Text

Draft Radiological Tech Specs for Facility
	ML20064H850
Person / Time
Site:	McGuire, Mcguire
Issue date:	10/30/1978
From:	; DUKE POWER CO.
To:	;
Shared Package
ML20064H848	List: ML20064H846; ML20064H850;
References
	RTR-NUREG-0472, RTR-NUREG-472 NUDOCS 7812270214
	Download: ML20064H850 (67)
	v • d • e

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cr' <9 NUREG-0472 d

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,.4 ORAFT RADIOLOGICAL EFFLUENT TECHNICAL SPECIFICATI0t5 iraljae.leavbSen

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w Revision 1 October 1978 L

em eERWID 9

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e 1.0 DEFINITIONS l

l CHANNEL CALIBRATION l.9 A CHANNEL CALIBRATION shall be the adjustmeh't, as necessary, of the l

, channel output such that it responds with the necessary range and ac,:uracy jto known values of the parameter.which the channel monitors. The CHANNEL iCALIBRATION shall encompass the entire channel including the sensor and dalam and/or trip functions, and shall include the CHANNEL FUNCTIONAL TEST.

I

~is The CHANNEL CALIBRATION may be perfomed by any series of sequential, over-

'; lapping or total channel steps such that the entire channel is calibrated.

dCHANNEL CHECX 31.10 A CHANNEL CHECK shall be the cualitative assessment of channel be-

.havior during operation by observation. This detamination shall include,

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qwhere possible, comparison of the channel indication and/or status with

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other indications and/or status derived from independent instrumentation gchannels measuring the same parameter.

CHANNEL FUNCTIONAL TEST 1.11 A CHANNEL FUNCTIONAL TEST shall be:

i; a.

Analog channels - the injection of a simulated signal into m

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the channel as close to the sensor as practicable to verify OPERABILITY including alam and/or trip functions.

b.

Bistable channels - the injection of a simulated signal into the sensor to verify OPERABILITY including alam and/or trip functions.

I USCURCE CHECX 71;1.29 A SOURCE CHECK shall be the qualitative assessment of channel l

[ response when the channel sensor is exposed to a radioactive source.

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I lPWR-5TS-1 1-1 6

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t 1.0 DEFINITIONS (Continued)

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l l0FFSITE DOSE CALCULATION MANUAL (00CM)

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1.32 An CFFSITE DOSE CALCULATION MANUAL (00CM) shall be a manual.contain-

'ing the methodology and parameters to be used in the calculation of off-site doses due to radioactive gaseous and liquid effluents and in the

, calculation of gaseous and liqufd effluent monitoring instrumentation s

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alam/ trip setootnts. Requirements of the 00CM are provided in iSpecification 6.15.

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~ GASEOUS RADVASTE TREATMENT SYSTEM

[1.33 A GASECUS RA0 WASTE TREATMENT SYSTEM is any system designed and in-istalled to reduce radioactive gaseous effluents by collecting primary

! coolant system offgases fra the primary system and providing for delay

!or holdup for the purpose of reducing the total radioactivity prior to

[reiease to the environment.

I VENTILATION EXHAUST TREATMENT SYSTEM 1.34 A VENTILATION EXHAUST TREATMENT SYSTEM is any system designed and

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installed to reduce gaseous raciofodine or radioactive material in parti-culate fem in effluents by passing ventilation or vent exhaust gases through charcoal adsorcers and/or HEPA filters for the purpose of removing iodines or particulates frem the gaseous exhaust stream prior to the reiease to the envircr:6ent. LC:.;j;ta i: n:: ::::H :r:d t Mrfe W cffx t :: :M: ;;; c f 9 ;;r t:. Engineered Safety Feature (ESF) atnospheric cleanup systens are not considered to be VENTILATION EXHAUST TREATMENT SYSTEM caponents.

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TABLE 1.2 FREOUENCY NOTATION

,0 NOTATION FREOUENCY S

At least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

O At least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

y

-'7.

W At least once per 7 days.

M' At least once per 31 days.

Q At least once per 92 days.

SA At least once per 184 days..-

R At least once per 18 months. -

S/U Prior to each reactor startup.

P Completed Prior to each release.

N.A.

Not applicable.

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INSTRUMENTATION RADI0 ACTIVE LIOUID EFFLUENT INSTRUMENTATION LIMITING CONDITION FOR OPERATION

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'3.3.3.8 The radioactive liquid effluent monitoring instrumentation jichannels shown in Table 3.3-11 shall be OPERABLE with their alarm / trip isetpoints set to ensure that the limits of Specification 3.11.1.1 are not exceeded.

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APPLICABILITY: As shown in Table 3.3-11.

ACTION:

-l a.

With a radioactive liouid effluent monitoring instrument.ation channel alann/ trip setpoint less conservative than a value which will ensure that' the limits of 3.11.1.1 are met, imme-1 diately suspnd the release of radioactive liquid effluents monitored by the affected channel or declare the channel in-

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operabl e.

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b.

With one or more radioactive licuid effluent monitoring in-J.

strumentation channels inoperable, take the ACTION'shown in Table 3.3-11.

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c.

The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

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?. SURVEILLANCE RE0'JIREMENTS

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4.3.3.8.1 The set:oints shall be detennined in accordance with fE:N8: 9

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1,as described in :ne CDCM and shall be recorded. S 2: :n-dH 'v.

q i4.3.3.8.2 Each radioactive liquid effluent monitoring instrumentation 5,4 channel shall be demonstrated CPERABLE by perfonnance of the CHANNELjC

'joperations during the MTODES and at the frequencies shown in Table 4.3-11.

4.3.3.8.3 Recerds - Auditable records shall be maintained, te-eeeeeeeeee f 5 pr =n: " Sc N",

of all radioactive liquid effluent jmonitoring instrumentation alann/ trip setpoints. Setpoints and setpoint calculations shall be available for review to ensure that the limits of

' Specification 3.11.1.1 are met.

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RADI0 ACTIVE Lif)UID EFFLUENT HONITORING INSTRUMENTATION S

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IllSTRUMENT OPERABLE APPLICABILITY ACTION 1.

Gross Radioactivity Monitors Providing Automatic Termination of Release Wasle LiquiJ l.ine (1)

At all tines 18 a.

De[de l

1 o

i'2.

Gross Radioactivity Honitors

$1 flot Providing Automatic Termination of Release a.

Connalwaal W4 FewaferTra4(m.,{

the (1)

. At all times 20 -

b.

bla'AmedWahldew (A.if Adeele hie (1)

At all times 20

Includes rinse, flush, and slurry waste from secondary system condensate deep bed demineralizer or filter-demineralizers.

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RADI0 ACTIVE LIQUID EFFLUENT HONITORING INSTRillENTATION

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HINIHt11 CllANNELS INSTRt# LENT Ol'ERABLE Al'PLICABILITY ACTION l.

Flow Rate Measurement Devices **

. Waste. li oil Line (1)

At all times 21 a.

S h.

Discharge Canal (1)

At all times 21 I

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Pianp curves may be utilized to estimate flow; in such cases, action statement 21 is not required.

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- Required only if alarm / trip set point is based on recorder-controller.

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'I' RADI0 ACTIVE LIQUID EFFLUENT HONITORING INSTRUMENTATION HINIHUH CllANNELS INSTRUMENf OPERABLE APPLICABILITY ACTION

!K Continuous Composite Samplers and Sampler Flow Honitor a.

Com=fdoal esla=aler Ttwinient (1)

At all times 19 Like

y b.

fe.tlab.m.+ W liidin 0,4f 6 4mcale (1)

At all times 20 lieic P.

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y.

Tincludes rinse, flush, and slurry waste from secondary system condensate deep bed demineralizer or filter-demineralizers.

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TABLE 3. 3 11

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(Continued)

. v ~d TABLE NOTATION ACTION 18 With the numeer of channels OPER _

Minimum Channels OPERABLE requirement resumed for up to 14 days, provided thatABLE F

, effluent releases may be a release:

prior to initiating 1.

with SpecificationAt least two independent samples a 4.11.1.1.3, and; a yzed in accordance 2.

At least two technically qgli Staff independently verifyf,fie pbers of the Facility

.,._q and discharge valving; re ease rate calculations gi v.sMr Otherwise, suspend release of radioacti g

pa thway.

ve effluents via this l

ACTION 19 With the number of channels OPER Minimum Channels OPERABLE requiremen

, effluent releases via a limit of detection of at least 10~/ uC1/g eta or gamma) at C

1.

m; At least once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months when the specifi s

secondary coolant is > 0.01 uCi/ gram DOSE EQUI M.f c activity of the Q

2.

At l.

NT I-131.

secondary coolant is < 0.01 uC1/ gram

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y of the ACTION 20 With the numbers of channel I-131.

Minimum Channels OPERABLE requirement least once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months grab samples

, effluent releases via ays provided that at for gross radioactivity- (

detection of at least 10 geta or gamma)e collected and analyzed uCf/mi.

at a lower limit of ACTION 21 With the numoer of channels OPERAB Minimum Channels CPERABLE requirementt LE less than required by the

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, effluent releases via rate is releases. estimated at least once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months during actu r

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RADI0 ACTIVE LIQUID EFFLUENT HONITORING INSTRUMENTATION SURVEILLANCE REQulREPENTS Td CllANNEL CilANNEL SOURCE CilANNEL FUNCTIONAL INSTR'* LENT CllECK CllECK CALIBRATION TEST 1.

Gross Deta or Ganina Radioactivity Honitors Providing Alarm and Auto-matic Isolation ble Liquid line.

D*

P R(3)

Q(1) a.

(\\ b t.c.Re 1

E' r.

2.

Gross Deta or Ganina Radioactivity y

Monitors Providing Alarm Dut f)9J gh j;

Providing Autanatic IsolationL a,

conymluh4 varle*4erTveAbed 1:in D*

H R(3)

Q(2) b.

A l.b. 4 %. fit 4 4 t)W } c u de.,sai c D*

H R(3)

Q(2)

Line 3.

Continuous Composite Samplers and Sample Flow Heasierement Device a.

8.mwheial wasleolev Treab..#

D*

N/A R

Q Line b.

N14 nie 1 Widilafi,s. U.JF de 44asolo D*

N/A

'R Q

Line s

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TABLE 4.3-11 (Continued)

TABLE' NOTATION i

0uring releases via this pathway.

- 0uring liquid additions to the ' tank.

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'Y'T (1) The CHANNEL FUNCTIONAL TEST shall also demonstrate that automatic isolation of this pathway and control room alam annunciation occurs if W:f *2: f:!! M n; ::rditi:n: ::1:*-

X strument inaicates measured levels above the alam/ trip.

setpointx oitd Skalt do.y shh. h+ ce nMI vee alarm newndabli oecurs W aq of %c w flewi $ ce d+ie.a uish I

IX.

Circuit failure.

27 Instrument indicates a downscale failure.

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Instrument controls not set in operate mode.

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(2) The CHANNEL FUNCTIONAL TEST shall also descutrate that ;ontrol roan alam annunciation occurs if any of the following conditions exist:

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1.

Instrument indicates measured levels above the alarm / trip setpoint.

2.

Circuit failure.

3.

Instrument indicr.es a downscale failure.

ly 4.

Instrument controls not set in operate mode.

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(3) The initial CHANNEL CALIBRATION for radioactivity measurement in-strumentation shall"be perfomed using one or more of the reference standards certified by the Nat1onal Bureau of Standards or using standards that have been obtained frem suppliers that participate in measurement assurance activities with NBS. These stancards should pemit calibrating the system over its intended range of energy anc rate capabilities. For suosecuent CHANNEL CALIBRATION, sources that have been related to the initial calibration should be used, at in-tervals of at least once per eighteen months. This can nomally be accomplished curing refueling outages.

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1 TABLE 4.3-11 (Continued)

(4) This requirement is applicable only to systems where the service water system or component ccoling water system is discharged to an effluent stream.

, ' iZ (5) CHANNEL CHECX shall consist of verifying indication of flow during periods of release. CHANNEL CHECK shall be made at least once daily on any day on which continuous, periodic, or batch releases are made.

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INSTRUMENTATION j,RADI0 ACTIVE GASEOUS PROCESS AND EFFLUENT MONITORING INSTRUMENTATION

!LIMITINGCONDITIONFOROPERATION h

3.3.3.9 The radioactive gaseous process and effluent monitoring instru-mentation channels shown in Table' 3.3-12 shall be OPERABLE with their alarn/ trip setpoints set to ensure that the limits of Specifica-tion 3.11.2.1 are not exceeded.

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APPLICABILITY: As shown in Table 3.3-12.

IACTION:

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With a radioactive gaseous process or effluent monitorinh in-a.

trumentation channel alam/ trip setpoint less conservative F

than a value which wilt ensure that the limits of 3.11.241 are met, declare the channel inoperable.

[

b.

With one or more radioactive gaseous process or eff1 cent monitoring instrumentation channels inoperacle, take the ACTION shown in Table 3.3-12.

1 c.

The provisions cf Specification: 3.0.3 and 3.0.4 are not appl icabl e.

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SURVEILLANCE REOUIREMENTS 4.3.3.9.1 The setpoints shall be detemined in accordance with ek:

$ T

..as described in the ODCM and shall be recorded f ; t c ':::ti:d 1:;.

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. 4.3.3.9.2 Each radioactive gaseous process or effluent monitoring instrumen-f tation channel shall be demonstrated OPERABLE by perfomance of the CHANNEL i CHECX, SOURCE CHECX, CHANNEL CALIBRATION, and CHANc3L FUNCTIONAL TEST opera-tions during the MOCES and at the frequencies shown in Table a.3-12.

4.3.3.9.3 Auditable recYrds.shall be maintained of the calculations e, 1

d: :: d th preert r::

W TT, of all radioactive precess and effluent monitoring instrumentation alam/ trip setpoints.

Set:oints and, setooint calculations shall be available-for review to ensure that the ylimits of Specification 3.11.2.1 are met.

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TAHLE 3.3-12 t

RAD 10AtilVE CASE 005 EFFLUENT HONIToltING instill #lENTATION

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CilANNELS Ol'ERAllLE APPLICARILITY fAllAMETER ACTION INSTRtMENT 1.

Wasic Gas Iloldup System.

Noble Gas Act'1ylty Honttor (1)

Radioactivity Rate

,a.

25

, Heasurement 4

Dc \\tW I

sg d.

Ef fluent Systegi Flow Rate (1)

System Flow Rate 26 Heasuring Device Heasurement u

'e.r Sampler flow Itate Heasuring **.

d

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Samphr-How-itate 26-Device.

Heasurement 2A. Waste Gas lloldup System Explosive Gas Honitoring System flee nt!=:

das4p ed-ta wIihstac4 the-e M eets i

(4-a-liyui oucu exp ius ion) a.

Ilydrogen Monitor (1)

% llydrogen 29 b.

Ilydrogen or oxygen Honitor (1)

% llydro9en or Oxygen 29

+k All e((lbeal Ow yus -14 rom l, lh we,,iIsr P8 M

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TABLE 3.3-12 (Continued) h',$

RADIDACTIVE GASEQUS EFFLUENT HONITORING INSTRUMENTATION b

h HINIMUM i

CllANNELS INSTRUMENT OPERABLE APPLICABILITY PARAMETER ACTION

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3.

Contaltunent Purge lionitoring System y.,

l Radioactivity Rate 27 a.

Noble Gas Activity Honitor (1)

Heasurement g,

m Verify presence of 31 b.

lodine Sampler Cartridge (1) cartridge Verify presence of filte h '

31 c.

Particulate Sampler Filter (1) 9 System flow Rate 26 d.

Effluent System Flow Rate (1)

Heasuring Device Measurement W60u a m *J....o.o i

t e.

Sampler flow Rate Heasuring (1)

Sanlpler Flow Rate 26 3

Device Heasurement l

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TABLE 3.3-12 (continued)

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yi RADI0 ACTIVE GASEOUS EFFLUENT HONITORING INSTRlMENTATION L

$1

[

HINIMUM l

CllANNELS INSTRlMENT OPERABLE A g CABILITY PARAMETER ACTION 4.

u.iaveosGas a.

Noble Gas Activity Monitor (1)

Radioactivity Rate Measurement 27 b.

Iodines 4mpler[artridge(1)

Verify presence of cartridge 31 c.

Particu14te Sampler Fitter (1)

Vertfy presence of filter 31 d.

Effluent System Flow u

E Rate Measuring Device (1)

System Flow Rate Measurement 26 u

Si e.

Sampler flow Rate a Ein;nw n.

W;.{ler Flow Rate Measurement Heasuring Device (1)

Samp 26 3

3. Oo_tdguitC[1 edo(

t a.

Noble Gas Activity Radioactivity Rate Measurement 27 Monitor (1)

De \\eit i

d.

Eftluent System Flow System Flow Rate Heasurement 26 Itate Measuring Device (1) f/.(llerFlowRateMeasurement a m ee'eem p.w c.

Sampler flow Rate Sami 26 Measuring Device (1) 3 fa aboire elt e,oun' dis'< feeled Oe. gas ewoiiiles; pave'o.eit ?arficulale 45.ccf e.we ]r<a(,

I4' a$es/if,nt be Icafen jto goan<ti d

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ease sosug ew

t TABLE 3.3-12 (Continued) m TABLE NOTATION

)

lof

During releases via this pathway.

.s.

"Ouring waste gas holdup system. operation (treatnent for primary system 2

offgases).

J 1

ACTION 25 With the number of channels OPERABLE less than required by the

',4 Minimun Channels OPERABLE requirement, the contents of the tank

.I may be released to the envirorment for up to 72 hm;; provided

,7 that prior to initiating the release:

R4

]

r 1.

At least two independent samples of the tank's contents h'

are analyzed, and 2.

At least two technically qualifiedeembers of the Facility s

Staff independently verifyS*"r18)IPlse rate calculations

j and discharge valve lineup;

.p Otherwise, suspend release of raqd oactive effluen/frip sah...~h se.+ -3 3

04+b+G. %4 H4Jn d ew.

.nde b ul alav ts via this pathway.

ACTION 26 With the number of channels OPERABLE less than recuired by the

1..

Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue for up to 28 days provided the flow rate is estimated at.least once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

l ACTION 27 With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue for up to 28 days provided grab samples are taken at least once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months and these samples are analyzed for gross activity within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

.(

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ACTION 28 (Deleted)

ACTION 29 With the numbYr of channels CPERABLE less than required by the Minimum Channels OPERABLE requirement, operation of the waste gas holdup system may continue for up to 28 days provided crab l

samples are collected at least onc'e per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months and analyzed j

within ensuing 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

i.

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TABLE 3.3-12 (Continued)

TABLE NOTATION

.a ACTION 31 With the number of channels OPERABLE less than required by the Minimin Channels OPERABLE recuirement, effluent releases via this pathway may continue for up to 28 days, provided samples are continuously collected with auxiliary sampling equipment for periods on the order of seven (7) days and analyzed within g,

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48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months of the end of sampie collection.

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b.

i PWK-375-1 3/4..a.5a I

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l TABLE 4.3-12 A

7' RADI0 ACTIVE GASEGUS EFFLUENT HONITORING INSTRUHENTATION SURVEILLANCE REQUIREMENTS I'l l'

CilANNEL CilANNEL SOURCE CilANNEL FUNCTIONAL i

INSTRl41ENT CllCCK CilECK CALIBRATION TEST 1.

Waste Gas lloldup System a.

Noble Gas Activity Honitor P*

P R(3) 4(1) b.

Iodine Sampler Cartridge Da N/A N/A N/A ParticulateSamp19rFilter Da +

N/A N/A N/A c.

d.

Systen Effluent Flow Rate P*

N/A R

Q

~

Heasuring Device Sampler flow Rate Measuring #

D' N/?,

R Q-e.

2.

Waste Gas lloldup System Explosive i'

Gas Monitoring System E

'a.

flydrogen Monitor (alternate)

D**

N/A Q(4)

M

(.. c.

Oxygen Honitor Da*

N/A Q(5)

H

'e8 G

9 Allr(fiveal Goao goes Mrs.,9. gaa,,,. %

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TABLE 4.3-12 (Continued)

RADI0 ACTIVE GASEQUS EFFLUENT HONITORING INSTRUMENTATION SURVElLLANCE REQUIREMENTS o

i.s "i

CllANNEL Y'

CllANNEL SOURCE.

CilANNEL FUNCTIONAL INSTRUMENT CilECX CilECK CAllDRATION TEST 3.

Containment Purge Vent System i

a. Noble Gas Activity Monitor D*

P R(3)

Q(1)

b. Iodine Sampler y

D*

N/A N/A N/A

c. Particulate Sampler D*

N/A N/A N/A

d. System Effluent flow Rate D*

N/A R

Q i

Heasuring Device

~

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e. Sampler Flow Rate Measuring D*

N/A R

Q Device l

El al.

UsM hed-Cas a.

Noble Gas Activity Honitor D*

M R(3)

Q(2) s b.

Iodine Sampler D*

N.A.

c.

Particulate Sampler D*

N.A.

d.

System Effluent flow Rate Heasurement Device D.*

N.A.

R

'Q e.

Sampler Flow Rate Measurement Device D*

N.A.

R Q

e s

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m e,

e.

l

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TABLE 4.3.12(Continued)

RADI0 ACTIVE GASEOUS EFFLUENT HONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS

$1 CllANNEL SOURCE CilANNEL CilANNEL FUNCTIONAL INSTRUMENT y

- CllECK CllECK CALIBRATION TEST

.f.

Dadwser Air 61' clef e

a.

Noble Gas Activity Honitor 0*

H R(3)

Q(2) y ete\\c l

\\>. jlf System Effluen( Flow Rate Measurement Device D.*

N.A.

R

'Q c: e.' Sampler flow Rate Heasurement Device D*

N.A.

R -

Q

~

R.

4 e9

?

I Q

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t TABLE 4.3-12 (Continued)

TABLE NOTATION

,+

During releases via this pathway.

"During waste gas holdup system' operation (treatnent for primary system offgases).

(1) The CHANNEL FUNCTIONAL TEST shall also demonstrate that automatic isol if.gion of this pathway and control room alarm annunciation occurs

.v the ';1bd ag c;nditicas exist:

)<

Instrtrnent indicates measured levels above the alam/ trip setpointrand sh(\\ itmea%+hd cedralmenu davmonnun da.hek m.euS9 am c+ %. CeIIcwiq cndih6a unt :

[ K.

Circuit failure.

1X.

Instrument indicates a downscale failure.

3 E.

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 exist:

1.

Instrument indicates measured levels above the alarm / trip setpoint.

2.

Circuit failure.

3.

Instruient indicates a dcwnscale failure.

4.

Instrument controls not set in operate mode.

l I

(3) The initial CHANNEY CALIBRATION for radioactivity measurement in-strumentation shall be perfonned using one or more of the reference standards certified by the National Bureau of Standards or using standards that have been obtained from suppliers that participate in measurement assurance activities with NBS. These standards should pemit calibrating the system over its intended range of energy and rate capabilities. For subsequent CHANNEL CALIBRATION, sources that have been related to the initial calibration should be used, at in-tervals of at least once per eighteen months. This can nomally be accanplished during refueling outages.

Cai::in; pi: t:

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' 3/4 3-62

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TABLE 4.3-12 (Continued) w (4) The CHANNEL CALIBRATION shall include the use of standard gas samples containing a nominal:

i 1.

On: :1 =: Mr:: t hyd :::n, balance ait c;en; and l

2.

Four volume percent hydrogen, balance nitrogen.

- (5) The CHANNEL CALIBRATION shall include the use of standard gas samples containing a nominal:

i.

Or.e selse gc ;nt ;y;;n, b:1:::: nit :; n; :nd 2.

Four volume percent oxygen, balance nitrogen.

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P'dR-STS-1 3/4 3-63 96 w

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f 3/4.11 RADIOACTIVE EFFLUENTS 3/4.11.1 LIOUID EFFLUENTS CONCENTRATION i

LIMITING CONDITION FOR OPERATION 3.11.1.1 The concentration of radioactive material relea' sed at anytime from the site to unrestricted areas (see Figure 3.11-1) shall be limited

.; to the concentrations specified in 10 CFR Part 20, Appendix B, Table II, e _.

i Column 2 for radionuclides other than dissolved or entrained noble gases.

For dissolved or entrained noble gases, the concentration shall be limited to 2 x 10-* uti/ml total activity.

APPLICABILITY: At all times.

ACTION:

With the concentration of radioactive material released from the site to

(

unrestricted areas exceeding the above limits, immediately restore' con-centration within the above limits and provide prompt notification to the Commission pursuant to Specification 6.9.1.12.

I SURVEILLANCE REOUIREMENTS

~$ -

4.11.1.1.1 The concentration of radioactive material at any time in t

liquid effluents released from the site shall be ::nti;;:::1; monitored in accordance with Table 3.3-11.

4.11.1.1.2 The liquid effluent sent4* vees monitors having provisions for autcmatic termination of. liquid releases, as listed ?n Table 3.3-11, shall be used to limit the concentration of radioactive material released at any time from the site to unrestricted areas to the values given in Speci-fication 3.11.1.1.

(

4.11.1.1.3 The radioacy waste to be discharged s!,vity content of each batch of radioactive liquid na11. be determined prior to release by sampling and analysis in accordance with Table 4.11-1.

The results of pre-release analyses shall be used with the calculational methods in the ODCM to assure that the concentration at the point of release is limited to the values in Specification 3.11.1.1.

4.11.1.1.4 Post-release analyses of samples frcm batch releases shall' be performed in accordance with Table 4.11-1.

The resul ts of the post-re'

<e analyses shall be used with the calculational methods in the ODCM to assus e that the concentrations at the point of release are limited to O

the values in Specification 3.11.1.1.

PWR-STS-1 3/4 11-1 e em e

me e

' ~

e

' SURVEILLANCE REOUIREMENTS (Continued) 4.11.1.1.5 The radioactivity concentration of licuids discharsed frem j

continuous release points shall be determined by collection and analysis i

of samples in accordance with Table 4.11-1.

Thy results of the analyses ishall be used with the calculational methods ih the ODCM to assure that jthe concentrations at the point of release are ifmited to the values in c+7 iSpecification 3.11.1.1.

i m

'4.11.1.1.6 Reoorts.

The semiannual Radioactive Effluent Release Report shall include tne information specified in Specification 6.9.1.9.

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TABLE 4.11-1 RADIDACTIVE LIOUID WASTE SAMPLING AND ANALYSIS PROGRAM Lower Limit' Sampling Minimum Type of Activity of Detection Liquid Release Type crequency Analysis Analysis (LLD)

Frequency (uCi/mi)a D

r-9 A. Batch Waste Re-Each Batch Each Batch Principal.Gama 5 x 10-7 9

1 ease Tanks 8 Emitters 3 I-131' 1 x 10-6 P

One Batch /M -

M Dissolved and 1 x 10-8 Entrained Gases

'(

P H'

1 x 10-5 Each Batch

.. :M ". -

CompositeC Gross a 1 x 10-7

?-3C 1 x 10 8 4

Sr-29, Sr-90 5 r. 10 Each Batch Q.

Compositec Fc ~-

1 x 10-6 d

B.

Plant Continuo'us Continucus W

Principal Gama b

d Releases f Composite Emitters 9 5 x 10-7

'(

I-131 1 x 10-6 7

Grab Sample M

Dissolved and Entrained Gases 1 x 10-5 d

H-3 1 x 10-5 Continuous g

d Composite

,7 P- :

1 x 10-6 d

~

Continuous g

Sr-89, Sr-90 5 x 10-8 Composited

,... e. ;.- 6

~

~'

PWR-STS-1 374 yy,3

s, l

TABLE 4.11-1 (Continued) 4 TABLE NOTATION t

a.

The lower limit of detection (LLD) is defined in Table' Notation a. of Table 4.12-1 of Specification 4.12.1.1.

..,._,a t

{

b.

For certain radionuclides with low gamma yield or low energies, or for i

certain radionuclide mixtures, it may not be possible to measure radio-l nuclides in concentrations near the LLD. Under these circumstances, the LLD may be increased inver ely proportionally to the magnitude of the gamma yield (i.e., 5 x 10 /I, where I is the photon abundance 4

expressed as a decimal fraction), but in no case shall the LLD, as j

i calculated in this manner for a specific radionuclide, be greater than 10% of the MPC value specified in 10 CFR 20, Appendix B t

Table II, Column 2.

A caposite sample is one i' which the quantity of liquid sam' pled is c.

n proportional to the quantity of liquid waste discharged and in which

(

t.he method of sampling employed results in a specimen wnich is repre-sentative of the liquids released.

j d.

To be representative of the quantities and concentrations of radio-

, :i active materials in liquid effluents, samples shall be collected continuously in proportion to the rate of flow of the effluent stream.

Prior to analyses, all samples taken for the caposite shall be thoroughly mixed in order for the composite sample to be representa-

?,Ci tive of the effluent release.

~

e.

A batch release is the discharge of liquid wastes of a discrete r

vol me.

f.

A continuous release is the discharge of liquid wastes of a non-discrete volume; e.g., from a volume of system that has an input flow during the continuous release.

A>

g.

The principal gamma emitters for which the LLD specification will

. apply are exclusiyely the following radionuclides: Mn-54, Fe-59, Co-58, Co-60, Zn-c1, Mo-99, Cs-134, Cs-137, Ce-141, and Ce-144 This list does not mean that only these nuclides are to be detected and reported. Other peaks which are measurable and identifiable, together with the above nuclides, shall also be identified and reported. Nuclides which are below the LLD for the analyses should not be reported as being present at the LLD level. When unusual circumstances result in LLD's higher than required, the reasons shall be documented in the semiannual Radioactive Effluent Release Repo rt.

i l

l PWR-STS-1 3/4 11-4 i

l 1

~

l This figure shall consist of a map of the site area showing the unre-stricted area boundary for liquid effluents as defined in 10 CFR Part 20.3(a)(17).

( Vse. 68.,h'guve 21.l 2 S

Cep oIIeden3

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' Figure 3.11-1 w

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RADIOACTIVE E FLUENTS DOSE LIMITING CONDITION FOR OPERATION

~

3.11.1.2 The dose or dose commit:nent to an individual from radioactive materials in liquid effluents released to unrestricted areas (see figure 3.11-1) shall be limited:

1; I'

a.

During any calendar quarter to j 1.5 mrem to the total body and to j 5 mram to any organ, and b.

During any calendar year to j 3 mren to the total body and to j 10 mrem to any organ.

1 j

2 (APPLICABILITY: At all times.

b i

I ACTION:

t

.!'j 6

a.

With the calculated dose fran the release of radioactive ~ materials 9

in if quid effluents exceeding any of the above limits, prepare and

g i-submit to the Commission within 30 days, pursuant tc Specifica-

-=

i:

tion 6.9.2, a Specir.1 Report (whictridentifies the cause(s) for ex-f ceeding the limit (s) and defines the corrective actions to be i,

taken to reduce the releases of radioactive materials in liquid effluents during r

~

and during the :g::;;;ggqogegggplendar quarter e--

...,............ r, ~ r ; so tha t the i

!j average dose or dose commitment to an individual frem such re-li leases during these four calendar quarters is within 3 mrem to the l!

total body and 10 mrem to any organ. This Special Report shall jj also include (1) the results of radiological analyses of the l

drinking water source, and (2) the radiological impact on finished drinking water supplies with regard to the reouirements I

of 40 CFR 141, Safe Drinking Water Act.

(41 icabl e m.i.,

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l

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drinking 4t:r : ; ply i: :k;; fr;.; the recaf eing e:a. bcd.r.'

)

b.

The provisions of Specifications 3.0.3 and 3.0.4 are not appl icabl e.

SURVEILLANCE REOUIREMENTS I

!4.11.1.2.1 Dese Calculations. Cumulative dose contributions fecm liquid Ieffluents shall ce ceramineo in accordance with the Offsite Case Calcu-l flation Manual (ODCM) at least once per 31 days.

! 4.11.1.2.2 Recorts. The semiannual Radioactive Effluent Release Report j.shall include tne infomation specified in Specification 6.9.1.9.

t h

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'PWR-STS-1 3/4 11-6 I

l

RADIOACTIVE EFFLUENTS LIOUID WASTE TREATMENT

~

LIMITING CONDITION FOR OPERATION

~

i a

fa6e sobsqve-s'ef Me 3.11.1.3 The id radwaste treatment system shall be OPERABLE. The

' system shall e used to reduce the radioactive materials in liquid wastes prior to their discharge when the projected dose due to liquid effluent releases to unrestricted areas (see Figure 3.11-1) when averaged over 31 days would exceed.QAtr mram to the total body or Av(mrem to any organ.

CW b,7 APPLICABILITY: At all times.

ACTION:

a.

With radioactive liquid waste being discharged without ' treat:nent and in excess of the above limits, prepare and submit to the Commission within 30 days, pursuant to Specification 6.9.2, a i

Special Repor*pwhich includes the following infomation:-

ek liso of 4 3 eArvep.ct, 1.

Identification of equipnent or subsystems not OPERABLE and the reason for inoperability.

2.

Action (s) taken to restore the inoperable equipnen' to t

OPERABLE status.

h.,

3.

%nnmary description of action (s) taken to prevent a recurrence.

b.

The provisions of Specification 3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE REOUIRE!ENTS 4.11.1.3.1 Doses due to liquid releases to unrestricted areas shall be projected at least once per 31 days.

4.11.1.3.2 The licui.d, radwaste system shall be demonstrated OPERABLE at least once per 92 days unless the liquid radwaste system has been utili:ed to process radioactive liquid effluents,during the previous 92 days.

l g

!PWR-STS-1 3/4 11 7 l

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RADIOACTIVE EFFLUENTS LIOUlO HOLDUP TANKS

~'

LIMITING CONDITION FOR OPERATION 3

3.'1 1.1. 4

The quantity of radioactive material contained in each of the

{

following tanks shall be limited to <

curles, excluding tritium and dissolved or entrained noble gases.

l a.

b.

c.

APPLICABILITY: At alI times.

l' ACTION:

With the quantity of radioactive matselal In any of the above a.

listed tanks exceeding the above limit, Immedlately suspend all additi,ans of radioactive material to the tr.nk and within 48 hrs either reduce the tank contents to within the limit or provide

-i i

pecept notification to the Commission pursuant to Specifica-tion 6.9.1.12.

The written followup report shall include' a schedule and descriptlen of activities planned and/or taken to reduce the tank contents to within the above limit.

.g w The provisions of SpectficatIons 3.0.3 and 3.0.4 are not j'

]

b.

{ *,

appl icab le.

SURVEILLANCE RECUIREMENTS

(

4.11.1.4 The quantity of radioactive material contained in each of the above listed tanks shall be determined to be within the abcVe limit by

}

analyzing a representative sample of the tank 8 s contents at least once per 7 days when radioact4ve materials are being added to the tank.

j o'

l

Tanns incluceo in this Speelfication are those outdecr tanks that are not surrounded by liners, d!kes, or walls capable of holding the tank contents cand that do not have tank overflows and crains connected to the liquid

/ cadwaste treatment system.

l FWR-STS-1 3/4 11-2 l

RADI0 ACTIVE EFFLUENTS 3/4.11.2 GASEOUS EFFLUENTS DOSE RATE

, LIMITING CONDITION FOR OPERATION i

j3.11.2.1 The dose rate, at any ' time, in the unrestricted areas (see l Figure 5.1-1) due to radioactive materials released in gaseous effluents

! rcm the site shall be limited to the following values:

f a.

The dose rate limit for noble gases shall be < 500 mrem /yr to the total body and 3 3000 mrem /yr to the skin 7 and b.

The dose rate limit for all radiciodines and for all radioactive materials in particulate fom and radionuclides other than noble

[

gases with half lives greater than 8 days shall be 31500 mrem /yr to any organ.

L APPLICABILITY: At all times.

,ACTIOH:

.With the dose rate (s) exceeding the above limits, immediately decrease the u! release rate to canply with the limit (s) give in Specification 3.'11.2.1

- Iand provide prompt notification to the Commission pursuant to Specifica-tion 6.9.1.12.

. SURVEILLANCE REOUIRENNTS l

t I

'4.11.2.1.1 The release rate, at any time, of noble gases in gaseous effluents shall be controlled by the offsite dose rate as established above in Specification 3.11.2.1.

(

4.11.2.1.2 The noble gas effluent :r.thab monitors having provisions for the automatic temination of gaseous releases, as listed in Table 3.3-12, shall be used to limit offsite doses within the values established in Specification 3.11.2.lghen monitor setpoint values are exceeded.

4.11.2.1.3 The release rate of radioactive materials, other than noble gases, in gaseous effluents shall be detemined by obtaining representative samples anc perfoming analyses in accordance with the sampling and analysis program, specified in Table 4.11-2.

i.

PWR-STS-1 3/4 11-9

<1

~

SURVEILLANCE REOUIREMENTS 4.11.2.1.4 The dose rate in unrestricted areas., due to radioactive materi-als other than noble gases released in gaseous effluents, shall be deterriined to be within the required limits by using the resugtgfg4he g ~" l

{

~

Hi ! ! 3. M ?. 22 2 I.M...M2.M..#..M...M.... i. f.:

2.:.5 !P?5.....!..,..". * *.

4.11.2.1.5 Recorts The semiannual Radioactive Effluent Release Report shall include tne information specified in Specification 6.9.1.9.

(

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1 P'.iR-STS-1 3/4 11-10 4

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TABLE 4.11-2 RADI0 ACTIVE GASEOUS WASTE SAllPLING AND ANALYSIS PROGRAM Minimum Lower Limit of g,

Sampilng Analysis Type of Detection (LLD)

Gaseous Release Type frequency frequency Activity Analysis-(gg j)a g

R P

h 1 x 10-4b

~

A.

Waste Gas Storage Each Tank Each Tank Principal Gamme Emitters Tank Grab Samile 11-3 1 x 10-6

)

P c

Each Purge Principal Gaassa Emit _terU 1 x 10-4b C

D.

Containment Purge Each Purge Grab (

li-3 1 x 10-6 Sample C.

Condenou Air M

H PrincipalGaeunaEmitterd

___ 1 x 10-4b Ej'eeb Grab

~

1 x 10'6 H-3 Sample f=

D.

O.id %gt Continuous 9 W"

l-131 1 x 10-1.2 Charcoal Sample I-133 1 x 10-10 Continuous

- W" 9

h Particulate Principal Gausna Emitters Saucle (I-131,Others) 1 x 10-II 1 x 10-II l

Continuous 9 H

Gross. alpha Compostte Particulate

.l Sample 1 x 10"II Continuous 9 q

Sr-89, Sr-90 Composite 1

4-Particulate Sample il

TABLE 4.11-2 (Continued)

TABLE NOTATION a.

The lower limit of detection (LLD) is defined in Table Notation a. of Table 4.12-1 of Specification 4.12.1.1.

b.

For certain radionuclides with low gamma yield or low energies, or for certain radionuclide mixtures, it may not be possible to measure radionuclides in concentrations near the LLD. Under these circum-i stances, the LLD may be increased inversely proportionally to the magnitude of the gamma yield (i.e.,1 x 10-4/I, where I is the photon abundance expressed as a decimal fraction), but in no case shall the i

LLD, as calculated in this manner for a specific radionuclide, be greater than 10". of the MPC value specified in 10 CFR 20, Appendix 0, Table II, Column 1.

c.

Analyses shall also be perfomed following shutdown, startup,' or similar operational occurrence which could alter the mixture of radionuclides.

)

g ',e.

Analyses shall also be perfomed at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .for 7 days following each shutdown, startup or similar operational occurrence which could lead to significant increases or decreases in radio-iodine releases. Samplers shall also be changed and analyzed at the

'.T

intentals in Specificationg.;;.2.1 ed 3.11.2.3.

When samples collected for 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months are analyzed, the corresponding LLD's may be increased by a factor of 10.

t-c-g.

The ratio of the sample ficw rate to the sampled stream ficw rate shall be known for the time period covered by eacn dose or dose rate calculation made in accordance with Specification /.;;.2.1,

2. ;'. 2. 2 eM-3.11.J.3.

E.h'.

The principal gamma emitters for which the LLD specification will apply are exclusively the following radionuclides: Kr-87, Kr-88, Xe-133, Xe-133m, Xe-135, and Xe-138. for gaseous emissions and Mn-54, Fe-59, Co-58, Co-60, In-65, Mo-99, Cs-134, Cs-137, Ce-141 and Ce-144 for particulate emissions. This list does not mean that only these nuclides are to be detected and reported. Other peaks which are measurable and identifiable, together with the above nuclides, shall also be identified and reported. Nuclides which are below the LL3 for the analyses should not be reported as being present at the LLD

. level for that nuclide. hen unusual circumstances resul t in LLD's higher than recuired, the reasons shall be dccumented in the semi-annual effluent report.

PWR-STS-1 3/4 11-12 9

RADIOACTIiEEFFLUENTS DOSE, NOBLE GASES

~

LIMITING CONDITION FOR OPERATION I

The air dose in unrestricted areas (seh Figure 5.1-1) due to 3.11.2.2 noble gases released in gaseous effluents shall be limited to the following:

During any calendar quarter, to f 5 mrad for gamma radiation a.

and f 10 mrad for beta radiation; b.

During any calendar year, to j 20 mrad for beta radiation;j 10 mrad for gamma radiation and I

h M e.

x j

i

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APPLICABILITY: At all times.

~

ACTION:

7 et.

'a. Wf th the calculated air dose from radioactive noble gases in 7E' gaseous effluents exceeding any of the above limits, prepare

.& E and submit to the Commission within 30 days, pursuant to Speci 4 '

fication 6.9.2, a Special Report (which identifies the cause(sL*5 for exceeding the limit (s) and defines the corrective actions to be taken to reduce the releases of radioactive noble gases in I"secus e endar q,, p and ur g th"" ".'_

,..,..............,... -.. so tha.

l the average dose during these four calendar cuarters is within

.. (

(10) mrad for gamma radiation and (20) mrad for beta radiation.

b.

The provisions of Specifications 3.0.3 and 3.0.4 are not appl icabl e.

l SURVEILLANCE REOUIREMENTS 4.11.2.2.1 Dese Calculations Cumu' e.tive dose contributions for the total time period snall De cetemineu in accordance with the Offsite Dose Calculation Manual (00CM) at least once every 31 days.

i 4.11.2.2.2 Recorts The semiannual Radioactive Effluent Release Repst shall include tne infornation specified in Specification 6.9.1.9.

~

i

.PWR-STS-1 3/4 11 13 I

=

RADI0 ACTIVE EFFLUENTS DOSE, RADI0 IODINES, RADIOACTIVE MATERIAL IN PARTICULATE FORM, AND RADIONUCLIDES OTHER THAN NOBLE GASES LIMITING CONDITION FOR OPERATION l

3.11.2.3 The dose to an individual from radiciodines, radioactive i

materials in particulate fom, and radionuclides other tnan noble gases with half-lives greater than 8 days in gaseous effluents released to unrestricted areas (see Figure 5.1-1) shall be limited to the following:

a.

During any calendar quarter to j 7.5 mrem to any organ; b.

During any calendar year to j 15 mrem to any organ; and P

'[

i C e_.( d t..

i i

(

i

' APPLICABILITY: At all times.

ACTION:

E:r.

a.

With the calculated dose from the release of radiciodines, i

radioactive materials in particulate fom, or radionuclides other than noble gases in gaseous effluents exceeding any of,g the above limits, prepare and submit to the Commission with- -:

in 30 days, pursuant to Specification S.9.2, a Special Report f y

which identifies the cause(s) for exceeding the limit and defines the corrective actions to be taken to reduce the j

' releases of radiciodines, radioactive materials in particu-late fom, and radionuclides other than noble gases with half-lives greater than 8 days in gaseous effluents during the EEfD[dd..[..r:

4+M__Qg:r ; gar quarter and during the ga ss

__. _e-! so that the average dose or

_- : 7 r. u dose ccumitment to an individual from such releases curing these four calendar quarters is within (15) arem to any organ.

b.

The provisioIs of Specifications 3.0.3 and 3.0.4 are not appl icable.

SURVEILLANCE REOUIREMENTS l

4.11.2.3.1 Dose Calculations Cumulative dose contributions for the total time period snail ce cetamined in accordance with the CDCM at least once every 31 days.

4.11.2.3.2 Recorts The semiannual Radioactive Effluent Release Report shall include tne infomation specified in Specification 6.9.1.9.

PWR-STS-1 3/4 11-14

RADI0 ACTIVE EFFLUENTS GASEOUS RADWASTE TREATMENT 3 LIMITING CONDITION FOR OPERATION The,ppropria+e so psg sto. o+ tm. gaseous radwaste treatment system,a a

, 3.11.2.4 treatment system shall be OPERABLE. The gaseous radwaste treatment system shall be used to reduce radioactive materials in gaseous waste prior to their discharge when the projected gaseous effluent air doses due to gaseous i effluent releases to unres ted areas (see Fidure 5.1-1) n averaged

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over 31 cays would exceed mrad for gamma radiation and mrad for i

! beta radiation and ventilation exhaust treatnent system shall be used to

- : reduce radioactive materials in gaseous waste prior to their discharge when

the projected doses due to gaseous effluent releases to unrestricted areas (see Figure 5.1-1) when averaged over 31 days would exceedhrf arem to any

, organ.

I.%C i APPLICABILITY: At all times.

f 1

i ACTION:

I' a.

With gaseous waste being discharged fo-nore than 31 days without j

treatnent and in excess of the above 1 amits, prepare and submit to the Commission within 30 days, pursuant to Specification 6.9.2, a Special Reporgwhich includes the following infonnation:

l 4 1.~eo 4 any e h r reo.

i 1.

Identification of equ1pnent df s systems not OPERABLE and i

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the reason for inoperability.

j

. m* '

g 2.

Action (s) taken to restore the inoperable equipnent to

(

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OPERABLE STATUS.

I-3.

Summary description of action (s) taken to prevent a re-Y Currence.

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b.

The provisions of Specification 3.0.3 and 3.0.4 are not i

appl icable.

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w n: SURVEILLANCE REOUIREPENTS l'

! 4.11.2.4.1. Ooses due to gaseous releases to unrestricted areas shall be l* projected at least once per 31 days.

..I i

(j4.11.2.4.2 The appropriatt systems shall be demonstrated CPERABLE at least

, once per 92

' radioactive. days unless the appropriate system has been utilized to precess gaseous effluents during the previous 92 days.

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l PWR-STS-1 3/4 11-15

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RADIOACTIVE EFFLUENTS DOSE LIMITING CONDITICN FOR OPERATION 3.11.2.5 The dose or dose commitment to a real inditidual fren all uranium fuel cycle sources is limited to < 25 mrem to the total body or any organ (except the thyroid, which is limited to < 75 mrem) over a j period of 12 consecutive months.

APPLICABILITY: At all times.

ACTION

i a.

With the calculated dose frem.the release of radioactive materials in liquid or gaseous effluents exceeding twice the limits of Specifications 3.11.1.2.a, 3.11.1.2.b, 3.11.2.2.a 3.11.2.2.b, 3.11.2.3.a. or 3.11.2.3.b, prepare and submit a

,, t.do 4q,brpentSoecial Report,,to the Commission pursuant to Specificatio'n 6.9.2 jj anc limit tne subsequent releases such that the dose or dose commitment to a real individual from all craniun fuel cycle sources is limited to < 25 mren to the total body or any organ i

(except thyroid, whien is limited to < 75 mrem) cver 12. consecu-tive months. This Special Report shat 1 in demonstrates that radiation exposures to.gu,d,eg analysis which

...... individuaTg) from all uranium fuel cycle sources (including all effluent J

pathways and direct radiation) are less than the 40 CFR Part 190 Standard. Otherwise, obtain a variance from the

~

i Commission to permit releases which exceeds the 40 CFR i

Part 190 Standard.

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b.

The provisions of Specification 3.0.3 and 3.0.4 are not l

applicable.

1 SURVEILLANCE REOUIREMENTS w.

4.11.2.5.1 Dese Calculations Cumulative dose contributions from licuid and gaseous effluents snall De deternined in accordance with Specifi-catio ns 3.11.1.2.a, 3.11.1.2.b, 3.11.2.2.a, 3.11.2.2.b, 3.11.2.3.a. and 3.11.2.3.b, and in accordance with the Offsite Dose Calculation !!anual (OCCM).

4.11.2.5.2 Reoorts Special Reports shall be submitted as required under Specifica:1or 3.11.2.5.a.

e PWR-STS-1 3/4 11-16

i 1

1RADICAC'.*IVE EFFLUENTS EXPLOS!YE GAS MIXTURE LIMITING CONDITION FOR OPERATION f

dowde d +he. neemWars 3.11.2.fA The concentration of hydrogen o cxygen in the waste gas hoicup g

r, system snall be limited to $ 4t by volume.

,..-j<

APPLICABILITY: At all times.

i ACTICN:

With the concentration of hydrogen or oxygen,ewdren~d % resem%%sm d

a.

in the waste gas holduo system exceeding. the limit, resare

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the concentration to within the limit within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months .

ts b.

The provisions of Spe:1fications 3.0.3 and 3.0.4 are not. -

applicable.

' SURVEILLANCE REOUIREMENTS Tne concentration of hydrogen or oxygendemba=.f Wrecemblaars I d

4.11.2.6A n the waste gas holcup system shall be determined to be within the above limits by continuously monitoring the waste gases in the waste gas hoicup system with the (hy-drogen or oxygen) monitors required CPERAELE by Table 3.3-12 of Speciff-ca ti o n 3. 3. 3. 9.

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3/4 11-17

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RADI0 ACTIVE EFFLUENTS EXPLOSIVE GAS MIXTURE (Systems not designed to withstand a hydrogen expl osion)

,e-

" LIMITING CONDITION FOR OPERATION I.

3.11.2.68 The concentration of hydrogen and/or oxygen in the waste gas

' holdup system shall be limited to j 2% by volume.

APPLICABILITY: At all times.

ACTION:

a.

With the concentration of hydrogen and/or oxygen in the waste gas holdup system > 2". by volume but j 4% by volume, festore the concentration of hydrogen and/or oxygen to within the. limit wtS'M

(

48 hoars.

b.

With the concentration of hydrogen and/or oxygen in the was*a gas holdup system > 4*. by volume, imediately suspend al.1 additions of waste gases to the system and reduce the concentra-

. !g tion cf hydrogen and/or oxygen to f. 2t within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months ..

i

'l c.. The provisions of Specification 3.0.3 and 3.0.4 are not'

^ ;. :

' applicabl e.

s

- SURVEILLANCE REOUIREMENTS 4.11.2.6B.The concentrations of hydrogen and/or oxygen in the waste gas holdup system shall be deternined to be within the abcve limits

'by continuously monitaring the waste gases in the waste gas holdup systes 4tn the hydrogen and/or oxygen monitors required CPERABLE by Table. 3.3-12 of Specification 3.3.3.9.

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FOR-STS-1 3/4 11-13 i:

-lRADICACTIVE EFFLUENTS

^

GAS STORAGE TANKS LIMITING CONDITION FOR OPERATION

,3.11.2.7 The quantity of radioactivity contained in each gas storage tank i

jshall be limited to < 4 curies noble gases (considered as Xe-133).

i

'l.9E+04

APPLICASILITY: At all times

~U ACTION:

a.

With the cuantity of radioactive material in any gas storage tank exceeding the above limit, immediataly suspend all additions of radioactive material to the tank and withiri 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months either reduce the tank contents to within the limit or provide prompt notification to the Commission pursuant to

/

Specification 6.9.1.12.

The written followup report shall

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include a description of activities planned and/or taken to reduce the tank contents to within the above limit.

D.

The provisions. of Specifications 3.0.3 and 3.0.4 are not appl icabl e.

SURVEILLANCE REOUIREMENTS

.u.;

4.112.7 The quantity of radioactive material contained in each gas storage tank shall be detennined to Le within the abcve limit at laast ionce per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months when radioactive materials are being added *w the

! *ank.

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,PWR-STS-1 3/4 11-19

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RAD!0ACTIYf EFFLUENTS 3/4.11.3 SOLID RADIOACTIVE WASTE LIMITING CONDITION FOR OPERATION 3.11.3.1 The solid radwaste system shall be OPERABLE and used to pro-vide for the SOLIDIFICATION of wet solid wastes, for the SOLIDIFICATION

.and packaging of other radioactive wastes, and to ensure the meeting of the reouirements of 10 CFR Part 20 and of 10 CFR Part 71 prior to ship-

'iment f : f::ti /c ::..t:f : : of radioactive wastes from the site.

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I l APPLICABILITY:

At all times.

ACTION:

a.

With the recuirements of 10 CFR Part 20,10 CFR Part 71, and the PROCESS CONTROL PROGRAM of Specification 6.14 not satisfied, suspend shipments of defective containers of solid radioactive wastes from the site.

b.

With the solid radwaste system not OPERABLE for more th$n 31 days, when requ': ad to meet 10 CFR Part 20 and 10 CFR Part 71, prepare and submit to the Commission within 30 days, pursuant to Specification 6.9.2, a Special Report which includes the following information:

1.

Identification of equipment of subsystems not OPERABLE and the reasons for inoperability.

2.

Action (s) taken to restore the inoperable equipment to OPERABLE status.

3.

A description of alternative used for SOLIDIFICATION and packaging of wastes.

,\\

4.

Summary description of action (s) taken to prevent a re-currence.

c.

The provisions ~of Specifications 3.0.3 and 3.0.4 are not appl icabl e.

SURVEILLANCE REOUIREMENTS e

l 4.11 3.1.1 Tha solid radwaste system shall be demonstrated OPERABLE at

/

least once per s? days, er there be the capability for SOLIDIFICATION of waste by meeting one or more of the conditions below:

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PWR-STS-1 3/4 11-20 l

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SURVEILLMICE REOUIRE!*ENTS (Continued)

\\ a.

By perfomance of functional tests of the ecuipment and ccm-ponents of the solid radwaste system.

b-By operating the solid radwaste system'at least once in the previous 92 days in accordance with the PROCESS CONTROL PROGRM.

j c.

Verification of the existence of a valid contract for SOLIDIFI-CATION to be performed in accordance with a PROCESS CONTROL

.j PROGRM.

,4.11.3.1.2 The PROCESS CONTROL PROGRAM of Specification 6.14 shall be i

tused to verify the SOLIDIFICATION of at least one representative test specimen from at least every tenth batch of each type of wet radioactive

waste (e.g., fil ter sludges, spent resins, evacorator bottoms, boric acid solutions, sodium sulfate solutions, and fil ter media).

Tne test'scecimens shall be processed in the radiochemical or waste processing laboratory in accordance'with procedures of the PROCESS CONTROL PROGRAM.

/

a.

If any test specimen fails to verify SOLIDIFICATION, the SOLI-

3:

DIFICATION of the batch under test shall be suspended until

J J.

such time as additional test specimens can be obtained, al-ternative SOLIDIFICATON parameters can be determined in accordance with the PROCESS CONTROL PROGRAM, and a subsequent test verifies SOLIDIFICATION.

SOLIDIFICATION of the batch may then be restmed 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 pro-vide for the collection and testing of representative test specimens from each consecutive batch of the same type of

. wet waste until 3 consecutive initial test specimens demon-strata SOLIDIFICATION.

The PROCESS CONTROL PROGRAM shall be modified as required, as provided in Specification 6.14, to-

, s assure SOLIDIFICATION of subsequent batches of waste.

% ;, b b I-4 y

4.11.3.1.3 Recorts - The semiannual Radioactive Effluent Release Repe erfeam as shall include the folicwing information for each type of solid waste bq.J 4.g,

shipped offsite during the report period:

%.Lsuku a..

container volume, b.

total curie quantity (determined by measurement or estimate),

PWR-STS-1 3/4 11-21 y

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SURVEILLANCE REOUIRDENTS (Cor.tinued) s principal radionuclides (detemined by measurement or ',

c.

estimate),

d.

type of waste (e.g., spent resin, compac sd dry waste eyaporator bottoms),

e.

type of container (e.g., LSA, Type A, Type B, Large Quantity), and f.

solidification agent (e.g., cement, urea formaldehyde).

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3/4.12 RADIOLOGICAL ENVIRONMENTAL MONITORING 3/4.12.1 MONITORING PROGRAM LIMITING CONDITION FOR OPERATION I

s 3.12.1 The radiological environmental monitoring program shall be con-ducted as specified in Table 3.12-1.

APPLICABILITY: At all times.

ACTION:

W1th the radiological enviromental monitoring program not being a.

conducted as specified in Table 3.12-1, prepare and submit to the Commission, in the Annual Radiological Operating Report, a description of the reasons for not conducting the program as required and the plans'for preventing a recurrence. (Deyiations are pemitted from the required sampling schedule if specimens e

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are unobtainable due to ha;:ardous conditions, seasonal unavail-ability, or to malfunction of automatic sampling equipment.

If the latter, every effort shall be made to cmplete corrective 4

action prior to the end of the next sampling period.1 b.

With the level oli' radioactivity in an enviramental sampling medium at one or more of the locations specified in Table 3.12-1 exceeding the limits of Table 6.9-2 when averaged over any calendar quarter, prepare and submit to the Commission within

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30 days from the end of the affected calendar quarter, a Special Report which includes an evaluation of any release conditions, environmental factors or other aspects which caused the limits of Table 6.9-2 to be exceeded. This report is not recuired if the measured level of radioact.vity was not the resul t of plant effluents; however, in such an event, the condition shall be reported and described in the Annual Radiological Environmental

(_

Operating Report.

of the sampleHocations required by Table 3.navN1abY ok any With milk -er ' :21::'y ?:::t2!: sampie c.

12-1, prepare and submit to the Ccamission within 30 days, pursuant to Specifi-cation 6.9.2, a Special Report which identifies the cause of the unavailability of samples and identifies locations for obtaining replacement samples. The locations from which sampies were un-L available may then be deleted from Table 3.12-1 provided the locations from which the replacement samples were obtained are added to the enviromental monitoring program as replacement locations, if available.

4 d.

The provisions of Specifications 3.0.3 and 3.0.4 are not appl icabl e.

PWR-STS-1 3/4 12-1

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...e I SURVEILLANCE REOUIREMENTS 4.12.1.1 The radiological environmental monitoring samples shall be collected pursuant to Table 3.12-1 fra. the 1:0: tic : :h=. :r ef p 2.12-1 and shall be analyzed pursuant to the requirements of i

Tables 3.12-1 and 4.12-1.4 Ii4.12.1.2 Recorts - The results 'of analyses perfomed on the radio-

!: logical enviromental monitoring samples shall be summarized in the 5: Annual Radiological Enviremental Operating Report, pursuant to

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Specification 6.9.1.6.

fI on 7.I'l.-f chews.supid leefou.v'ad'4 auch sob id +o c.ka.ge g

3 bede Iaad use casus vuo Ns.

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TAfil.E 3.12-1 RADIOLOGICAL EllVIR0fli4EllTAL I40lll10 RING PROGRAll 05

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llumber of Samples 5o Exposure pathway and Sampling and Type and frequency E!

anil/or Sample Sampic Locations" CoIIcction frequency of Analysis 1.

AIRIlORllE t.

.dio.4 i scs W 6,,Q.'

r 'r :i c.. des, (p.,,c,')

a.

Radiciodine Continuous operation of Radiciodine c.anister.

and partic-L or< ~ i a i.. tc 6,,,,,b,,.,.

sampler uith sample col-r,..,v s i sologic. ca.i.g. ;.,

ulates N E 5.c.-4 c.. q,. c,. ]

lection as required by

. q,t I'- N o,a ec^d sem(AC t.oroi.., n 5 - 5de tic,,,. Joe,... dus t loading bu t a t least

< to s.cc i, ( p.cm,}

once per 7 days.

Particulate sampler.

c Londi i n - Co,xl....,,,;.c.,

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n..Jw.T.(enina isotopic fitse<4..(t.9,,.')

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s Co., lad L c.ndi,, ri.4 - t.id L; xwl 23,<.it,t, analysis on each sample.

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2 n)--a.

. m.

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C

=

..s.. '. s enc. c.5,-.e2

., O a

-.J d.

e.

c

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o m

e J JA

"".s

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8 8

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at g g o;

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=

i=

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- a,,g.

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c 9 '.'

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mi

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=

g 6,

U T

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w e

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@ @.,1 Wg Qg 4

g, -

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.==

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'L

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=

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@ =

\\

~

.=

C S I

)'*=

m 5

K-v m

m

=

Q U C

=

i

.o=

0 6.J L

g x"*

(

r b b f:

Op o

= O

=

m *N r3 jL

=

OO c.'=

U l *=:

..J x et La A

.[

e C'JR.$~3 4 1

~

./ f..i t. ::

H-4

~.-

m

1 9

... w i

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E.

4

... /

y-

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'w.,

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\\

w F.qk k %> <2 Figure 3.12-1

'4 Radiological Envircr. mental Monitoring Sample Locations (Except for those locations subject to change based on unusual census results.)

3/4 12-6

-PiR-STS-1 e

..---aw

h

)

y t r n d.

e 0

mg 5

ik 1

d/

e1 SC p

(

h)ct nI ew u$ g, 9e g

LY k

0 0

/

6 8 oT i

mY cC

$. (p a) 0 S

t L

(

)

1 N

k/

8 O

l i 1

I iC T

Hp 5,

5 1

C

(

1 1

E T

LU F

)

0 O

t e

5 S

w 1

, T i g 0

I lsk 0

0 0

0 3

M

/

3 6

1 1

I i

L Fi 1

2 1

2 2

c 1

R p

E

(

l 1

l O

C L

tn C

e A-i t

l T

T a

l R

u O

c F

i

)

2 2

t 3 r*,

0 d S

a 1

I f

E P

U x

x L

e A

n

{

6, 7

V

. r M

)

5 l

U r

H i

A

]

X AH 8

)

1, rl I'

C e/

f 0 5

0 5

f 5 5 tf 0

1 3

1 5

1 1

4 aC 0

1 1

p 2

1

(

a s

t s

i e

C a s

i 0

i 3

t 7

L y

C H

l s

0 a

1, a

s n

6, n

r H

n o

g 7

i Z

1 4 0 A

r g

4 9

0 5

3 3 4 a.

l' g

3 S

5 5

6 1

1 1

's

!s Py l,!

,7.

,,,s l

l l

t i

ij i

j

TABLE 4.12-1 (Continued)

TABLE NOTATION The LLD is the' smallest concentration df radioactive material a

in a sample that will be detected with 951 probability with 55 1

probability of falsely concluding that a blank observation represents a "real" signal.

.jb' For a particular measurement system (which may include radio-

.d chemical separation):

i 4.66 s LLD =

b E

V 2.22. Y expt-Mt) where LLD is the lower limit of detection as defined above (as pCi r

per unit mass or voltsie)

N..$i s is the standard deviation of the background counting rate b

or of the counting rate of a blank sample as appropriate (as 2',

counts per minute)

E is the counting efficiency (as counts per transformation) l - "?-

V is the sample size (in units of mass or volume) 2.22 is the number of transfomation per minuta per picoeurie, 1

[ ;.e Y is the fractional radiochemical yield (when applicable) l Ais the radioactive decay constant for the particular

~N.

radionuclide "4

A:is the elapsed time between sample collection (or end of the samp1'e-collection period) and time of counting

~ '

used in the calculation of the LLD for a detec-The value of sill be based on the actual cbserved variance of tion system sh l

blank samples (as appropriate) rather than on an unverified

~

the background counting rate or of the counting rate of the theoretically predicted variance. In calculating the LLD for a radionuclide detemined by gamma-ray spectrometry, the back-l ground shall include the typical contributions of other radio-l nuclides nomally present in the samples (e.g., potassium-40 in g

milk sampi es).

P l

PWR-STS-1 3/4 12-8 l-l

,. ~ _ _

'i.

~~

. _ -. _, ~

S i

t IAELE 4.12-1 (Ccn?Invec}

~

TAELE t:OTATION t

Analyses snell ce perfer ed LLCs will De ecalevec under ecutine con:in such a manner 4

Ittens.

backgrcund fluctua?!cns, unavelcably s=all sample sizes, inoOccasionally i

presence cf Interferring nuclices, er einer uncentro!!able cir-cuestances may rencer inese LLDs uncenlevaDie, in sucn cases, The cent.-Ibuting fec?ces W[tI ce [centiflec and described in the Annual Rac!clegical Envircneental 0;cra?!ng Recce?.

D LLO fcr ce!nk!ng.ater.

Q,.

L Ca$dablI$lcl/::r..b :a C.K.?/ &llp{&

4

/

7 k h d $fI o u G4 h <;-6~~h f m jap, 4U$

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(

fw yuw Lc.w.lc<rdwlamstus auf wJGut~~(2 jn&wA$)hiv!Z^H/

f.

NA c.5%d.I?!) 5C

!:M SI W

.E d.hfuo'sn il 0 NA 3.!4tvs Go-ik)cb kh AtEac,-

hrA/;kt ljYl.b!54)

?

r

, ~l5l 1./A A UA)' 20A /t fh,.

'u i

BWR-STS-1 3g 12 3

-A%9

9 RADIOLOGICAL ENV!RC.N." ENTAL NT ITCRING 3/a.12.2 LAND USE CENSUS LIMITING CCNDIT!CN FCR CPERATICN

?

3.12.2 A land use census small be conducted and shall Identify the tcca-tien of the nearest milk animal anc the nearest resitence Ir. eecn of the j

16 metecreicgical sectces within a distance'cf"five" miles.

Becac leaf vegetation sa pling shall te :erformec at the s! e beundary in the Irection sectcr with the hignest O/Q In lieu cf the garden census t,

A::L I CA3 ! L I TY : At al l times.

i ACTICN:

I a.

With a land use census identifying a lccaticn(s7 -1Ich yleics f

a calculatec dose ce ccse commit =ent greater than the values

(

currently being calculated in 53ecificatien 4.11.2.3.1, pre-pare and sutmit to the Cccelssicn witnin 30 cays, cursuant to Specificatica 6.9.2, a Scecial Repcet ahich identitles tne new iccation(s),

b.

With a land use census ident!!ying a Iccation(s) wnich yleles a calculated cosa ce ccse commitment (v!a ine same ex:csure pathway) greater than at a Icce*len fecm.hich secoles are currently being cotainec in acccedance.Ith Scecificatica 3.12.1, prepare and su mit to tne Commissien,I nin 30 cays, cursuant te Saeci ficatien 5.9.2, a Scecial c :cet anich identifies tne ne.

e Iccation. The new iccarlen Shall be accec#

=ciclecical

~ -*

environmen*almeni*cringOrcgramw!*hin30c$(aN# sam 51Iri

!ccatien having ine icwes calculated ccse er cose cce I? ment (via ine same ex;csure ca tency) may be deleted fecm this meni-tering pregram after (Cerccer 3!) cf the year in.nien inis N.

lanc use census was cceducted.

he previsiens of Specificatiens 3.0.3 anc 3.0.4 c.

are no-acclica0le.

SURVEILLANCE RECulREVEN S a.12.2.1 The land use cersus shall te conducted at leas cuida pKA /2.

-- t hry meafndS bet.een the cates of <fJune 1 anc Ceteter if, :y cecc-te-:ccc survey, aerial survey, ce by consulting Iccal agriculture aut crities.

4.12.2.2 Re:cets - The results c! ine lanc use census snall te inciuce:

In the Annual ;a:Iciegical Enviren. ental C:erating Me:ce.

hM MM

..!.s - 3. 2 - ;

3/

4- 0 mme

0 RADIOLOGICAL ENVIR0!:MEllTAL MONITCRING 3/4.12.3 INTERLABORATORY COMPARISON PROGRAM i

~'

LIMITING CONDITION FOR OPERATION 3.12.3 Analyses shall be perfomed on radioactf8e materials supplied as part of an Interlaboraboratory Comparison Program which has been approved

. -- : e by NRC.

APPLICABILITY:

At all times.

ACTION:

i a.

With analyses not oeing perfomed as recuired above, report the corrective actions taken to prevent a recurrence to, the Commission in the Annual Radiological Enviromen al Operating Report.

(,,

b.

The provisions of Specification 3.0.3 and 3.0.4 are not~

/

applicable.

SURVEILLANCE REQUIREhENTS drAk 4.12 M i'e nf analyses perfomed as part of the above required Interlaboratory Comparison Progh..up 5-included in the Annual Radio-logical Enviremental Operating Report pursuant to SpecificaQ e:..

~.

w i

i PWR-STS-1 3/4 12-11

f Figure 3.12-1 (Later) f J

O m

4-.

3/4 12-13 i

L-

^

l INSTRUMENTATION BASES i

3/4.3.3.8 RADIOACTIVE LIOUID EFFLUENT INSTRUMENfATION The radioactive liquid effluent instrumentation is provided to monitor and control, as applicable, the releases of radioactive materials in licuid effluents during actual or potential releases. The alarm / trip

^'

setpoints for these instruments shall be calculated in accordance with NRC approved methods in the 00CM to ensure that the alarm / trip will occur prior to exceeding the limits of 10 CFR Part 20. The OPERABILITY and use of -this instrumentation is consistent with the requirements i of General Design Criteria 60, 63 and 64 of Appendix A to 10 CFR Part 50.

3/4.3.3.9 RADIOACTIVE GASECUS EFFLUENT INSTRUMENTATION The radioactive gaseous effluent instrumentation is provided to

"/

' 's

! monitor and control, as applicable, the releases of radioactive materials in gaseous effluents during actual or potential releases. The" alarm / trip

'setpoints for these instruments shall be calculated in accordance with NRC approved methods in the ODCM to ensure that the alarm / trip will occur. prior to exceeding the limit; of 10 CFR Part 20. This instrumen-tation also includes provisions for monitoring (and controlling) the concentrations of potentially explosive gas mixtures in the waste gas holdup system. The OPERABILITY and use of this instrumentation is con-sistant with the requirements of General Design Criteria 60, 63 and 64 oof Appendix A to 10 CFR Part 50.

g.~

L.

1. : s s

se e

O t

A i

i

)

{;PWR-STS-1 B 3/4 3 4

,_,m

_.w-.--. -

,-1.

3/4.11 RADIOACTIVE EFFLUENTS

, BASES j 3 /4.11.1 LIOUID EFFLUENTS h

i

! 3/4.11.1.1 CONCENTRATION L

U This specification is provided to ensure that the concentration of l. m.~

jradioactive materials released in liquid waste effluents from the site to

' 4 +n~

', in 10 CFR Part 20, Appendix B, Table II. This limitation provides addi-

~

lunrestricted areas wC be less than the concentration levels specified E tional assurance that the levels of radioactive materials in bodies of Jwater outside the site will not result in exposures within (1) the U ectfon II. A design objectives of Appendix I,10 CFR Part 50, to an S

gj individual and (2) the limits of 10 CFR Part 20.106(e) to the population.

"The concentration limit for noble, gases is based upon the assumption that P 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 Ccmmission on Radiological Protection (ICRP)

, Publication 2.

3/4.11.1.2 OOSE i

This specification is provided to imp 1 ment the requirements "of

>} Sections II.A, III.A and IV. A of Appendix I,10 CFR Part 50. The

Limiting Condition for Operation implements the guides set forth in

Section II.A of Appendix I.

The ACTION statements provide the recuired

operating flexibility and at the same time implement the guides set

.forth in Section IV.A of Appendix I to assure that the releases of

radioactive material in liquid effluents will be kept "as low as is

reasonably achievable". Also, for fresh water sites with drinking wa*ar jlsupplies which can be potentially affected by plant operations, there is

1. reasonable assurance that the operation of the facility will not result Lin radionuclide concentrations in the finished drinking water that are

[in excess of the requirements of 40 CFR 141. The dose calculations in i;the 00CM implement the recuirements in Section III.A of Appendix I l'that confomance with the guides of Appendix I is to be shown by cal-

.;culational procedures b& sed on models and data such that the actual

% exposure of an individual through appropriate pathways is unlikely pto be substantially underestimated. The equations specified in the

,00CM for calculatino the doses due to the actual release rates of

[ll methodology provided in Regulatory Guide 1.109, " Ca radioactive materiais in if quid effluents will be consistent with the j Doses to Man from Routine Releases of Reactor Effluents for the Purpose iof Evaluating Compliance with 10 CFR Part 50, Aopendix I," Revision 11, October 1977, and Regul atory Guide 1.113, " Estimating Acuatic Di s-persion of Effluents fran Accidental and Routine Reactor Releases for g

the Purpose of Implementing Appendix I," April 1977. HUREG-0133 provides methods for dose calculations consistent with Regulatory Guides 1.109 and 1.113.

li

',' PWR -S TS-1 B 3/4 11-1 s

. s.;

F RADICACTIVE EFFLUENTS BASES This specificatten~appiles to the release d1 liculd effluents from each reacter at the site.

.cr un't;

h:r:d due:t: * ::r ;r*

I eox e. m.

7:--:, *': 't;;!d 244!;:---

4---

+%: th-- e :y: - : : p ee-+! -e

.T;r- *h: ur. ' t: :h:-'r; 'h:t :f:':=.

3/4.11.1.3 LlCUlO WASTE TREATMENT I

I The CPERABILITY of the liquid radwaste treatment system ensures that this system will be available fer use whenever liquid effluents recuire treatment price to release to the environment. The requirements that the appecorlate portions of this system be used when specified prevides assur-ance that the releases of radicactive materials In liquid effluents will be kept "as low as is reasenably achieveole." This specification,Imple-ments the requirements of 10 CFR Part 50.36a, General Design Criterien 60

/

of Appendix A to 10 CFR Part 50 and design coJective Section li.0,cf Appendix A to 10 CFR Part 50.

h :;;;!'!:d '*: gover 'n; *h: ;:: Of

r

;rt: ?: ;e-*! n: ef 'he '!pu!d

?d-es*e **ee*==a* sys*== c=-a er=rf

:c :: : :;!?:b!: ' ctica of 'r.: ;;!d: ::t fcith in Sectica l:.A ef a;p ndix i, 10 OF" Part !O, fer '! quid ef'!;;rt:.

.-C fS l

3/4.11.2 GASECUS EFFLUENTS 3/4.11.2.1 COSE RATE This specificatiqn is previded to ensur'e that the dose rate at any-time at the exclusien area beundary from gasecus effluents from all units en the site will be within the annual dese limits of 10 CFR Part 20 for unrestricted areas. The annual dese limits are the deses associated with the cencontrations of 10 CFR Part 20, Aapendix S, Tac le 11.

These limits previce reasonable assurance that radicective materisi discharged in gasecus effluents will not result in the exposure cf an Individual in an unrestricted area, either within er cutsica the exclusten area beundary, to annual average cencentrations exceeding the limits soecified in Appendix S, Table 11 of 10 CFR Part 20 (10 CFR Part 20.106(D)). For Incividuals who may at times be within the exclusten area bcundary, the cccunancy of the incividual will be sufficiently Icw to ec=pensate for FWR-STS-1 E-3/4 11-2

. o RADI0 ACTIVE EFFLUENTS i

BASES any increase in the atmospheric diffusion factor (above that for the ex-clusion area boundary. The specified release rate limits restrict, at all times, the corresponding ganna and beta dose rates above background to an individual at or beyond the exclusion area boundary to j (500) i mre/ year to the total body or to I (3000) mesm/ year to the skin. These release rate limits also restrict, at all times, the corresponding thyroid 5C dose rate above background to an infant via the cow-milk-infant pathway to j 1500 are/ year for the nearest cow to the plant.

This specification applies to the release of gaseous effluents from all reactors at the site. For units with shared radwaste treatment systes, the gaseous effluents from the shared system are proportioned among the units sharing that system.

l3/4.11.2.2 00SE, NOBLE GASES

/

This specification is provided to impleent the requirments of Sections II.B. III.A and IV.A of Appendix I,10 CFR Part 50. The Limiting Condition for Operation implements the guides set forth in Section II.S of Aopendix I.

The ACTION statements provide the recuired operating flexibility and at the same time impleent the guides set

!forth in Section IV.A of Aopendix I assure that the releases of radio-active material in gaseous effluents will be kept "as low as is reasonably achi evabl e."

The Surveillance Requirments implement the requirenen*a in Section III. A of Appendix I' that confor-s with the guides of Aopendix 1 to be shown by calculational procedures based on models and data such that the actual exposure of an in.fividual through the ap;ropriate path-ways is unlikely to be substantiaily underestimated. Tne dose calcula-

'tions established in the CDCM for calculating the doses due to the actual release rates of radioactive acble gases in gaseous effluents will be consistent with the methodology proviced in Regulatory Guide 1.109, s

" Calculation of Annual Doses to Man fra Routine Releases of Reactor

' Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I," Revision 1, October 1977 and Regulatory Guide 1.111 " Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases fran Light-Water-Cooled Reactors," Revision 1, July 1977. The ODCM ecuations provided for determining the air doses at the exclusion area boundary will be based uoon the historical average atmos-pheric conditions. NtREG-0133 provides methods for dose calculations consistent with Regulatory Guides 1.109 anc 1.111.

"3/4.11.2.3 00SE. RADIO!0DIHES. RADI0 ACTIVE MATERIAL IN PARTICULATE FORM AND RADIONUCLIDES OTHER TMAN NOBLE GASE5 This specification is provided to impleent the recuirments of Sections II.C, III. A and IV.A of Acrendix I,10 CFR Part 50. Tne Limiting PWR-STS-1 3-3/4 11-3 i1 1

s, O

RADIOACTIVE EFFLUENTS BASES j

hConditions for Operation are the guides set forth in Section II.C of Appendix 1.

The ACTION statements provide the recuired operating flexi-

, bility and at the same time implement the guides set forth in Section i

!!Y.A of Appendix I to assure that the releases of radioactive materials in gaseous effluents will be kept "as low as is reasonably achievable."

l rThe 00CM calculational methods specified in the surveillance requirements dimplement the reouirements in Section III. A of Appendix I that confom-

...a

'. ~

[j ance with the guides of Appendix I be shown by calculational procedures j

Obased on models and data such that the actual exposure of an individual i

! through appropriate pathways is unlikely to be substantially under-i estimated. The ODCM calculational methods approved by NRC for calculating h the doses due to the actual release rates of the subject material.s

,are required to be consistent with the methodology provided in Regulatory a

'. Guide 1.109, " Calculating of An.nual Doses to Man from Routine Releases iof Reactor Ef"luents for the Purpose of Evaluating Compliance with "10 CFR Part 50, Appendix I," Revision I, October 1977 and Regulatory 7

j Guide 1.111. " Methods for Estimating Atmospheric Transport and Dispersion

,of Gaseous Effluents in Routine Releases from Light-Water-Cooled Reactors,"

!" Revision 1, July 1977. These equations also provide for detennining j!The release rate specifications for radiciodines, radioactive material the actual ~ doses based upon the historical average atnospheric conditions.

d; in particulate fann and radionuclides other than noble gases are dependent -l jon the existing radionuclide pathways to man, in the unrestricted area.

!The h

i

.!are: pat ways wh ch are examined in the development of tnese calculations

1) individual inhalation of airborne radionuclides, 2) deposition iof radionuclides onto green leafy vegetation with subsequent consumption

by man, 3) deposition onto grassy areas where milk animals and meat j!and 4) deposition on the ground with subsequent exposure of man. producing animals gr j

1 1 h3 /4.11.2.4 GASEOUS WASTE TREATPENT

!)The OPERASILITY of the gaseous radwaste treament system and the ventila-Jtion exhaust treatnent systems ensures that the systems will be availacle a{for use whenever gaseo'Us effluents require treatnent prior to release

. the environnent. The requirement that the appropriate portions of these

,jsystems be used when specified provides reasonable assurance that the

releases of radioactive materials in gaseous effluents will be kept "as ilow as is reasonaoly achievable." This specification implements the drequirenents of 10 CFR Part 50.36a, General Design Criterion 60 of Appen-

~ !

dix A to 10 CFR Part 50, and design objective Section IID of Appendix I ito 10 CFR Part 50.

";c ;;;ecified if-f t: g verMrg the u:0Of:gr- "

ip;rtion: O f the-sys-tems-were-spec 4fied-as-a-sui t21 : fracti;r :f th:

jguide ::t f0rth i-5 : tion: ::.S cad ::.C cf Appendix I,10 C.~7 Part 50, it f;c succus ef'ha ns.

PWR-STS-1 B 3/4 11 4 4

i

RADI0 ACTIVE EFFLUENTS BASES 3/4.11.2.5 00SE

~

This specification is provided to meet the reporting requirements of 40 CFR 190.

3/4.11.2.6 EXPLOSIVE GAS MIXTURE This specification is provided to ensure that the concentration of potentially explosive gas mixtures contained in the waste gas treat-cnt system is maintained below the flammability ifmits of hydrogen and oxygen. ( Automatic control features are included in the system to prevent the hydrogen and oxygen concentrations from reaching these flammability limits. These automatic control features include isolation of the source of hydrogen and/or oxygen, automatic divers 1on to re-canbiners, or injection of dilutants to reduce the concentration below the flammability limits.) Maintaining the concentration of hydrogen

, and oxygen below their flamability limits provides assurance that the releases of radioactive materials will be controlled in confonnance lwith the requirements of General Design Criteriorr 60 of Appendix A

]to10CFRPart50.

3/.4.11.2.7 GAS STORAGE TAHKS Restricting the quantity of radioactivity contained in each gas

+

storage tank provides assurance that in the event of an uncont elled release of the tanks contents, the resulting total body exposure to an individual at the nearest exclusion area boundary will not exceed

!0.5 ren. This is consistent with Standard Review Plan 15.7.1, " Waste

,Cas System Failurt."

l PWR-STS-1 3 3/4 11-5 l

1.

c p

J,

'e 3/4.12 RADICLCGICAL ENVIRONMENTAL '.CNITORING EASES 3/4.12.1 MCNITCRING FROGRAM The radiclogical monitoring pecgram required by this specification pro-vides measurements of radiation and of radicactive materials in these exposure pathways and for those radienuclides which lead to the hignest potential radiation expsures of Individuals resulting from the station cperation. This monitoring program thereby supplements the radiological ef fluent monitoring program by verifying that the measuracle concentra-tiens of radicactive materials and levels of radiation are not nigner inan expected en the casts of the ef fluent measurements and meceling of the environmental exoosure patnways. The InI?lally s;ecified menticring program will be ef fective for at least tne first inree years of commercial coeration. Folicwing inis period, pecgram enanges may be initiated based on cperational experience.

e

/

The cetection capa:llities recuired by Table 4.12.-l are state-of-the-art for ecutine envircnmental measurements in Incustrial laboratories.

The specified Icwer limits of cetection correscend to I?% %maf.-10CFRc0, App d I

. cesign cbjective <csa-ecuivalent of 15 meem/ year for armespheric releases and 10 mesm/ year for Ilcuid releases ?: ine ecst sensitive crgan and incividual 3 based on the assumptlens given In Regulatory Gulce 1.109, " Calculation of Annual Ocses to Man fecm Rcutine Releases of Reactor Effluents for tse Pur:cse of Evalua?Inc Ccepilance witn 10 CFR Part 50, Appendix 1," ^Oc oQrt, P, q.

a s

3/a.12.2 LAND USE CENSUS 4

This scecifica?!cn Is pecvidec to ensure inat changes in the use of unrestricted areas are Icentified anc inat medlfications ? the monitoring pecgram are made if required by the results of inis census.

I This census sa?Isfies tne reculcements of Section IV.S.3 of Accendix I to 10 CFR Part 50.

t gg 373,7

. _... g 3g g

.m

sa.,n t

,(2 i

RADIOLCGICAL E!!VIRCP:?' ENTAL,YOt:1 ?CR i t:G SASES 3/.1.t2.3 E u % q\\a hoprA nro r.pgkna re.,3e....

n The recuirement for participatien in w b 4 c A egofeng co,,gn g fp. m is previded ic ensure inat independent checks en the precisicn an'c accuracy of the measurements of racicac?!ve caterla; in envircnnmental sample matrices are performec as part cf a cuality assurance pecgram for env!renmental monitoring in ceder tc cemenstrate that the results are reasenacly valle, i

e t

I i

l f

i I

SiiE-375-1

, 3g, -2

-

ML20064H850

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