURVEILLANCE RECUIREMENTS
.3.7.11 Each radioactive liquid effluent monitoring instrumentation channel sr.all be demonstrated OPERABLE by performance of the CHANNEL CHECK, SOURCE
^ HECK, CHANNEL CALIBRATION and CHANNEL FUNCTIONAL TEST operations at the requencies shewn in Table 4.3.7.11-1.
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INDEX EASES PAGE SECTION c'4.1 1 RADICACT:VE EFFLUENTS E 3/4 11-1 1/ 4.11.1 LIOUID EFFLUENTS.
S 3/4 11-2 1/4.11.2 GASEOUS EFFLUENTS.
3/4.11.3 SOLID RADICACTIVE WASTE.
E 3/4 11-5 S 3/4 11-5 3/4.11.4 TOTAL DOSE.
1/4.12 RADICACTIVE ENVIRONMENTAL MCNITORING E 3/4 :2-1 2/4.12.1 MONITCRING PROGRAM.
E 3/4 12-1 3/ 4.12.2 LAND USE CENSUS.
B 3/4 12-1 3/4.12.3 INTERLAECRATRY CCMPARISCN PROGRAM.
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1.C CEFINITICNS CHANNEL CALIBRATION 19 A CHANNEL CALIBRATION shall be the adjustment, as necessary, of the c5annel output such that it responds with the necessary range and accuracy to known values of the parameter which the channel monitors.
The CHANNEL CALI3RA-
'ICN shall encompass the entire channel including the senscr and alarm and/cr The CHANNEL
. rip functicns, and shall include the CHANNEL FUNCTIONAL TEST.
CALIERATICJ may :e performed by any series of cequential, overlapping or total c9annel steps such that the entire channel is calibrated.
CHANNEL CHECK
.10 A CHANNEL CHECK shall be the cualitative assessment of channel behavier curing operation by cbservation.
This determination shall incluce, where cssible, comparison of the channel indication and/or status with other indica-tions and/or status cerivec f rom incependent instrumentation channels measuring the same parameter.
- MANNEL FUNCTIONAL TEST 11 A CHANNEL FUNCTIONAL TEST shall be:
Analcg channels - the injection of a simulated signal into tne a.
channel as close to t.'.e sensor as practicable to verify CPERASILITY inclucing alarm and/or trip functions.
b.
Bistable channels - the injection of a simulated signal into the sensor-to verify CPERASILITY including alarm anc/cr trip functions.
_CSE ECJIVALENT I-131 1.19 The DCSE EQUIVALENT I-131 shall be that concentration of I-131 (microcurie /
jram) which alone would produce the same thyroid cose as the quantity and isotopic mixture of I-131, I-132, I-133, I-13A and I-135 actually present.
The thyroid dose conversion factors used for this calculation shall be those listed in Table III of TID-148A4, " Calculation of Distance Factors for Power and Test Reactor Sites."
SCURCE CHECK 1.09 A SC'JRCE CHECK shall be the qu?litative assessment of channel response t"e cnannel senser is ex csec tc a radicactive source.
er
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-ic9 5:_IC:F:Cai:CN c' acic active wastes '-cr 5:1~5 5 as5J"ec.
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'.0 DEFINITIONS (Continued)
SOLIDIFICATION
'.31 SOLIDIFICATION shall be the conversion of racicactive wastes from liquid systems to a homogeneous (uniformly distributed), monolithic, immobilized solid with definite volume and shape, beunded by a stable surface of distinct cutline on all sides (free-standing).
3FFSITE DOSE CALCULATION MANUAL (ODCPd
.32 The OFFSITE DOSE CAL.dLATION MANUAL shall contain the methodology and arameters used in the calculation of offsite cases due to radicactive gasecus
.nd liquid effluerts and in the calculation of of gasecus and liquid efficent monitoring alarm / trip ietpoints.
GASEOUS RADWASTc TREATMENT ;YSTEM
'.33 A GASEGUS RA0 WASTE TREATMENT SYSTEM is any system desi,ned and installed to reduce racioactive gaseous ef fluents by collecting primary coolant system cf fgases frcm :he crimary system and providing for delay or holdup for the Ourpose of reducing the total radioactivity prior to release to the environment.
.'ENTILATION EXHAUST TREATMENT SYSTEM
.34 A VENTILATION EXHAUST TREATMENT SYSTEM is any sys m designed and installed to reduce gaseous radiciocine or radicactive material in particulate form in af fluents by passing ventilation or vent exhaust gases through charccal adsorbers and/or HEPA filters for the purpose cf removing iodines or particulates from tre gasecus exhaust stream prior to the release to the environment (such a 3ystem is nct ccasidered te nave any effect on noble gas effluents).
Engineered 5afety Feature (ESF) atmospheric cleanup systems are not ccnsicered to Oe JENTILATION EXHAUST TREATMENT SYSTEM components.
' URGE - PURGING 1.35 PURGE or FURGING is the controllec 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.
/ENTING
.35
.-ENTI:.3 is the centrolled process of discnarging air er gas from a
'i e ent to aintain temcerature, cressure, numidity, concentration or
- er :: era:" g ccnciticn, in sucn a marner that replacement air or gas is nct
- -cvice: er -ec_irec curing.'ENTING.
vent, usec in syster names, coes mc "ri.
s.EN':N2 :rocess.
pgg ORGE 1-3
TABLE 1.2 FREQUENCY NOTATION FREOUENCY NCTATION S
At least ence per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
D At least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
At least cnce per 7 days.
W At least once per 31 days.
S' Q
At least once per 92 days.
SA At least once per 184 cays.
E At least once per 15 months.
5/U Prior to each reactor startup.
E Completed prior to each release.
N A.
Not applicable.
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'ABIL 3.3.7-l_l-]
o RA010ACilVL LIQUID LI F LUErli M0til 10 RING lilS TRUrtEt1IAT IOtt
,l MINIMUM CilANt4ELS INSTRUMEtiT OPERABLE ACTION I.
GROSS RAD 10AClIVITY MONi10RS PROVIDifiG AUTOMATIC ILRMitlATI0tt 0F RELEASE Liquid Radwaste Effluent Line (1) 110 a.
7.
GRO M RA010ACllVITY MON 110RS tl0T PROVIDING AUTOMAllC flRMitlAIlott 0F RELEASE Service Water System Effluent Line (1) 112 a.
h.
Component Cooling Water System Effluent Line (1) 112
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3.
FLOW RATE MEASUREMENT DEVICES Liquid Radwaste Efflueat Line (1) 113 a.
b.
Discharge Canal (1) 113 4.
RAD 10ACIIVITY RECORDERS (*)
Liquid Radwaste Effluent Line (1) 115 a.
(* Required only if alarm / trip set point is based on recorder / controller) ixJ IN '!
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T Alll E 3.3.7.11-1 (ConLinued)
RADIDACilVE LIQUID FFf LUElli' M0til10Rif4G lilS T RUME ti T AT I0tt J
MIti! Mull CilAritil:LS OPERABI[
ACT10ft INSTRUMEllT 5.
IAtlK ll.VL L li1DICATING DEVICES (for tanks outsiale plant. buildings)
(1) 114 a.
(1) 114 b.
(1) 114 c
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TABLE 3.3.7.11-1 (Continued)
TABLE NOTATION ACTION 110 -
With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases may continue for up to 14 days provided that prior to initiating a release:
At least two independent samples are analyzed in acccrdance a.
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 cischarge line valving; Otherwise, suspend release of radioactive effluents via this pathway.
ACTION 111 -
Not A;plicable.
4: TION 112 -
With the numoer of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluert releases via this pathway may continue for up to 30 days provided that, at least once per S hours, grab samples are collected and analyzed for gross radioactivity (beta or gamma) at a limit of detection of at least 10-7 micorcuries/ml.
ACTION 113 -
With the numoer of channels OPERAELE iess than required by the Minimum Channels OPERABLE requirement, effluent releases via tnis oathway may continue for up to 30 days providec tne 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 /> curing actual releases.
Fump curves may be used to estimate flow.
ACTION 114 -
With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, liquid additions to this tank may continue for up to 30 days provided the tank liquid level is estimatea during all liquid additions to the tank.
ACTION 115 -
With the numoer 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.
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I Allt I 4. 3./.Il-I RAD 10At:llVL LIQUID Li'f tllLNI MONIIORING lilSIRilMl tll AT 10tl SllRVElll ANCF HlylllRil11:NIS CllANNEl.
CilANNEL SOURCE CilANNEI.
FUNCl10NAL i rr,I Ruhl til CilECK CilLCK CALillRA~l 10N TEST I
GRO% lil l A OR GAMilA RAD 10ACTIVliY M0filIORS l'ROVIDING ALARM AND AUTOMATIC TERMIflATION Of Rill ASI Iiviuid R.ufwaste Effluents Line D
P R(3)
Q(1) a.
?
GROM lil I A OR GAMi1MA RADI0 ACTIVITY MONITORS l'ROVIDING ALARM BUT NOT PROVIDING AUTOMATIC IlRMitlAl10N Of RELEASE
(
Service Water System Effluent Line D
M R(3)
Q(2)
[,',
a.
5 l>.
Component Cooling Water System Effluent iine D
M R(3)
Q(2) 3.
ILOW RAIL MEASilREMENT DEVICES (4)
Liquid Radwaste Effluent Line D(4)
N.A.
R Q
a.
13.
Discharge Canal D(4)
N.A.
R Q
b
)
'R j= s
'O
.M EFE) 0 0
.o su N
y EED L
TABit 4.3.7.11-1 (Continued) 4 RADIOAClIVE LIQUID EffillENT MONITORIflG INSTRUMLitTATION SURVEILLAtlCE RLQl11RLMENTS CilANNE L CilANNEl SOURCE CilANNE L FUNCTIONAL I N 51 HliMi til CllECK CllLCK CAllDRA110N TES1 4.
RAD 10ACilV11Y RECORDERS (5) l iquid Radwaste Ef fluent Line D
N.A.
R Q
.i LANK liVEL INDICATING DEVICES (for tankt, outside the ljuiIding) (6)
.i.
D*
N.A.
R Q
D*
N.A.
R Q
13 c.
D*
N.A.
R Q
'l d.
D*
N.A.
R Q
k-)
Mai 5d ISP] C"~l
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N b c:3) c s_
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TABLE 4.3.7.11-1 (Continued)
TABLE NOTATION During liquid additions to tne 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 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 / trip setpoint.
2.
Circuit failure.
3.
Instrument indicates a cownscale failure.
4.
Instrument controls not set ir. 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 stancards that have been obtained from suppliers that participate in measurement assurance activities with NSS.
These standards shall permit calibrating the system over its intended range of energy and measuremer,t 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.)
a) CHANNEL CHECK shall consist of verifying indication of flow during periods s
of release.
CHANNEL CHECK shall be made at least once daily on any day en which continuous, periodic, or batch releases are made.
(5) This requirement is applicable only to systems where an alarm / trip action is performed by recorder-controller instrumentation.
'6)
This requirement is not applicaDie to tanks which have dikes or re-tention ponds capable of preventing runoff in the event of a tank cse?'l:w and have pro.isions for sampling collected liquics and rnM'ng them to a licuid racwaste treatment syste-QQ p'
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I'.5TRUMENTATION RADICACTIVE GASECUS EFFLUENT MONITORING INSTRUMENTATION LIMITING CONDITION FOR OPERATICN 3.3.7.12 The radioactive gaseous effluent monitoring instrumentation channels anc*n in Table 3.3.7.12-1 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.
nPPLICABILITY:
As shown in Table 3.3.7.12-1 ACTION:
With a radioactive gaseous effluent monitorirp instrumentation a.
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 one or more ra90 active gaseous effluent monitoring instrumenta-tion channels inor able, take the ACTICN shown in Table 3.3.7.12-1.
c.
The provisions e Specifications 3.0.3 and 3.0.4 are not applicable.
SURVEILLANCE REOUIREMENTS 4.3.7.12 Each radioactive gaseous effluent monitoring instrumentation channel shall be demonstrated OPERABLE by porfo.mance of the CHANNEL CHECK, SOURCE CHECK, CHANNEL CALIBRATION and CHANNEL FUNCTIONAL TEST operations at the frequencies shown in Table 4.3.7.12-1.
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_l.A._ll t. _i _ 3. 3 7. 17 - I RADIDACT IVE GASL0llS LIi LtlEllT M0 fill 0RiflG Ifl51RilMLNI AT IOft MINIMUM CilANNELS Ifh iRuf1[ fli OPERABLE APPLICABILITY ACTION
(-
]
1.
f!AIN CONDLilStR OFFGAS TREATMENT SYSTEM liflutNI fl0 Nil 0 RING SYSTEM a
^
123 i
a.
floble Gas Activity Monitor (1) bb b.
lodine Sampler (1) 127 fM (' _)
^
127 c
larticulate Sampler (1) 122 d.
Iffluent System Flow Rate Measuring Device (1) 6 122 e.
Sampler Flow Rcte Measuring Device (1) s.
2A.
MAIN CONDENSER OFFGAS TREATMENT SYSTEM EXPLOSlVE
- g GAS MONITORING SYSTEM (for systems designed to withstand the effects of a hydrogen explosion)
^^
125 a.
Ilydrogen Monitor (1) 125 h.
Ilydrogen or Oxygen Monitor (1) 2 11.
MAlfi CONDLNSER OFFGAS TREATMENT SYSTEM IXPl0SIVI~ GAS MONITORING SYSTEM (for systems not designed to withstand the effects of a hydrogen explosion)
^^
126 c
a.
Hydrogen Monitor (2) 126 b.
liydrogen or Oxygen Monitor (2) m L.r-L
I Alli L 3.3.7.12-1 l
RADI0 ACTIVE GASEOUS EFFLUENT' MONIIORING INSIRUMENIAT10N MINIMUM CilAtit1ELS Iris IRilMf N T OPERABLE APPLICABILITY ACTION 3.
RI ACIOR Bil)G. VENTILATION / PURGE MONITORING SYSILM 124 Nol>le Gas Activity Monitor (1) 127 t,
lodine Sampler (1)
Particulate Sampler (1)
(y 127 c
ti.
fffluent System Flow Rate Monitor (1) 122 c.
Sampler flow Rate Monitor (1)
]
122 7;
'G
]
4.
MAIN STACK MONITORING SYSTEM VMt a.
tioble Gas Activity Monitor (1) h 123 b.
Iodine Sampler (1) 127 Particulate Sampler (1) 127 t
d.
[ffluent System Flow Rate Monitor (1) 122
^
122 Sampler flow Rate Monitor (1) e 5.
IURBINE Bll)G. VENTILATION MONITORING SYSTEM c:
floble Gas Activity Monitor (1) 123
~,
a.
127 b.
Iodine San.pler (1) y..
i/'
Particulate Sampler (1) 127 r
C'
I Al!! I 3.3./.12-1 (Continued)
If RADI0 ACTIVE GASE0llS fl F illENT MONI TORING INSTRllMENIATION MINIMllM CilANill LS lil'> l Riltil ti l OPERABLE APPLICABILITY ACTION S
luRit i tlI !!! I)G. VENTILAI10N M0f1Il0 RING SYSilM (Continued) 122 CQ Etfluent System Flow Rate Monitor (1) e 122 t.
Sampler flow Rate Monitor (1) 59 6.
AllXIl I ARY lillll DING VENTILATION MOH110 RING SYSTEM Notile Gas Activity Monitor (1) 123 L
a.
^
127 li.
lodine Sampler (1) 127 c.
Particulate Sampler (1) 122 d.
flow Rate Monitor (1)
Sampler flow Rate Monitor (1) 122 e.
/.
f ill t STORAGI AREA VENTILATION MONITORiflG SYSTEM Notile Gas Activity Monitor (1) 123 a.
t).
lodine Sampler (1) 127
('
Particulate Sampler (1) 127 c.
d.
Ilow Rate Monitor (1) 122
^
122 sampler flow Rate Monitor (1)
/
IABli J.3./.12-1 (Continued)
RADI0 ACTIVE GASEOUS EFf_tuttif fl0NITORiflG It1SIRtitif.fifAfl0N
..l MINIMUt1 CllANflELS 1flS I RUML fil OPERABLE APPLICABillIY ACTI0tt (k
8.
RADWASIf AREA VENIILAT10N MONITORiflG
' Y S i lli 123 tiable Gas Activity Monitor (1) g]
a.
^
127 b.
Iodine Sampler (1)
S WN._ _~bT Particulate Sampler (1) c 127 122 d.
Ilow Rate lionitor (1)
{,
122 Sampler I low Rate lionitor (1) c.
k's.
9.
I URH i tti GlAt40 SEAL CONDENSER VENT AND o,
/u MECilAl41 CAL VACUUM PUMP EXHAUST M0f4ITORIf4G SYSIEM 123 tioble Gas Activity Monitor (1) a.
127 b.
Iodine Sampler (1)
^
127 Part iculate Sampler (1) r 122 d.
I low Rat e Monitor (1) 122 Sampler flow Rate Monitor (1) e 10.
f.ONDLrl5LR AIR [JECTOR RADI0 ACTIVITY MONITOR r
(Prior to input to lloldup System)
~,/
121 floble Gas Activity flor.itor (1) a.
cm
TABLE 3.3.7.12-1 (Continued)
TABLE NOTATION At all times.
During main condenser offgas treatment system operation.
'** Curing operation of the main concenser air ejector.
ACTICN 121 -
With the r. umber of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, the contents of the tank (s) may be released to the environment for up to 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> provided:
a.
The offgas system is not bypassed, and b.
The offgas delay systam nobla gas ctivity effluent (down-stream) monitor is 0PERABLE; Otherwise, be in at least HOT STANDBY sithin 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
ACTION 122 -
With the number oi channels OPEF.ABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue for up to 30 days providec the flow rate is estimated at least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.
ACTION 123 -
With the number of channels CPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via tnis 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 124 -
With the number of channels CPERABLE less than required bv the Minimum Channels OPERABLE requirement, suspend release or radioactive effluents via this pathway.
ACTION 125 -
With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, operation of main condenser offgas treatment system may continue 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 126 -
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 incperacle, be in at least HOT STANCB: within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
iCTICN 127 -
with the numcer of cnannels CPERAELE less than requirec by tne Minimum Channels C?ERABLE requirement, effluent releases via tris patnway may continue for up to 30 davs proviced samples
-re continucusly caliectec wit.* auxilia y sampling equierent as ecuirea in Ta:Te 4.11-2.
D D
R-z~*
3/a 3-5:
O '9
'}
, @-l11
_a vi
IAutE 4.3.7.12-1
/
RAD.1_0ACi_lVL GASEGUS EFFLUENT MONIf0 RING IllSTRUMENIAIION SURVEILLANCE REQUIREMENIS e
CilANNEL MODES IN WillCil CllANNEL SOURCE CilANilLL FUtiCTIONAL SURVEILLANCE Illh i RUMi N 1 CilECK CHECK CAllBRATION TEST REQUIRED
[g 1.
?!AIN CONDIfl5LR OFfGAS TREATMENT SYSTEM EF FLUENT MONITORING y
SYSILM C@
a.
tioble Gas Activity Monitor D
P R(3)
Q(1) ti.
Iodine Sampler W
N.A.
N.A.
N.A.
BD c.
Particulate Sampler W
N.A.
N.A.
N.A.
d.
flow Rate tionitor D
N.A.
R Q
- e. Sampler flow Rate Monitor D
N.A.
R Q
a (U
2.
MAIN CONDENSER OFFGAS TREATMENT SYSTEM EXPLOSIVE GAS MONITORING SYSILM
- a. ilydrogen Monitor D
N/A Q(4)
M
- b. Hydrogen Monitor (alternate) 0 N/A Q(4)
M
- c. Oxygen Monitor D
N/A Q(5)
M
- d. Oxygen Monitor (alternale)
D N.A.
Q(5) f1 f'
.P-C'
IAbil 4.3.7.12-1 (Continueil)
I" RAD 10ACilVE GASE0US EFFL.UfflI MONIIORING INSTRUMENIAlf0f4 SURVEILLANCE RfQUIREMff415
<n
(/)
CllAllNE L MODES IN WilICH CilANNi l SbtJRCf CilANNEL FUNCTIONAL SURVElllANCE
_I flS I..Rllfil N I Clll CK CilECK CALIBRATION TEST REQUIRED 3.
REACIOR BLDG. VENTILATION / PURGE MONIl0RiflG SYSTEM Noble Gas Activity Monitor D
M R(3)
Q(1)
CQ a.
b.
lodine Sampler W
N. A.
N.A.
N.A.
EP Part iculate Sampler W
N.A.
N.A.
N.A.
t it. Effluent System Flow Rate Monitor D
N.A.
R Q
x Sampler flow Rate Monitor D
N.A.
R Q
e.
(7) 4.
MAIN STACK MONITORING SYSTEM
- a. Noble Gas Activity Monitor D
M R(3)
Q(2) b.
Iodine Sampler W
N.A.
N.A.
N. A.
c Particulate Sampler W
N.A.
N.A.
N.A.
it. I f f luent System Flow Rate Monitor D
N.A.
R Q
Sampler Ilow Rate Monitor D
N.A.
R Q
e c
\\
N, a
T Alil l 4.3.7.12-1 (Continued)
/;
RADi(JACilVE GASE01)S Ef fluEt41 Morl!!0 RING INSTRUMENT ATION Si1RVEILLAllCE REQlllRIMENTS CilANNLI MODES IN WillCH CllAl4NI I SOURCE CilAriHL L FUNCTIONAL SURVEIll.AllCE I fh i Rilill N I CllECK CilECK CAllBRAIlON TLSI REQlllRED IURitifit til 0G. VfNIlLA110N f10NilORING SYSIEM
'E m
Noble Gas Activity Monitor D
M R(3)
Q(2)
Q a.
b.
lodine Sampler W
N.A.
N.A.
N.A.
d a
c.
Particulate Sampler W
N.A.
N.A.
N.A.
- d. Flow Rate Monitor D
N.A.
R Q
^
Sampler flow Rate Monitor D
N.A.
R Q
e.
(3.
AUXIIIARY BUILDING VENTILATION MONITORING SYSTEM
- a. floble Gas Actvity Monitor D
M R(3)
Q(2) b.
lodine Sampler W
N.A.
N.A.
N.A.
Particulate Sampler W
N.A.
N.A.
N.A.
c
- d. Ilow Rate Monitor D
N.A.
R Q
Sampler flow Hate Monitor D
N.A.
R Q
e 4
.P g- :
I Alti l 1.3.7.12-1 (Contisnied)
RAD 10Al llVI. GASEOUS El f lutNI MONI_IORiflG If4SlHUMLHI Al10t1 SllHVLIll AtiCL Rf Qtilfif tll fif S i
y u,
CilANilL L MODES IN WillCil CilANNEl SOURCE CilANNEL FUNCT 10tlAL SURVEILLANCE h
Ith I RUM 1 til Clit CK CllECK CALIBRAlIGN lESI REQlllRED C
/
Ilitt. SiORAGL AREA VENTILATION h.
MONIIORIrlG SYSTEM Notile Gas Activity Monitor D
M R(3)
Q(2) a.
ti. lodine Sampler W
fl. A.
N.A.
N.A.
c.
Particulate Sampler W
ti. A.
N. A.
N.A.
f
- d. Flow Rate Monitor D
N.A.
R Q
t' Sampler Flow Rate Monitor D
N.A.
R Q
e.
8.
RADWASlE AREA VENTILATION MONITORING SYSTEM a.
Notile Gas Activity Monitor D
M R(3)
Q(2) li.
Iodine Sampler W
N.A.
fl. A.
N.A
- c. Particulate Sampler W
fl. A.
N.A.
H.A
- d. I' low Rate Monitor D
N.A.
R Q
Sampler flow Rate Monitor D
N.A.
R Q
e.
c w
w
.h'
T ABll 4. 3. /.12-1 (Cont intn d)
RAI)li)ACIIVL GASEOUS Ef f tlllill M0til10RIrlG INST RUMLilT AII0ft SllRVLILLANCE REQUIR[MErl15 e;,
CllANilEL MODE S Ill WilICil CllANilE L SOURCE CllAtlNI I FUNCTIONAL SURVEILLANCE
- - -I N S I kl.lM_ I ti l CllECK CllECK CALIBRAIION TEST REQUIRED 9.
IUkilliti GIAt10 SEAL C0tlDENSER VENT AND MI CllANIC Al VACUUM PllMP EXNAUSI MONIIORING Shlt M tiotele Gas Activity Monitor D
M R(3)
Q(2) a.
b.
l oili ne Sampler W
ti. A.
fl. A.
N.A c.
Particulate Sampler W
N.A.
fl. A.
N.A.
- 41. Ilow Rate Monitor D
N.A.
R Q
<p Sampler flow Hate Monitor D
N.A.
R Q
3-e.
,l 10.
CONDIflSLR AIR EJEC10R RADI0 ACTIVITY M0tilIOR tioble Gas Activity Monitor D
M R(3)
Q(3) a.
k, 'E wa ve3 Mg p
c g
c-
.P
,p
TABLE 4.3.7.12-1 (Continued)
TABLE NOTATION
- At all times.
Ouring main condenser offgas treatment system operation.
D.'ing :peraticn of tne main condenser air ejector.
(i) The CHANNEL FUNCTIONAL TEST shall also ders nstrate that automatic isolatisn of this pathway and control room alarm annunciation occurs if any cf the following conditions exists:
1.
Instrument indicates measured levels above tt 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 rcom a' arm annunciation occurs if any of the following conditions exists:
1.
Instrument indicates ceasured levels above the alarm / trip setpoint.
2.
Circuit failure.
3.
Instrument indicates a downscale failure.
a.
Instrument controls not set in operate mode.
3)
Tne initial CHANNEL CALIBRATION shall be performed using one or more of tne reference standarcs certifiec by the Natioral Bureau nf Standarcs 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 suostitute previously established calibration procedures for this requirement.)
(4)
The CHANNEL CALIBRATION shall include the 'Jse of standard gas samples containing a nominal:
One volure percent hydrogen, balance nitrogen, and 2.
Feur volume percent hydrogen, balance nitrogen.
(5)
~~e CHANNEL CALIBRATICN snali incluce the use of stancara gas samoles
=
-4,7 3
-4,31 e re-cent eqgen, calance n,tregen, and Ie.: u
- c e ci e
- e-ce-t o=jgen, ta'a ce nitrogen.
CN "9 0 O
W C.s T3 F
QIO n @ji dul a m#
u, aq w 3-90
.~
(
.,4.11 RAP!0 ACTIVE EFFLUENTS
- .'4.11.1 LICJID EFFLUENTS CONCENTRATICN
_:MITING CONDITION FOR OPERATION 3.11.1.1 The concentration of radioactive material released from t.Pe site Esee Figure 5.1.4-1) shall be limited to the concentrations specified in 10 CFR Part 20, Appendix B, Table II, Column 2 for radionuclides other than cissolved or entrained noble gases.
For dissgived or entrained noble gases,
- te concentration shall be limited to 2 x 10 microcuries/ml total activity.
APPLICABILITY:
At all times.
-CTION:
'ith the concentration of radioactive material released from the site exceeding
.he above limits, immediately restore the concentration to within the above
- imits.
3URVEILLANCE REOUIREMENTS 4.11.1.1.1 The radioactivity content of each batch of radicactive 1:cuid maste shall be cetermined prior to release by sampling anc analysis in accord-ance with Table 4.11-1.
The results of pre-release analyses shall be used with the calculational methods in the CDCM 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 -f rom 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.
4.11.1.1.3 The radioactivity concentration of liquids discharged from continuous elease points snall be determined by collection and analysis of samoles in accordance ith Table 4.11-1.
The results of the analyses shall be used with
- "e calculational methods in the 00CM to assure that the concentrations at the
- oint cf e
- ease are maintained within the limits of Speci fication 3.11,1.1.
' C' D
0
<> uw e
a tru A
_ i
~ a 3/a 11-1 l
70
,0
- f
TABLE 4.11-1 RADICACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGRA.M I
Minimum Lower Limit Sampling Analysis Type of Activity of Detection Liquic Release TyDe Frequency Frequency Analysis (LLD) _
(pCi4,1) 9 P
P i
l SatchwgsteReleasellEachBatch
_7 Each Eatch Principa)Gamms 5x10 t
n.
Tanks Emitters I-;31 1 x 10 P
lOneBatch/M M
Dissolved and lx10 "
j Entrained Gases (Gamma emitters)
I P
Each Batch M
H-3 lx10 Composite l
Gross Alpha lxlG'#-
P-32 lx10~
0x 13'S Each atch Q
Sr-89, Sr-90 b
Composite I
-6 i
Fe-55 i 10
-7 c
l B. PlantContjnuous Continuous W
Principa) Gamma 5x10 Releases Composite Emitters l
t
~-
I-131 1x10
- M
-5 Grab Sample M
Dissolved and lx10 Entrained Gases (Gamma Emitters)
D IC tinuous M
H-3 1x10~
C Composite"
~-
M h,(
Gross Alpha l
1x10 '
I l
{
l 0) i P-32
- x10 '
l l:cntinuous
{
Q Sr-59, Sr-90 i
5xlG'E C
i uc-cos te' I
l lxic'E l
=e-55
~1
/!"tl E-!
3/4 11-2 c.
e s
a TABLE 4.11-1 (Cortinued)
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 LLD =
E V
2.22 Y
exp (-Aat)
Where:
LLD is the lower limit of detection as defined above (as picocurie per unit mass or volume),
s is the standard deviation of the backgrour.d counting rate or of toe 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 is the number of transformations per minute Oer picacurie, 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 thc calculation of the LLD for a detection b
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.
In calculating the LLD for a radionuclide determined by gamma-ray snectrometry, the background shall inciuce the typical contributions of other racionuclices normally present in the samples.
Typical values of E, V, Y, and at shall be used i n the calculation.
The background count rate is calculated from the background counts that are cetermined to be within + one FWHM (Full-Width-at-Half-Maximum) energy band aDout t!.e ene_rgy of the gamma ray peak usec 'cr the quantitati.e analysis for t9at radionuclice.
OD I
I Tg EQ({ Zl
^
m 3/.; 11-3
,C 0 0-5TC-I
5 TABLE 4.11-1 (Continued)
TABLE NOTATION composite sample is one in which the quantity of liquid sampled is b.
nproportional to the quantity of liquid waste discharged and in which the method of sampling employed results in a specimen which is soresentative of the liquids released.
c.
-c ca reoresentative of tne quantities and concentrations of radicactive material: in licuid effluents, samples chall be collected continu:usly in proportion to the rate of flow of the ef fluent stream.
Prior to analyses, all samples taken for the composite shall be throughly mixec in order for the composite sample to be r ;resentative of the ef fluent release.
A batch release is the discharge of liquid wastes of a discrete c.
volume.
Prior to sampling for analyses, each batch shall be isolated, and tnen thoroughly mixed, by a method described in the ODCM, to assure representative sampling.
A continuous release is the discharge of liquid eastes of a nondiscrete e.
volume; e.g., from a volume of system that has an input ficw during the continuous release.
f.
Tne principal gamma emitters for which the LLD specification applies exclusively are the following radionuclides:
Mn-54, Fe-59, Co-58, Cc-60, Zn-65, Mo-99, Cs-134, Cs-137, Cs-141, and Ce-la4.
This list Oces nct mean that only these nuclides are to be detected and reported.
^trer peaks whicn are measurable anc identifiacle, together with the aDove nuclides, shall also be identified and reported.
Nuclides whiCn are'below the LLD for the analyses shall be reported as "less than" the nuclide's LLD, and shall not be reported as being present at the LLO level for that nuclide.
The "less than" values shall not be used in the required dose calculations.
f 9
0 D
WL 9 R' pj' T 3
j DJ J bi\\
(
-~~'
3/4 11-4
(, ' )
(k
RADICACTIVE EFFLUENTS COSE LIMITING CCNDITION FOR OPERATICN 3.11.1.2 The cose or dose commitment to an individual from radioactive materials in liquid effluents released from tne site (see Figure 5.1.4-1) shall be limitec:
During any calendar quarter to less than or equal to 1.5 nrem to the a.
total body and to less than or equal to 5 mrem to any organ, and b.
Curing any calendar year to less than or eoral to 3 mrem to the total body and to less than or equal to 10 arem to any organ.
APPLICABILITY:
At all times.
ACTION:
a.
With the calculated dose from the release of radioactive materials in liquid effluents exceeding any of the above limits, in lieu of 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 such releases during these four calendar quarters is within 3 mrem to the total body and 10 mrem to any crgan.
(This Special Report shall also include (1) the results of radiological analyses of the drinking water source and (2) the radiological ir. pact on rinished drinking water supplies with regard to the requirements of 40 CFR 141, Safe Drinking Water Act.")
b.
The provisicos of specifications 3.0.3 and 3.0.4 are not applicable.
SURVEILLANCE REQUIREMENTS 4.11.1.2 Dose Calculaticns.
Cumulative cose contributions from liquia effluents shall ce cetermined in accordance with the ODCM ct least once per 31 days.
~;;al::acie Orly if crirsing -ater supply is taken from the receiving aater todv.
D a MMEM
.4 9 g,
/
11.:
ces..:.j
22:::AC":'/E EF LUENTS LIQU:0 WASTE TREATMENT LIMITING CONDITION FOR OPERATION he licuid radwaste treatment system shall be OPERABLE.
The acpro-
.3 3.i'l1:e : rc ons of the system shall ce used to reduce tre radioacti'.e materials 4:uid wastes prier to their discharge when the projected doses due to the
'iquic effluent from the site (see Figure 5.1.4-1) when averaged over 31 days, wou'd exceed 0.05 mrem to the total body or 0.2 mrem to any organ.
APPLICASILITY:
At all times.
ACT:0N:
With the liquid racwaste treatment system inoce acle for more than a.
31 days or with radioactive liquid waste being discharged without treatment and in excess of the above limits, in 'ieu of any othar report required by Specification 6.9.1, prepa-e and submit to the Commission within 30 days cursuant to Soecification 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 CPERABLE status, and 3.
Summary description of action (s) taken to prevent a recurrence.
The provisions of $pecifications 3.0.3 and 3.0.4 are not applicable.
b.
SURVEILLANCE REQUIREMENTS 4.11.1.3.1 Doses due to liquid releases shall be projected at least once per 21 cays, in accordance with the ODCM.
The 'icuid -acwaste treatment system shal' ::e demonstratec OPERABLE
':.2 fcr at least
- erat"rg the l' quid radwaste treatment system ecuincent least crce pe-92 days onless the liquio radwaste system nas teen
'stes at ut":ec to process radioactive liquid effluents durirg the previous 92 cays.
i 1 MB,0$ ^
~-
2 ry ' >
RADIOACTIVE EFFLUENTS LIOUID HOLDUP TANKS" LIMITING CCNDITION FOR OPERATION 3.11.1.4 The quantity of radicactive material contained in each cf the following tanks shall be limited to less than or equal to curies, excluding tritium anc dissolved er entrained noble gases, a.
b.
C.
d.
Outside temporary tank A PP LI CABI LI_T_Y:
At all times.
ACTION:
With the quantity of radioactive material in any of the above listed a.
tanks excecding the above limit, immediately suspend all adoitions 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.
cn r31 D
]
O Cs Cb J Q "9}
}a m
m SURVEILLANCE REOUIREMENTS b
J 4.11.1.4 T.he quantity of radicactive material contained in each of the above listed tanks shall be determined to be within the above limit by analyzing a representative sarple of the tank's contents at least once per 7 days when radicactive materials are being added to the tank.
- Tanis included in this Specification are those cutcccr tanks that are not sur canced 0;. liners, dikes, or walls capable of holcing the tan < contents cc :nat cc not nave tan ( cuerflows and surrouncing area drains ;on-ected c t~e quic rac-aste treatrent system.
/
- )
{.) G E,: :~3-:
3/4 11-7
RADICACTIVE EFFLUENTS 3/4.11.2 GASE0US EFFLUENTS DOSE RATE LIMITING CONDITION FOR OPERATION
_.11.2.1 The cose rate due to radioactive materials released in gascous ef fluerts f rom the site (see Figure 5.1.3-1) shall be limited to tra 'oilcwina:
a.
For noble gases:
Less than or equal to 500 mrem /yr to the total body and less than or equal to 3000 mrem /)
to the skin, and D.
For all radioicdines and for all radioact ' ve materials in particulate 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.
APPLICABILITY:
At all times.
ACTICN:
With the dose rate (s) exceeding the above limits, immediately decrease the release rate tc within the above limit (s).
EUR'iEILLANCE RE U I RE.uENTS 4.11.2.1.1 The dose rate due to noble gases in gaseous effluents shall be ceterminea to be within the above limits in accordance with the methods and procedures of the CDCM.
4.11.2.1.4 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 0 1
D CJ C h
7 L
"A a
~
j' J 3/4 ll-E
1A3t2
- 1. i i B
RADIOACTIVE GAsl0t15 WASTE SAMPIING AND ANALYSIL PROGRAM v.
- l Lower Limit o'
~
~
~
Minimum Sampling Analysis Type of Detecting (lli Gaseou, Relcase lyp ___
Frequency frequency Activity Analysis
_ _(_pCi/ml) 1 P
P l
9 A.
Waste Gas Storage Each Tank Each Tank Pr-incipal Gar:vna Emitters lx10 lank Grab Sample U
lx10' 11.
Containment Purge Eac Purge Each Purge Principal Gamma Emitters Grab
-6 Sample 11-3 lx10 9
C. (List other release H
'C
M Principal Gamma Emitters lx10 points where gas-Grab eous effluents are Sample
-6 li-3 lx10 C
discharged from the di facility)
- l
f W'j I-131 lx10 D. All Release Types Continuous as listed in A, B, Charcoal
-10 j
C above.
Sample I-133 lx10
~II 9
Continuous W
Principal Gamma Emitters lx 10 Particulate (I-131, Others)
(;
-g Sample
-11 f
Continuous M
Gross Alpha lx10 Composite
, ~,
Particulate hh
[
Sample
~II c~-
Continuous Q
Sr-89, Sr-90 lx10 fy (g >
Con:p(y s i te L.
Particulate h
Sample
-6 Continuous Noble Gas Noble Gases lx10 Monitor Gross Deta & Gamna
}
.3
TABLE 4.11-2 (Continued)
TABLE NOTATION a.
The LLD is the smallest concentration of radioactive material in a sample that will be detectea with 95% probability with 5% probability of falsely ccncluding th?t a blank cbservation represents a "real" signal.
Fcr a particular measurement system (which may incluce radiochemical s e;;a rati on):
4.66 s b LLD =
2.22 Y
exo (-Aat)
EV Where:
LLD is the lower limit of cetection as defined above (as picccurie per unit mass or volume),
s is the stancard deviation of the cackground counting rate or of gthe counting rate of a blank sample as a:propriate (as counts per minute),
E is the counting ef ficiency (as counts per transformation),
V is the sample size (in units of mass or vclume),
2.22 is the nu-Oer of transformations per minute per picocurie.
Y is the fractional radiochemical yield (wnen applicable),
A is the radioactive decay constant fer the particular racionuclide, 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 ir, the calculation of the LLD for a cetection b
system shall be based on the actual observed variance of the background counting rate or of the counting rate of the blank samples (as appecpriate) rather than on an unverified theoretically precicted
.ariance.
In :alculating the LLD for a radicnuclide determined by
- a-ma--ay s;;ectrc etr;., *re background shal' incluce the typicai centri
- utiars :# Other racianuclides normal'y present in the samoies.
~ypical 'alues ;f E.
V, Y, and at snall be usec in the calculation.
Se tacs;-cund c._.t rate is calculated frc, the tackgrounc counts that 2-e cete-mirec to be with'., One 4hM (Pull-Winth-at-half-Max imum)
' e g card at:_t 19e energy of the gama -ay ceak used 'c-the
- _3-t' tat.e
- a. sis f0r
- rat cad 7aruclice.
4 9
0 b11 i
fj 6];L A{ta ny3
- - d. pn o
u n-m k
=
TABLE 4.11-2 (Continued)
TABLE NOTATION b.
Analyses shall also be performed following shutdown, startup, or similar operational occurrence which could alter the mixture of radionuclides.
c.
Not Acplicable.
d.
Samples shall be changed at least once per 7 days and analyses shsll be ccmpleted within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> af ter charging (or af ter rem val from sampler).
Sa.mpling and analyses shall also te 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 shutcown, startup or thermal power level change exceeding 15% of RATED TH RNAL POWER in one hour.
When sample collected for 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> are analyzee, the cor-responding LLD's may be increased by a factor of 10.
Tritium grab samples shall be taken at least once per 7 cays from e.
the ventilation exhaust from the spent fuel pool area.
f.
The ratio of the sample flow rate to the sampled stea9 fl0w rate shall be knowr. for the time period covered by each dcse or dose rate calculation made in accordance with Specificatiens 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-83, Xe-133, Xe-133m, Xe-135, and Xe-138 for gaseous emissions anc Mr-54, Fe-59, Co-58, Co-60, Zn-65, Mo-99, Cs-134, Cs-137, Ce-141 and Ce-144 for particulate emissions.
This list does not mean that only these nuc-lides are to be detected and reported.
Other peaks wnich are measure-able and identifiable, together with the above nuclices, shall also be identified and report.
Nuclides which are below the LLD for the analyses shall be reported as "less than" the nuclide's LLC and shall not be reported as being present at the LLD level for that nuclide.
The "less than" values shall not be used in the required dose calcul-tions.
9 jl
- 3-:
3/4 11-11
(
RADICACTIVE EFFLUENTS OSE - NrBLE GASES LIMITING CCNDITION FOR OPERATION 3.11.2.2 The air dose due to noble gases released in gaseous effluents from
- ne site (see Figure 5.1.3-1) shall be limited to the fcliowing:
a.
Curing any calendar quarter:
Less than or equal to 5 mrad for gam a radiation and less than or equal to 10 mrad for beta raciation, ar.c b.
During any calendar year:
Less than or equal to 10 mrad for ganma radiation and less than or equal to 20 mrac for beta radiation.
(The dose design objectives shall also be reduced based on exOected public occupancy of areas, e.g., beaches and visitor centers within the site boundary.)
APDLICABILITY:
At all times.
ACTICN a.
With the calculated air dose from radioactive noble ga3es 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 icentifies the cause(s) for exceeding the limit (s) anc defines the corrective actions to be taken to reduce the releases of radioactive noble gases in gaseous ef fluents during the remainder o' the current calendar quarter and during the subsequent three calencar quarters so that the cumulative dose during these four calendar quarters is within 10 mrad for gamma radiation and 20 mrad for ceta radiation.
b.
The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.
SURVEILLANCE REQUIREMENTS c.'
.:.2
- se Calculations Cumulative dose contributions for the current
- :;- :;a-te-a-d cur e-t ca'encar year shall be determined in accordar.ce
- e ::CY st least c ce esery 31 days.
)
^) D I g I
QC 0
3/4 il-12 m
,I 1 $
PADI0 ACTIVE EFFLUENTS DOSE - RADICI00!NES. RADI0 ACTIVE MATERIALS IN PARTICULATE FORM. AND RADIONUCLIDES OTHER THAN NCBLE GASES, LIMITING CONDITION FOR OPERATION 3.11.2.3 ne cose to an individual from radiciodines and radioactive materiais in particulate form, and radionuclides (other than ncble gases) with half-lives greater than 8 days in gaseous effluents released from the site (see Figure 5.1.3-1) 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 mram to any organ.
(The dose design objectives shall be reduced based on predicted carbon.14 releases releases if effluent sampling is not provided.)
APPLICABILITY:
At all times.
ACTION:
a.
With the calculated dose from the release of radiciodines, radioactive materials in particulate 'orm, or radionuclides (other than noble gases) with half lives greater than 8 days, 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 and defines the corrective actions to be taken to reduce the releases of racio-iodines and radioactive materials in particulate form, anc radio-nuclides (other than nobles gases) with half-lives greater than 8 days in gaseous effluents during the remainder of the current calendar quarter and during the subsequent three calencar quarters, so that the cumulat've dose or dose commitment to an indivicual from such releases der'ng these four calendar quarters is within (15) mrem to any organ.
9e p cvisions of Specifications 3.0.3 and 3.0.4 are not applicacie.
7 JuO.E:- nNCE RECUIREMENTS cse Calca;aticns :_mu;at've cose contributions fc-the cur-ant
- ar
__a-ter and current cale car year shall te cetermined in accerca-ce
'*-a
^3CV at ' east once every 31 cays.
L
- :-: E-:
3/4 11-13
, - P,
>v
=
RADICACTI'.'E EFFLUENTS G ASECUS R AC'a ASTE TRE ATPENT LIMIT!N3 CCNCITION FCR OPERATION 3 'i.2.4 The gaseous rac~aste treatment system shall be in operation.
neneser the main concenser air ejectcr system is in cperaticn.
A;rL::AE L:Ti:
n A:TICN:
With the gaseous rac~aste treatment system incperable for mere than a.
7 days, in lieu of any other eport required y Specification 6.9.1, prepare and submit to the Cor.. mission within 30 days, pursuant to Specification 6.9.2, a Special Report which iacludes the folicwing information:
1.
Identification of the inoperable equipment or su0systers anc the reason for inoperability, 2.
Action (s) taken to restore the inoperable equipment to CPERAELE status, anc 3.
Summary description of action (s) taken to prevent a recurrence.
Tne provisions of Specifications 3.0.3 and 3.0.4 are not applicable.
O.
SURVEILLANCE RECUIREMENTS 4.11.2.4 The gaseous racwaste treatment system shall be demonstrated OPERABLE by operating the gaseous radwaste treatment system equipment for at least minutes, at least once per 92 days unless tne system has been utilized to process radioactive gaseous effluents during the previous 92 days.
C' D
D L es eu n'
F D
3 w
(
_J Ma
^4 11-14 J '.)
a 3ADI0 ACTIVE EFFLUENTS VENTILATION EXHAUST TREATMENT LIMITING CONDITION FOR OPERATION 3.11.2.5 The appropriate portions of the ventilation exhaust treatment system shall OPERABLE and be use: to reduced radioactive materials in gasecus waste prior to their discharge wnen the projected deses cue to gasecus e' fluent releases from tne site (see Figure 5.1.3-1) when averaged over 31 cays would exceed 0.3 mrem to any organ.
APPLICABILITY:
At all times.
ACTION:
With the ventilation exhaust treatment system inoperable for more a.
than 31 days, or with gaseous waste being cischarged 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.
Identificaticr. 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 Specifications 3.0.3 and 3.0.4 are not applicable.
SURVEILLANCE REQUIREMENTS 4.11.2.5.1 Doses due to gaseous releases from the site shall be projected at least once per 31 days in accordance with the ODCM.
4.11.2.5.2 The ventilation exhaust treatment system shall be demonstrated
- PERABLE by cperating the ventilation exhaust treatment system equipment #or at least minutes, at least once per 92 days unless tne accropriate system nas teen utilized to process radioactive gaseous ef'luents curing tne previcus 32 d?)s.
GN
'^N 1 0 D
Lv cs Cp ']}
~
l[
p I
e dd ; 0]
]L j a 5%:-5 3-:
3/4 11-15
),
L
a 10:0A:TI.E EFFLUENTS EsPLCSI'.'E GAS MIXTURE (Systems designed to withstand a hydrogen explosion)
LIMITING CCNDITION FOR OPERATION 9e concentration of hydrogen or oxygen in the main condenser offgas 3.l'.2.6 7
t' eat ent s stam shall be limited to less than or equal to 4% by volume.
A;0LICAEILITY:
At all times.
ACTICN:
a.
nith the concentration of hydrogen or oxygc in the main concenser offgas treatment system exceeding the lir'., restore the cor. centration 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 />.
The provisiens of Specifications 3.0.3 and 3.0.4 are not applicable.
3.
5JREILLANCE REQUIREMENTS 4.11.2.6 The concentration of hydrogen or oxygen in the main conds7ser offgas treatment system shall be determined to be within the above limits Dy con-tinuously monitoring the waste gases in the main condenser offgas treatment system with tne hydrogen or oxygen monitors required CPERABLE by Taole 3.3.7.12,
cf 5cecification 3.3.7.12.
D h) V D
d 73 oJU_5].Alda 7ei
- .a m-1E
<; l
4 4ADICACTI.E EFFLUENTS EXPLOSIVE GAS MIXTURE (Systems not cesigned to withstand a hydrogen explosion)
LIMITING CONDITION FOR OPERATION 3.ll.2.6A The concentraticn of hydrogen and/or oxygen in the main condenser offgas treatner.t system s.all be limited to less tnan or eoual to 2% by volume.
APPLICABILITY:
At all times.
ACTION:
a.
With the concentration of hydrogen and/or oxygen in the main concenser of fgas treatment system greater than Z% 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 main condenser affgas treatment system greater than 4% by volume, immediately suspend all adciticns of waste gases to the system and reduce the ccncentration cf hydrogen and/or oxygen to less than or equal to 2%
within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />.
c.
The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.
SURVEILLANCE REOUIREMENTS 4.ll.2.6A The concentrations of hydrogen anc/or oxygen in the main condenser offgas treatment system shall be cetermined to be within the above limits by continuously monitoring the waste gases in the main condenser offgas treatment system with the hydrogen and/or oxygen monitors required OPERABLE by Table 3.3.7.12-1 of Specification 3.3.7.12.
2nm
.~i-I 2/4 ':-17 o
'? b L L')
ADICACTIVE EFFLUENTS
- I N CCNDENSER LIMITI",3 CCNDITION FOR OPERATION l'.2.7 The gross radioactivity (beta and/or gamma) rate of ncble gases cssured at the main condenser air ejector sNall be limited to less than or ec.a' to ('00 microcuries/sec/ Ka';).
ADcLICA5ILITv:
At all times.
ACTICN:
aith tne g-css radioactivity (beta and/or gamma) ra:
of ncble gases at the main concenser air ejector exceeding (100 microcuri-s/sec/F'W ),
restore
".e gross adioactivity rate to within its limit within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or be in at least HOT STANCEY wi-hin the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
SURVEILLANCE RECUIREMENTS 4.11.2.7.1 The radioactivity rate of noble gases at (neer) the outlet of the main condenser air ejector shall be continuously monitored in accordance with Specification 3.3.7.12.
4.11.2.7.2 The gross racicactivity (beta and/or gamma) rate of nccle gascs frcT ine Tain condenser air ejector shall be cetermined tc be within the is o' Scecification 3.11.2.7 at the fellowing frequencies by performing an
'imi isotcpic analysis of a representative samcie cf gases taken at tne discharge (prior to dilution and/or discharge) of the main condenser air ejector:
a.
At least once per 31 days.
b.
Within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> folicwing an increase, as indicated by the Condenser Air Ejector Ncble Gas Activity Monitor, of greater than 50%, after factoring out increases due to changes in THERMAL POWER level, in the nominal steady state fission gas release from the primary coolant.
~!
O 34
,3
RADICACTIVE EFFLUENTS MARK I or II CONTAINMENT (Optional)
LIMITI.,G CONDITION FOR CPERATION 3.11.2.8 VENTING or PURGING of the Mark I or II containment drywell shall be theou;9 the Standby Gas Treatment System.
APPLIC EILITY:
Whenever the drywell is vented or purged.
ACTION:
With the requirements of the above specification not satisfied, a.
suspend all VENTING and PURGING of the dryw 11.
Ine provisions of Specifications 3.0.3 ana 3.0.4 are not applica0le.
b.
SURVEILLANCE RECUIRMENTS 3.10.2.8 The containment drywell shall be determined to be aligned for VENTING or PURGING through the Standby Gas Treatment System within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> price to ctart of and at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> during VENTING or PURGING of the drywell.
a
^
./; 11_.c.
r, ',)
t 2,, :
2.ADICACTIVE EFFtUENTS 3/;.11.3
$ LIC RADICACTIVE wA$iE cIMITING CCNDITION FCR OPERATION 3.1 3
"'e so'ic radoaste system shall bc CPERABLE and used, as apolicable in irc;rcarce
-it.- a -HOCE55 CONTROL PRCGRAM, for the SCLI;I:ICATI:N ard packagin; radioactive.sastes to ensure Teeting the requirerents of 10 CFR Cart 20 and
- f 10 CFR Part 71 prior to shi; Tent of radioactive eastes from the site.
,PPLICAEILITY:
At all times.
1CTION:
itn the packaging recuirements of 10 CFR Part 20 and/or 10 CFR Part a.
n71 not satisfiec, suspend shipments of defectively packaged solid scicactive wastes from the site.
D.
nitn tre solic.acoaste system inocerable for more than 21 cays, in ieu Of any ot c-eport recuired by Specification 6.9.', prepare anc suon't to the C:mnission within 30 days pursuant :o 5:ecification 6.9.2 a Special Re: ort whicn includes the following information:
1.
Icentification of the 'noperable equipment or subsystems and tne reason for incperatiility, 2.
Actica(s) taken to restore the incoerable ecuipment to 0;EAELE status, 3
A cescriptien of the alternative used for SOLIDIFICATION and aackaging of radioactive wastes, anc 4
Summary description of action (s) taken to prevent a recurrence.
~he provisions of Specifications 3.0.3 and 3.0.4 are not applicable.
c.
SURVEII. LANCE REQUIREMENT 5
.3.i
~le solic 'acasste sistem snail te cemonstratec "PER;EuE at. east
- " Le
- . ca; 5 D 5.
De'iting !Te 5.
- 3C-aste system i* leas t OrCe '- tre Dre'. ic ui
.r.c.r o.
,4+w tng D ;6 [;..c 3 C. y7 q" i ; ; n.,.~, ;. ; v
-p
+
^.
- ^
4 m
m
.u....
% 4.
3 y
.v L..
..'"'e
.a
.14.
Os
'Ad.-wd v
?.
t
.r-
~
- **r.
.4., ;.;.
- ". ^ 2 in
- w
.w 9
g e d :3 A A-3.
3 Utiau
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0
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RADI0 ACTIVE 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 Datch of each type of wet radioactive waste (e.g., filter sludges, spent resins, evaporator bottoms. and sedium sulfate solutions).
If any test specimen fails to verify SOLIDIFICATION, the SOLIDIFICA-a.
TION of the batch under test shall be suspended until such time as additional 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.
b.
If the initial test specimen from a batch of waste fails to verify
~
SOLIDIFICATION, the PROCESS CONTROL PROGRAM shall provice for the collection and testing of representative test specimens from each consecutive batch of the same type of wet waste urtil at least 3 consecutive initial test specimens demonstrate 50LIDIFCATION.
The PROCESS CONTROL PROGRAM shall be modified as required, as provided in Specification 6.13, to assure SOLIDIFICATION of suosequent batches of waste.
J - T3-I 3/4 11-21 D,u,
RADI0 ACTIVE EFFLUENTS 3/4.11.4 TOTAL DOSE LIMITING CONDITION FOR OPERATION 3.11.4 The dose or dose commitment to any real individual 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 tnan or equal to 75 mrem) over 12 consecutive months.
APPLICABILITY:
At all times.
ACTICN:
With the' calculated dose from the release of radioactive materials a.
in liquid or gaseous effluents exceeding twice the limits of Specifica-tions 3.ll.l.2.a, 3.ll.l.2.b, 3.11.2.2.a, 3.11.2.2.b, 3.11.2.3.a. or 3.II.2.3.b, in lieu of any other re9 ort required by Specification 6.9.i, prepare and submit a Special Report tc the Commission pursuant to Specification 6.9.2 and limit the subsequ'nt releases sucn that the dose or dose commitment to any real individual from uranium fuel cycle sources is limited to less than or equal to 25 mrem to the total body or any organ (except thyroid, which is limited to less than or equal to 75 mrem) over 12 consecutive months.
This Special Report shall include an analysis which demonstrates that radiation exposures to any real individual from uranium fuel cycle sources (including all effluent pathways and direct radiation) are less than tae 40 CFR Part 190 Standard.
Otherwise, obtain a variance from the Commission to permit releases which exceed the 40 CFR Part 190 Standard.
b.
The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.
SURVEILLANCE REQUIREMENTS 4.11.4 Dose Calculations Cumulative dose contributions from liquid and gasecas effluents shall be determined in accordance with Specifications 4.11.1.2, 4.11.2.2, and 4.11.2.3, and in accordance with the ODCM.
- r :-
3/4 11-22 Y
'l D
3/4.12 RADIOLOGICAL ENVIRONMLNIAL MONIIORING 3/4.12.1 MONITORING PROGRAM LIMITING CONDITION FOR OPERATION 3.12.1 The radiological environmental monitoring program shall be conductec as specified in Table 3.12-1.
AP P LICABI L.' T Y:
At all times.
ACTION:
With the radiological environmental monitor'.ng program not being a.
conducted as specified in Table 3.12-1, prepare and submit to the Commission, in the Annual Radiological Opcrating 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, prepare and submit to the Commission within 30 days frcm the end of the affected calendar quarter a Report pursuant to 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 q
submitted if:
concentration (1) concentration (2) +
{q fM limit level (1) limit level (2)
- 1'0 h
9r 1
When radionuclides other than those in Table 3.12-2 are detected and b
)
[O{
are the result of plant effluents, this report shall be submitted if
% P' 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 b
d radioactivity was not the result of plant effluents; however, in such an event, the condition W il be reported and described in the Annual Radiological Environmenu'. Operating Report.
With milk or fresh leafy vegetable samples unavailable from one or c.
more of the sample locations required by Table 3.12-1, in lieu of any other report requirea by Specification 6.9.1, prepare and submit to the Ccmmissicn within 30 days, pursuant to Specification 6.9.2. a Special Report which identifies the cause of the unavailability of sarpies ano identifies locations for obtaining replacement samples.
T"e locations from ohich samples were unavailable may then be deleted
' rom those requ' red by Table 3.12-1, provided the locations from which the replacement samples were obtained are added to the environmental cnitoring program as replacement locations.
c
~~.e provisions of Specifications 3.0.3 and 3.0.J are not applicacie.
a-5 5-;
3/4 12-1
RADIOLOGICAL ENVIRONMENTAL MONITORING
$URVEILLANCE REQUIREMENTS 4.12.1 The radiological environmental monitoring samples shall be collected cursuant to Table 3.12-1 from the locations given in the table and figure in
- "e CCCM and snall be analyzed pursuant to the requirements of Tables 3.12-1 and 4.12-1.
- e;-5 5-!
3/4 12-2
..L
--.' (l l e jy
It.BLL 3.12 _1 sj RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM 4
Number of Samples t xposure Pattra iy and Sampling and Type and frequency and/or Samlyle Sample Locations **
Collection frequency of Analysis 1.
AIRBORNL Radioiodine and (locations 1-5)
Continuous operation of Radioiodine canister.
Particulates sampler with sample col-Analyze at least once lection as required by per 7 days for I-131.
dust loading but at least once per 7 days.
Particulate sampler.
Q 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 /> dd following filter change.
Perform gamma isotopic C@
Q analysis on each sample R
when gross beta activity a
is > 10 times the yearly
[
mean of control samples.
Perform gamma isotopic analysis on composite (by location) sample at least once per 92 days.
2.
DIRECI RADIATION (Locations 1-8)
At least once per 31 days.
Gamma dose.
At least
> 2 dosimeters or > 1 once per 31 days.
or instrument for con; gp 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.)
r.
- Sample locations are given on the figure and table in the ODCM.
TABLE 3.12-1 (ContinuiJi RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Number of Samples txposure Pathway and Sampling and Type and frequency and/or Sample Sample Locations **
Collection Frequency of Analysis 3.
WAlfRBORNE a.
Surface (Locations 9 and 10)
Composite" sample collected Gamma isotopic analysis over a period of < 31 days.
of each composite sample.
Tritium analysis of com-posite sample at least once per 92 days.
b.
Ground (Locations 11 and 12)
At least once per 92 days.
Ganna isotopic and tritium analyses of each c,,
j;
- sample, w
ry c.
Drinking (Locations 13-15)
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 < 31 days.
isotopic analysis of each composite sample.
Tritium analysis of composite sample at least once per 92 days.
r' d.
Sediment from (Locations 18)
At least once per 184 days.
Gamma isotopic analysis Shoreline of each sample.
rs-
.~
^ 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 ODCM.
IABLL 3.12-1 (Continueg)
'E RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM
'f.
Number of Samples
- ~
Exposure Pathway and Sampling and Type and frequency and/or Sample _
Sample Locations **
Collection Frequency of Analysis 4.
INGESTION a.
Milk (LocaLlons 17-20)
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 times.
b.
Fish and (Locations 21 and 22)
One sample in season, or at Gamma isotopic analysis invertebrates least once per 184 days if on edible portions.
not seasonal.
One sample of u,);
each of the following species:
U l.
E' 2.
c.
Food Products (Locations 23-25)
At time of harvest.
One Gamma isotopic analysis sample of each of the fol-on edible portion.
Iowing classes of food products:
1.
2.
3.
(location 26)
At time of harvest.
One I-131 analysis.
sample of broad leaf r
vegetation.
m N
- 5 ample locations are shown on the figure in the ODCH.
r-
t l Alil l 3.12 2 b
iii Pf:!lllNG LEVELS FOR RAD 10ACTit'ITY CONCENTRAT.10 tis IN EilVIR0flMENTAL SAMP! ES I
Reporting Levels Water Airborne Particulate Fish Milk Food Products Analysis (pCi/l) or Gases (pCi/m )
(pCi/Kg, wet)
(pCi/1)
(pCi/Kg,-wet) 3 ll-3 2x 10 4
Mn-54 1x 10 ~3 3x 10 4
o le-59 4x 10 Ix 10 i
i Co-58 1x 10 3x 10 i G-
]
i Co-60 3x 10 1 x 10 fM h
2
()
In-65 3 x 10 2 x 10 tr-Nb-95 4 x 10 2
I-131 2
0.9 3
1 x 10 Cs-134 30 10 1 x 10 r,0 I x 10 Cs-137 SO 20 2x 10 70 2x 10 B a - l. a - 14 0 2 x 10 3 x 10 iIi) For drinking water samples.
This is 40 CFR Part 141 value.
(b) lotal for parent and daughter.
~..
,M L.c
IABLE 4.12-1 MAXIMUM VALUES FOR THE 10WER LIMITS OF DETECTION (LLD)'
~
Airborne Particulate Water orGa3 Fish Milk Food Products Sediment Analysis (pCi/1)
(pCi/m )
(pCi/kg, wet)
(pCi/l)
(pCi/kg, wet)
(pCi/kg, dry)
I
-2 gross beta 4'
1 X 10 Q
~
b il 2000 (1000 )
d Co Mn 15 130 h
ie 30 260 a8,60 130 Co 15 65 260 h
In 30 1
Zr-Nb IS
[
C f
l
-2 I3I l'
7 X 10 1
60 l
134,137 15 (10'), 18 1 X 10~
130 15 60 150 t
Cs c
O c
jg Ba-ta 1S IN_
~ _.
WQ
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 radiochemical separation):
4.66 s b LLD = E exp(-Aat)
Y 2.22 V
Where:
LLD is the lower limit of detection as defined above (as picocurie per u.1it mass or volume),
is the standard deviation of the background counting rate or s b the counting rate of a blank sample as appropriate (as oT 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 b
system shall be based on the actual observed variance of the background counting rate or of the counting rate of the blank samples (as apprcoriate) rather than on an unverified theoretically predicted variance.
In calculating the LLD for a radionuclice 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 mil k samples).
Typical values of E, V, Y and at shall be used in the calculations.
EWR-575-I 3/4 12-8
-c
'} ~ )
,)
TABLE 4.12-1 (Continued)
TABLE NOTATION b
LLD-for drinking water.
c Total for parent and daughter.
d' Other peaks which are measurable and identifiable, together with the radionuclides in Table 4.12-1, shall be identified and reported.
L7, d/
- ,q-s s-3/4 12-9
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 4.11.2.3.1, 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 (s).
b.
With a land use census identifying a location (s) which yields a calculated dose or dose commitment (via the same exposute pathway) 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.
c.
The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.
SURVEILLANCE REOUIREMENTS 4.12.2 The land use census shall be conducted at least once per 12 morths between the dates of (June 1 and October 1) by a door-to-door survey, aerial survey, or by consulting local agriculture authorities, using that inf ormation which will provide the best results.
- 3rcac leaf vegetation sampling may be performed at the site bouncary in tne cirectior. sector sitn the highest D/Q in lieu of the garcen census.
.7; 5-I 3/4 12-10
!. l I L
RADIOLOGICAL ENVIRONMENTAL MONITORING 3/4.12.3 INTERLABORATORY COMPARISON PROGRAM LIMITING CONDITION FOR OPERATION
?.12.3 Analyses shall be performed on radioactive materials supplied as part 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 4.12.3 A summary of the results cbtained as part of the above recuired Interlaboratory Comparison Program and in accordance with the CDCM shall be included in the Annual Radiological Environmental Operating Report.
Ea;-ST3-I 3/4 12-11 O
, f
'u l'. I U
B INSTRUMENTATION BASES 3/4.3.3.9 RADI0 ACTIVE LIOUID EFFLUENT INSTRUMENTATION The radicactive liquid effluent instrumentation is proviced to monitor anc control, as applicable, the releases of radioactive materials in liquid effluents during actual or potential releases of liquid effluents.
The alarm /
trip setpcints for these instruments shall be calculated in accordar:e 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 wi*.h the requirements o' General Design Criteria 50, 63 and 64 of Appendix A to 10 CFR Part 50.
3/4.3.3.10 DADI0 ACTIVE GASEOUS EFFLUENT INSTRUMENTATION The radioactive gaseous effluent instrumentation is provided to monitor and control, as applicable, the releases of radioactive materials in gaseous effluents during actual or potential releases of gaseous effluents.
The alarm / trio 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 OFERASILITY 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.
2 -
's-:
3 3/4 3-5 s>
- f
3/4.11 RADI0 ACTIVE E/FLUENTS BASES 3/4.11.1 LIOUID EFFLUENTS 3/4.11.1.1 CONCENTRATION This specification is provided to ensure that the concentraticn :f radio-active materials released in liquid waste effluents from the site will be less than the concentration levels specified in 10 CFR Part 20, Appendix E, Table II, Column 2.
This limitation provides additional assurance that the levels of radioactive materials in bodies of water outside t7e site will result in exposures within (1) the Section II.A design objectises of Appendix I, 10 CFR 50, to an indivicual and (2) the limits of 10 CFR 20.106(e) to the population.
The concentration }init for dissolved or entrained noble gases is based upon the assumption that Xe-135 is the controlling radioisotope and its MPC in air (submersion) was converted to an equivalent concentration in water using the methods described in International Commission on Radiological Protect:en (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 Cond; tion for Operation implements the guides set forth in Section II.A of Appendix 1.
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 ef fleunts will be kept "as low as is reasonably achievable".
Also, for fresh water sites with drinking water supplies which can be potentially affected by plant operations, there is 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 Apper. dix I be shown by calculational procedures based on models and data, such that the actual exposure of an individual through appro -
priate pathways is unlikely to be substantially underestimated.
The equations specified in the ODCM for calculating the doses due to the actual release rates of radicactive materials in liquid effluents are consistent with the et,ccoloqj provided in Regulatory Guide 1.109, " Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance witn 10 CFR Part 50, Appendix I," Revision 1, October 1977 and Regulatory Guide 1.113, " Estimating Aquatic Dispersion of Effluents from 1:cicental and Routine Reactor Releases for the Purcose of Implementing ascend'x : " April '977.
7-is specification applies to the release of liquid effluents from each
' e a c *. o r at the site.
Fcr units witn shared radwaste treatment systems, tne iq.ic effluents ferm the snared system are proportioned among the units
.3r',;
n c. t system.
o,n i
_. m
$i
- I*
E 3/c l*1
('(
\\mt a
RADI0 ACTIVE EFFLUENTS BASES 3/4.11.1.3 LIOUID WASTE TREATMENT The OPERABILITY of the liquid radwastu 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 icw as is reasonably achievable".
This specification implements the requirc.nents 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 liqu'd 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.c LIQUID HOLDUP TANKS Restricting the quantity of racicactive 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 EFFl.UENTS 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 tne annual dose 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.l.
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 bouncary, to annual average concentrations exceeding the limits specified in Appendix 3, TaDie II of 10 CFR Part 20 (10 CFR Part 20.106(b)(1)).
- or individuals who may at times be within the site boundary, the occupancy of the incividual will be sufficiently low to compensate.for any increase in the atmospheric dif fusion f actor abcve that fcr the site bouncary.
The specified elease rate limits restrict, at all times, the corresponding gamma and beta Jose rates above background to an 'ncividual at or beyond the site boundary to
'ess than cr equal to 500 mrem / year to the total bocy or to less tnan or ecual to 3000 nrem/ year to the skin.
These release rate limits also restrict, at all times, the corresponding thyroic cose rate above ba:kground to an
- I B 3/4 11-2
(.')
I
[Oi
RADIOACTIVE EFFLUENTS BASES infant via the cow-milk-infant pathway to less than or equal to 1500 mrem /
year for the nearest cow to the plant.
This specification applies to the release of gaseous effluents frcm 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 OOSE - NOBLE GASES This specification is provided to implement the requirements of Sections II.3, III.A and IV.A of Appendix I, 10 CFR Part 50.
The Limiting Condition for Operation implements the guides set forth in Section 11.8 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" The Surveillance Requirements implement the requirements in Section III.A of Appendix I that conformance with the guides of Appendix I be shown by calculational procedures based on models and data such that the actual exposure of an individual through appropriate 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 noole gases in gaseous effluents are consistent with the methodology provided in Regulatory Guide 1.109, " Calculation of Annual Doses to Man f rom Routine Releases of Reactor Effluents for the Purpose of Evaluating Ccmpliance 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 ODCM equations provided for determining the ai.r doses at the sita boundary are based upon the historical average. atmospheric conditions.
3/4.11.2.3 DOSE, RADI0 IODINES, RADI0 ACTIVE 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 IV.A of Appendix I, 10 CFR Part 50.
The Limiting Condition for Cperation are the guides set forth in Section II.C of Appendix I.
The ACTION statements provide the required operating flexibility and at the same time implement the guides set forth in Section IV.A of Appendix I to assure that the releases of radioactive materials in gaseous effluents will be kept "as low as is reasonaoly achievable" The ODCM calculational methods specified in tne Surveillance Requirements implement the requirements in Section III.A of Lopendix ! that conformance with the guides of Appendix I be shown by calcula-tional procedures cased on mocels and data, such that the actual exposure of 39 inlivicual through appropriate pathways is unlikely to be substantially ecer.stimated.
The CDCM calculational methods for calculating the coses due m
IL( b
~'
2,
-STS-I B 3/4 11-3
RADIOACTIVE EFFLUENTS
-BASES to the actual release rates of the subject materials are consistent with the methodology provided in Regulatory Guide 1.109, " Calculation of Annuai Doses to Man frcm Rcutine Releases of Reactor Effluents 'or the Purocse cf Evaluating Ccepliance with 10 CFR Part 50, Appe.-' x I," Revision 1, Octoter lET and Regulatory Guide 1.111
" Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light-Watsr-Coolec Reactors," Revision 1, July 1977.
These equations alsc provide for cetermining the actual doses based upcn the historical average atmospheric concitions.
The release rate specifications for radiciodinc3, radioactive materials in particulate form and radionuclides other than noole gases are dependent en the existing radionuclide pathways to man, in the unrestricted area.
The patnways which were examine / in the development of these calculations were:
- 1) individual inhalation of airborne radionuclides, 2) deposition of rad- 'uclides onto
- een leafy vegetation with subsequent consumption by man, 3) ceposition onto grassy areas waere milk animals and meat producing animals graze with consump-tion of the milk and meat by man, and 4) deposition on the ground with subsecuent exposure of man.
3/4.11.2.4 AND 3/4.11.9.5 GASEGUS RA0 WASTE TREATnENT AND VENTILAT:0N EXHAUST TREATMENT The OPERABILITY of the gaseous radwaste treatment system anc the ventila-tion exhaust treatment sjstem ensures that the systems will De available for use whenever gaseous effluents require treatment prior to release to the environment.
The requirement that the appropriate portions of these systems be used, when specified, provides reasonable assurance that the releases of racioactive 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.0 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.C.6 EAPLOSIVE GAS MIXTURE This specification is provided to ensure that the concentpation of potentially explosive gas mixtures contained in the waste gas noicap system 's maintained below the flammability limits tf hydrogen and cxygen.
(Autcmatic
- crtrc' features are included in tre system to crevent the hycroge' and oxygen ccrcertrations from reacning these 'lammability limits.
'tese aut:nat ic cert ci 'eatures incluce isolation of the source of hydroger anc/c-or.cen.
sutcmatic civersion to recombiners, or injection of d'lutants tc ecace tne cc,:ertration celcw the C ar-stility limits.) Mainta'ning : e co centration
53crocon ano oxygen below tneir 'lammability limits prcvices assurance trat
-'e ess-s of racloactive aterials oill be centrol'ed in ccnfo 9a ce with
.irenents of General Cesign Criterion 60 o' Accendix A to 10 CFR Dart 50.
c Op l[gtndhL E..-
- -I B 3/4 11 % '
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nn010AClivt EFFtdENTS BASES 3/4.11 2.7 MAIN CONDENSER Restricting the gross radioactivity rate of noble gases from the main concenser prov# des reasonaDie assurance that the total body exposure to an individual at tr.e exclusion area boundary will not exceed a small fraction of the limits of 10 CFR Part 100 in the event this effluent is inadvertently discharged directly to the environment without treatment.
This specification implements the requirements of General Design Criteria 60 and 64 of Appendix A to 10 CFR Part 50.
3/4.11.2.8 MARK I CONTAINMENT (OPTIONAL)
This specification provides reasonable assurance that releases from crywell pruging operations will not exceed the annual dose limits of 10 CFR Part 20 for unrestricted areas.
3/4.11.3 SOLID RADIOACTIVE WASTE The OPERASILITY of the solid radsaste system ensures that the system will be available for use whenever solid radwastes require processing and packaging prior to being shipped offsite.
This specification iraplements 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 cont'nt, 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 real individual will exceed 40 CFR 190 if the individual reactors remain within the reporting recuirement level.
The Special Report will describe a course of action which shca'd result in the limitation of dose to a real individual for 12 consecutive mcotts to within the 40 CFR 190 linits.
For the urposes of the Special Repo-t, it may be assuned that the cose commitment to the real indivicual from other uranium fuel cycle sources is negligible, with the exception that dose contributions frcm other nuclear feel cycle facilities at the same site or wi thi, 3 radius of 5 miles must be considered.
P00R MirilhL
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- D'E" 9
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8 3/4 11-5 L1 ~,.
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a 3/4.12 RADIOLOGICAL ENVIRONMENTAL MONITORING BASES 3/4.12.1 MONITORING PROGRAM Ine radiciogical monitoring program required by this specification provides measurements of radiation and of radioactive materials in those exposure pathways and for those radionuclides, which lead to the highest potential radiation exposures of individuals resulting from the station operation.
This monitoring program thereby supplements the radiological effluent monitoring program by verifying that the measurable concentratiers of radioactive materials and levels of radiation are not higher than expected on the basis of the effluent measurements and modeling of the environmer;al exposure pathways.
The initially s;ecified monitoring program will be effective for at least the first three years o'f commercial operation.
Following this period, program changes may be initiated based on operational experience.
The cetection capabilities required by Table 4.12-1 are state-of-the-art fcr routine environmental measurements in industrial laboratories.
The LLD's for drinking water meet the requirements of 40 CFR 141.
3/4.12.2 LAND USE CENSUS This specification is provided to ensure that changes in the use of unrestricted areas are identified ano 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 sinc ( a garden
~ ~ ~ ~
' f this size is the minimum required:tomproduce the quantityz(26,kg/ year.);of. --..
o
- - ' ~
leafy vegetables assumedlin.Regulatocy Guide.4.109ifor consumption by.a child,s u.
To determine this minimum garden size, the following assumptions were used, 1) that 20% of the garden was used-for:gr.owing ebroad : leaf..vegetationa(i:_e. c -
similar to lettuce and cabbage), and 2) a vegetation yield of 2 kg/ square meter.
3s4.'2.3 INTERLABORATORY COMPARISON PROGRA,M Tre requirement for participa+'
ui an Interlaboratory Comparison Program is cro icec to ensure that indep_ovent checks on the precision and accurary cf
' e easc ements of radioactic. material in environmental sample matrices are as part of the cuality assurance program for environmental monitcring cer':
e: to ceronstrate that the results are reasonably valid.
rce'
- 3-:
6 3/4 12-1
.c r d0J
- 5. 0 DESIGN FEATURES 5.1 SITE EXCLUSION AREA 5.1.1 The exclusion area shall be as shown in Figute 5.1.1-1.
LOW POPULATION ZONE 5.1.2 The low population zone shall be as shown in Figure 5.1.2-1.
SITE BOUNDARY FOR GASEQUS EFFLUENTS 5.1.3 The site boundary for gaseous efflue.its shall be as shown in Figure 5.1.3-1.
SITE BOUNDARY FOR LIQUID EFFLUENTS 5.1.4 The site boundary for liquid effluents shall be as shown in Figure 5.1.4-1.
5.2 CONTAINMENT CONFIGURATION 5.2.1 The primary containment is a steel lined presetressed ccncrete structure consisting of a drywell and suppression chamber.
The drywell is in the form of a truncated cone on top of a cylindrical suppression chamber attached to the suppression chamber through a series of downcomer vents.
The primary con-tainment has a minimum free air volume of (273,000) cubic feet.
DESIGN TEMPERATURE AND PRESSURE 5.2.2 The primary containment-is designed and shal1 be mamtained :for:
a.
Maximum internal pressure (45 psig).
b.
Maximum internal temperature:
drywell (340) F.
suppression chamber (275)*F.
c.
Maximum external pressure (2) psig.
e.
Maximum floor cifferential pressure:
(25) psid, downward.
(9) psic, upward.
D D
oo 1"
m o
Jd 2.\\ L L a o
au
- y. -S. I 51
This figu-e 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 FIGURE 5.1.1-1
- --iTS-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 shall be indicated in sufficient detail to allow identification of significant shifts in population distribution within the LPZ.
LOW POPULATION ZONE FIGURE 5.1.2 -1 E'nR ' i-I 5-3 C77
[ i-( O
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 ce sufficiently detailed to allow identification of structures and release point elevations, and areas within the site boundary that are accessible by members of the general public.
See NUREG-0133 for additional guidance.
SITE BOUDARY FOR GASEOUS EFFLUENTS FIGURE 5.1.3-1
.=-5 5 -
s-a L ' i,'
g d ')
a 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-tien of structures near the release points and areas within the site boundary where ground and surface water is accessible by members of the general public.
See NUREG-0133 for additional guidance.
SITE BOUNDARY FOR LIOUID EFFLUENTS FIGURE 5.1.4-1 ra:-sTS-!
5-5
/ :/ O
6 ALL STS-I SECTION 6.0 ADMINISTRATIVE CONTROLS G
E'
l l
E.0 ADMINISTRATIVE CONTROLS 6 c.1 UNIT REVIEW GROUP (URG)
FESPONSIBILITIES 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 t!.e corrective action to prevent recurrence to the (Superintendent of Pcwer Plants) and to the (Company Nuclear Review and Audit Group).
1.
Review of major changes te radwaste systems.
6.5.2 COMPANY NUCLEAR REVIEW AND AUDIT GROUP (CNPAG)
AUDITS 5.5.2.8 Aucits of unit activities shall be performed under the cognizance of the (CNRAG).
These audits shall encumpass:
1.
The radiological environmental monitoring program and the results thereof at least once per 12 months.
The OFFSITE DOSE CALCULATION MANUAL and implementing procedures at m.
least once per 24 months.
The PROCESS CONTROL PROGRAM and implementing procedures for solidifica-n.
tion of radioactive wastes at least once per 24 months.
The performance of activities required by the Quality Assurance o.
Program to meet the criteria of Regulatory Guide 4.15, December 1977 at least once per 12 months.
5.8 PROCEDURES 5.3.1 Written precedures shall be established, implemented and maintained covering the activities referenced below:
g.
PROCESS CONTROL PROGRAM implementation.
h.
OFFSITE DOSE CALCULATION MANUAL implementation.
i.
Cuality Assurance Progran for ef fluent and environmental ronitoring,
. sing the guicance in Regulatory Guide 4.15.
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ACMINISTRATIVE CONTROLS A!
ONUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT 6.9.1.6 Routine radiological environmental operating reports covering the oparation 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.
5.9.1.7 The annuci radiological environmental operating reports shall include st.mmaries, interpretations, and an analysis of trends of the results of tne radiological environmental surveillance activities for the report perioc, ir.cluding a comparison with preoperational studies, operational controls (as appropriate), and previous environmental surveillance r uorts and an assessment of the observed impacts of the plant operation on the eivironment.
The reports shall also include the results of land use censuses re ;uired by Specification 3.12.2. If harmful effects or evidence of irr_eversible 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.
Tr.e annual radiological environmental operating reports shall include summarized and tabulated results in the format of Regulatory Guide 4.8, December 1975 of In the all radiological environmental samples taken during the report period.
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.
Tae reports shall also include the following:
a summary description of the radiological environmental monitoring program; a map of all sampling locations kayed 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.
S SEMIANNUAL RADI0 ACTIVE EFFLUENT RELEASE REPORT 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 data of initial criticality.
The submittal A single suomittal may be made for a multiple unit station.
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shoulc combine those sections that are common to all units at the station; for units with separate radwaste systems, the submittal shall M-ever,
- tecih ' c releases of raoicactive material f rom each unit.
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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 Plar.ts," Revision 1, June 1974, with data summarized on a quarterly ca:i's following tne format of Appendix B thereof.
The radioactive effluent release report to be submitted 60 days after January 1 of each year and shall include an annual summary of hourly meteorological data collected over the previous year.
This annual summary may be either in the form of an hour-by-hour list'ng of wind speed, wind direction, atmospheric stability, and precipitation (if measured) on magnetic tape, or in the form of jcint frequency distributions of wind speed, wind direction, and atmospheric stability.
This same report shall include an assessment of the radiation dcses due to the radioactive liquid and gaseous effluents released from the unit or station during the previous calendar year.
This~same report shall also include an assessment of the radiation doses from radioactive liquid ant' gaseous effluents to individuals due to their activities inside the site ocundary (Figures 5.1-3 and 5.1-4) during the report period.
All assumptions used in.aking 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 determining the gaseous pathway doses.
The assessment of radiation doses shall be performed in accordance with the Offsite Dose Calculation Manual (CDCM).
The radioactive effluent release report to be submitted 60 days after January 1 of each year shal-1 also include an assessment of radiation doses to the likely most exposed real individual from reactor releases and other nearby uranium fuel cycle sources (including-doses fremr primary-ef. fluent. pathways.and direct, radiation) for the previous 12 consecutive-months to.'iow conformance with.
40 CFR 190, Environmental Radiation Protection Standards for Nuclear Power Operation.
Acceptable methods-for calculating.the-dose contribution frem.
liquid and gaseous effluents are given in Regulatory Guide l.-109, Rev. 1..
T.ie radioactive effluent release reports shall include the following information for each type of solid waste shipped offsite during the report period:
a.
container volume, b.
total curie quantity (specify whether determinec by measurement or estimate),
W,cipal radionuclices (specify whether cetemir.ed by measurement c.
er estimu
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type of waste (e.g., spent resin, compacted dry waste, evaporator bottoms),
type of container (e.g., LSA, Type A, Type B, Large Quantity), and e.
f.
sclidification agent (e.g., cement, u.ea formaldehyde).
Tne radioactive effluent release reports shall include inolanned releases frem the site to unrestricted areas of radioactive materials in gaseous and liquid effluents on a quarterly basis.
The radioactive effluent release reports shall include cly changes to the PROCESS CONTROL PROGRAM (PCP) made during the reporting period.
.#.ONTHLY REACTCR OPERATlNG REPORT 6.3.1.10 Routine reports of operating statistics and shutdown experience shall be submitted on a monthly basis to the Director, Office of Management Program Ana'ysis, U.S. Nuclear Regulatory Commission, Washington, D.C.
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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 mace effective.
In addition, a report of any major changes to the radioactive waste treatment systems shall be submitted with the Monthly Operating Report for the period in wnich 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 ef fluents which exceed the limits of Specification 3.11.1.1 or 3.11.2.1.
Exceeding the linits 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 witt.in the specif'ed limits.
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ADu.INISTRATIVE CONTROLS THIRTY DAY WRITTEN REPORTS 6.9.1.13 An unplanned offsite release of 1) more than 1 curie of radioactive e.
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.
Measured levels of radioactivity in an environmental sarpling 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.
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4 ACMINISTRATIVE CONTROLS 6.13 PROCESS CONTROL PROGRAM (PCP) 6.13.1 The PCP shall be approved by the Corrrnission 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:
sufficiently detailed information to totally support the rationale a.
for the change without benefit of additi nal or supplemental information; b.
a determination that the change did not reduce the overall conformance of tne solicified waste product to existing criteria for soi.J wastes; and c.
documentation of the fact that the change has been reviewed and found acceptable by the (URG).
2.
Shall become effective upon review and acceptance by the (URG).
6.14 0FFSITE DOSE CALCULATION MANUAL (ODCM) 6.14.1 The 00CM shall be approved by the Commission prior to implementation.
6.14.2 Licensee initiated changes to the ODCM:
1.
Shall be submitted to the Commission in the Monthly Operating Report within 90 days of the date the chanr?(s) was made effective.
This submittal shall contain:
a.
sufficiently detailed information to trtally support the rationale a
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 apprepriate analyses or evaluations justifying the change (s);
b.
a determination that the cnange 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 accentacle by the (URS).
2.
3 :ii become eff?ctive upon review ata roMwa % the (URG).
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ADMINISTRATIVE CONTROLS 6.15 MAJOR CHANGES TO RADI0 ACTIVE WASTE TREATMENT SYSTEMS (Liquid, Gtseous 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 summary of the evaluation that led to the determination that a.
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 comparison of the predicted releases of radioactive materials, in liquid and gaseous effluents and in solid waste, to the actual releases for the period prior to when the changes are to be made; g.
.an estimate of the exposure to plant operating personnel as a result of the change; and h.
documentation of the 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
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