ML20045G842

Proposed Tech Specs Supporting Change in Frequency for Submittal of Radioactive Effluent Release Repts from Semiannual to Annual & Extension of Preparation Period from 60 Days to 90 Days

ML20045G842
Person / Time
Site:	River Bend
Issue date:	07/02/1993
From:	GULF STATES UTILITIES CO.
To:
Shared Package
ML20045G839	List: ML20045G842 RBG-30706, Application for Amend to License NPF-47,revising TS to Change Frequency for Submittal of Radioactive Effluent Release Repts from Semiannual to Annual & to Extend Preparation Period from 60 Days to 90 Days
References
NUDOCS 9307160054
Download: ML20045G842 (26)

Text

i ATTACIIMENT 3 i

REVISED TECHNICAL SPECIFICATIONS t

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INSTRUMENTATION RADI0 ACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION LIMITING CONDITION FOR OPERATION

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3.3.7.10 The radioactive liquid effluent monitoring instrumentation channels j

shown in Table 3.3.7.10-1 shall be OPERABLE with their alarm / trip setpoints set to ensure that the limits of Specification 3.11.1.1 are not exceeded.

The alarm / trip setpoints of these channels shall be determined and adjusted in j

accordance with the methodology and parameters in the OFFSITE DOSE CALCULATION MANUAL (00CM).

APPLICABILITY:

At all times.

i ACTION:

I With a radioactive liquid effluent monitoring instrumentation channel a.

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.

Wit

@ ^an b.

mo itorihg ins % e p in % m number of radioactive liquid effluent trMentatior channels OPERABLE, take the ACTION shown i

in Table 3.3.7 10-1.

Res ore the inoperable instrumentation to OPERABLE statu within t time soecified in ACTION or explain in the next Seedj nual Ra oactive Effluent Release Report why this inoperability was not c rrected within the time specified.

The provisions of Specific ion 3.0.4 are not applicable.

' ions of Spe ification 3.0.3 are not applicable.

c.

SURVEILLANCE REQUIREMENTS 4.3.7.10 Each radioactive liquid effluent monitoring instrumentation channel-shall be demonstrated OPERABLE by performance of the CHANNEL CHECK, SOURCE CHECK, CHANNEL CALIBRATION and CHANNEL FUNCTIONAL TEST operations at the frequencies shown in Table 4.3.7.10-1.

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RIVER BEND - UNIT 1 3/4 3-94 Amendment No. 47

4 INSTRUMENTATION RADI0 ACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.7.11 The radioactive gaseous effluent monitoring instrumentation channels shown in Table 3.3.7.11-1 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 and adjusted in accordance with the methodology and parameters in the ODCM.

APPLICABILITY:

As shown in Table 3.3.7.11-1.

ACTION:

With a radioactive gaseous effluent monitoring instrumentation channel a.

alarm / trip

• setpoint less conservative than required by the above Specification, immediately suspend the release of radioactive gaseous ef fluents monitored by the affected channel, or declare the channel inoperable, With less tpdn th(minimum number of radioactive gaseous ef fluent b.

arrartnpinstruw-ion nnels OPERABLE, take the ACTION shown in Table 3.3.7.11-1.

Restore he inoperable instrumentation to OPERABLEstatuswjthinthetim specified in the ACTION or explain in the next Ge=4ennual Radioac ive Effluent Release Report why this inoperability was not correct within the time specified.

The provisions of Specificathin 3'.0.4 are not applicable.

TheprovisionsofSpecifigation3.0.3arenotapplicable.

c.

SUREVEILLQCEREQUI TS 4.3.7.11 Each radioactive gaseous effluent monitoring instrumentation channel shall be demonstrated OPERABLE by performance of the CHANNEL CHECK, SOURCE CHECK, CHANNEL CALIBRATION and CHANNEL FUNCTIONAL TEST operations at the frequencies i

shown in Table 4.3.7.11-1.

• The alarm / trip setpoints for the Explosive Gas Mixture in the Main Condenser Offgas Treatment System are set in accordance with Specification 3.11.2.6.

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RIVER BEND - UNIT 1 3/4 3-99 Amendment No. 47

4 TABLE 4.11 1.1.1-1 3ADI0 ACTIVE LIQUID WASTE SAFPLING AND AN Minimum Lower Limit Liquid Release Sampling Analysis Type of Activity of Deteegion Type Frequency Frequency Analysis (LLD)

A.

Batch Waste (pCi/ml)

P Release P

PrincipajGamma 5x10 7 Each Batch Each Batch (Liquid Emitters ; except Radwaste for Ce-144 5x10 5 Recovery Sample I-131 b)

P 1x10 S

"" 8 M

One Batch /M Dissolved and 1x10 8 Entrained Gases (Gamma Emitters)

P M

H-3 Each Batch Composited 1x10 5 Gross Alpha 1x10 7 P

Q Sr-89, S r-90 Each Batch Composite d 5x10.s Fe-55 1x10 5 TABLE NOTATION The LLD is defined, a-concentration of radioactive material in a sample that w above system background, 5% probability of falsely concluding that a blank observation

count, "real" signal.

esents a For a particular measurement system, which may include radiochemi cal separation:

4.56s O"

b E

V 2.22 x los. y. exp (.x3g)

Whe re:

LLD is the "a priori" lower limit of detection as defined above picrocuries per unit mass or volume,

, as i

FyI

- N o e nM6,E RIVER BEND - UNIT 1 3/4 11-2

v 9j TABLE 4.11.1.1.1-1 (continued) 1 TABLE NOTATION (continued) is the standard deviation of the background counting rate or of the sh counting rate of a blank sample, as appropriate, as counts per minute E is the counting efficiency, as counts per disintegration, V is the sample size in units of mass or volume, 2.22 x 10e is the number of disintegrations per minute per microcurie, Y is the fractional radicchemical yield, when applicable, A is the radioactive decay constant for the particular radionuclide, and at for plant effluents is the elapsed time between the midpoint of sample collection and the time of counting.

Typical values of E, V, Y, and at should be used in the calculation.

It should be recognized that the LLD is defined as an a priori (before the fact) limit representing the capability of a measurement system and not as an a posteriori (after the fact) limit for a particular measurement.

b-A batch release is the discharge of liquid wastes of_a discrete volume.

Prior to sampling for analyses, each batch shall be isolated, and then thoroughly mixed to assure representative sampling.

c-The principal gammaA mT Eer for wh ch the L specification applies exclu-sively are the fo Towing radionuclides: Mn-

, Fe-59, Co-50, Co-60, 2n-65, Mo-99, Cs-134, Cs 137, Ce-141, and Ce-144.

This ist does not mean that only these nuclid are to be considered.

Other maa peaks that are identifiable, gather with those of the above nu lides, shall also be analyzed and eported in the Semilhnual Radioacti e Effluent Release Report pursuant to S ecification 6.9.1.8.

d-A composite s le is one in which the quan ity of liquid sampled is propor-tional to the qu y of liquid ste di harged and in which the method of sampling employ d results in s

men that is representative of the liquids g ased.

RIVER BEND - UNIT 1 3/4 11-3

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RADI0 ACTIVE EFFLUENTS LIQUID HOLDUP TANKS LIMITING CONDITION FOR OPERATION 3.11.1.4 outdoor tank shall be limited to less than or eThe quantity of tritium and dissolved or entrained noble gases. qual to 10 curies, excluding e

APPLICABILITY: At all times.

ACTION:

With the quantity of radioactive mat a.

unprotected outdoor tanks exceedin any of the a ve the above limit, immed 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; and dsuspend all additions of ely the events leading to this condit'on in the next W' nual R di escribe active Effluent Release Report.

a o-n b.

The provisions of Specifications 3 0.3 and 3.0.4 are not applicabl e.

-SURVEILLANCE REQUIREMENTS N

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1 4.11.1.4 The quantity of radioactive material contained in each of the a unprotected outdoor tanks shall be determined to be within the abov analyzing a representative sample of the tank's contents at'leas ve 7 days when radioactive materials are being added to the tank m

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RIVER BEND - UNIT 1 3/4 11-6

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TABLE 4.11.2.1.2-1 RAD 10ACIIVE GASEOUS WASTE SAMPLING AND ANALYSIS PROGRAM y

m Minimum Sampling Analysis Type of Lower Limit of Gaseous Release Type Frequency frequency Activity Analysis Detection (LtD)*

c' Main Plant c

A (pCi/ml)

H H

Principal Ganwna Emittersb Exhaust Duct Grab Sample H

1x10 4 w

H-3 1x10 6 B.

Fuel Building Md Principal Gamma Emittersb Ventilation Grab Sample H

lx10 4 Exhaust Duct H-3 1x10 6 C.

Radwaste Building H

Ventilation Grab Sample H

Principal Gamma Emitters lx10 i g

Exhaust Duct y

D.

All Release Types Continuous" I

W 1-131 co as listed in A, B, C above.

Charcoal lx10 i2 Sample I-133 1x10 8"

Continuous

• I W

Principal Gama Emitters 1x10 8"

Particulate (I-131, Others)

Sample Continuous" M

Gross Alpha Composite lx10 8"

Particulate Sample FyE Continueus" o

SR-89. SR-90 Composite 1 io -

Nd b C-S ny e Continuous" Noble Gas Noble Gases Honitor 1x10 6 Gross Beta or Gamma t

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IABLE A. 11.2.1.2-1 (Continued)

TABLE NOTATION The LLD is defined, for purposes of these specifications, as the sm a-concentration of radioactive material in a sample that will yield a net with only 5% probability of falsely concluding tha represents a "real" signal.

For a particular measurement system, which may include radiochem separation:

4.66 s b E

V 2.22 x 108 + Y exp (-AAt)

Where:

microcuries per unit mass or volume,LLD is the "a prior v

is the standard deviation of the background counting rate o s g tne counting rate of a blank sample as appropriate, as counts per r of

minute, E is the counting efficiency, as counts per disintegration, V is the sample size, in units of mass or volume, 2.22 x 105 is the number of disintegrations per minute per mi crocurie, Y is the fractional radiochemical yield, when applicable, A is the radioactive decay constant for the particular radionuclide and at for plant effluents is the elapsed time between the midpoint of sample collection and time of counting.

Typical values of E, V, Y, and at should be used in the calculation.

It should be recognized that the LLD is defined as a oriori (before the fact) limit representing the capability of a measurement system and not as an a posteriori (after the fact) limit for a particular measurement.

I A n-FJo C mME RIVER BEND - UNIT 1 3/4 11-9

1 TABLE 4.11.2.1.2-1 (Continued)

TABLE NOTATION b-exclusively are the following radionuclides:The principal gamm Xe-135, and Xe-138 for gaseous emissions and Mn-54, Fe-52Kr-87, Kr-88, X 13 Xe-133m, Zn-65, Mo-99, Cs-134, Cs-137, Ce-141 and Ce-144 for p6 tic 2

58, Cb Other gamma peaks that are identifiable, toThis list does not m ate emissi nuclides, shall also be analyzed and report Ther with th eoftheabove]

Effluent Release Report pursuant to Specific in the nual Radioac.tive on 6.9.1.8.

Sampling and analysis shall also be performe c-shutdown, startup, or a THERMAL POWER change exwithin o e hour followi THERMAL POWER, unless (1) analysis shows that the DOSE E5 percent of JATE ettthg of 3 and (2) the condenser offgas noble gas activity m LVAl FNT M31 offgas activity has not increased by more than a factor of 3 d-Tritium grab samples shall be taken at least once in the spent fuel pool. ventilation exhaust from the spent fuel pool area,per 7 d whenever spent fuel is The ratio of the sample flow rate to the sampled stream floy rate shall b e-known for the time period covered by each dose or dose rate calc l ti e

made in accordance with Specifications ua on 3.11.2.1, 3.11.2 2 and 3 11 2 3 f-completed within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> after changing or after re e

Sampling shall also be performed at least once.per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> for the mai plant exhaust for at least 7 days following each shutdown n

hour, and analyses shall be completed within 48 ho

, startup or n one samples collected for 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> are analyzed, the corresponding LLDs ma

. When increased by a factor of 10.

lysis shows that the DOSE EQUIVALENT I-131 concentration i coolant has not increased more than a factor of 3; and (2) the condenser offgas noble gas monitor shows that offgas activity has not increased more than a factor of 3.

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RIVER BEND - UNIT 1 l

3/4 11-10

I 3/4.12 RADIOLOGICAL ENVIRONMENTAL MONITORING 3/4.12.1 MONITORING PROGRAM LIMITING CONDITION FOR OPERATION 3.12.1 The radiological environmental monitoring program shall be conducted as specified in Table 3.12.1-1.

APPLICABILITY:

At all times.

ACTION:

With the radiological environmental monitoring program not being a.

conducted as specified in Table 3.12.1-1, prepare and submit to the Commission, in the Annual Radiological Environmental Operating Report required by Specification 6.9.1.7, a description of the reasons for not conducting the program as required and the plans for preventing a recurrence.

b.

With the level of radioactivity, as the result of plant effluents, in an environmental sampling medium at a specified location exceeding the reporting levels of Table 3.12.1-2 when averaged over any calendar quarter, prepare and submit to the Commission within 30 days, pursuant to Specification 6.9.2, a Special Report that identifies the cause(s) for exceeding the limit (s) and defines the corrective actions to be taken to redure radioactive effluents so that the potential annual dose

• to A MEMBER OF THE PUBLIC is less than the calendar year limits of.

Specifications 3.11.1.2, 3.11.2.2, and 3.11.2.3.

When more than one of the radionuclides in Table 3.12.1-2 are detected in the sampling medium, this report shall be submitted if:

concentration (1) concentration (2)

+ * * * > 1. 0 reporting level (1) reporting level (2)

When radionuclides other than those in Table 3.12.1-2 are detected and are the result of plant effluents, this report shall be submitted if the potential annual dose

• to A MEMBER OF THE PUBLIC is equal to or greater than the calendar year limits of Specifications 3.11.1.2, 3.11.2.2 and 3.11.2.3.

This report is not required if the measured level of radioactivity was not the result of plant effluents; however, in such an event, the condition shall be reported and described in the Annual Radiological Environmental Operating Report.

c.

With milk or broad leaf vegetation samples unavailable from one or more of the sample locations required by Table 3.12.1-1, identify locations for obtaining replacement samples and add them to the radiological environmental monitoring program within 30 days.

The

• The methodology and parameters used to estimate the potential annual dose to a HEMBER OF THE PUBLIC shall be indicated in this report.

RIVER BEND - UNIT 1 3/4 12-1

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RADIOLOGICAL ENVIRONMENTAL MONITORING LIMITING CONDITION FOR OPERATION (Continued)

ACTION:

(Continued) f c fic locations from which sample e

elet d from the monitoring program.s were unavailable ma en be ide he cause of the unavailability of samples ancPursuant to S new locati (s) for obtaining replacement samples in t dentify the kphnual Radio ctive Effluent Release Report and include in the report next J r' -

a revised fi location (s) gure(s) and table for the 00CM reflecting the new i

t d.

The pro ons of Specification 3.0.3 are not applicable.

SURVEILLANCE REQUIREMENTS 4.12.1 pursuant to Table 3.12.1-1 from the specific locations figure (s) in the ODCM, and shall be analyzed pursuant to the req i e table and Table 3.12.1-1 and the detection capabilities required by Table 4 12 u rements of

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RIVER BEND - UNIT 1 3/4 12-2 Amendment No. 47 1

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TABLE 3.12.1-1 h

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

'a m

Number of Representative Exposure Pathway Samples and Sampling and Type and Frequency and/or Sample Sample Locations

• E Collection Frequency of Analysis b

Q 1.

DIRECT RADIATION 40 routine monitoring stations Quarterly Gamma dose quarterly.

either with two or more dosim-eters or with one instrument for measuring and recording dose rate continuously, placed as follows:

an inner ring of stations, one in each meteorological sector in the general area of the SITE BOUNDARY; Y

an outer ring of stations, one in g

each meteorological sector in 4

the 6.to 8-km range from the site; the balance of the stations to be placed in special interest areas such as population centers.

T nearby residences, schools, and in

}j 1 or 2 areas to serve as control y

stations.

2.

AIRBORNE g

Radiciodine and Samples from 5 locations:

Continuous sampler Radioiodine Cannister:

Particulates operation with sample I-131 analysis weekly.

q 3 samples from close to collection weekly, or the 3 SIIE DOUNDARY locations, more frequently if in different sectors, of the required by dust Particulate Sampig; iiighest calculated antiual average loading.

Gross beta radioactivity p

groundlevel D/Q.

ahalysis following

k.

TABLE 3.12.1-1 (Continued)

D RADIOLOGICAL ENVIRONMENTAL HONITORING PROGRAM u

Number of Representative Exposure Pathway Samples and Sampling and Type and frequency and/or Sample Sample tocations, c_5 Collection Frequency af Analysis fliter change;d

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1 sample from the vicinity of Gama isotopic analysis

• a comunity having the highest of composite (by calculated annual average ground level D/Q.

location) quarterly.

1 sample from a control location, as for example 15-30 km distant and in the least prevalent wind direction.

R 3.

WATERBORNE u

a.

Surface 1 sample upstream and Weekly samples com-Gamma isotopic analysis" L

1 sample downstream.

posited monthly or monthly.

Composite for quarterly.

tritium analysis quarterly.

Discharge line.

Compositesampjeover 1-month period b.

Ground Samples from 1 or 2 sources Quarterly Gama isotopic" and trittua.

only if Ilkely to be affected analysis quarterly.

c.

Sediment I sample from downstream area Semiannually Gamma isotopic analysis" from with existing or potential sera lannua l ly.

D shoreline recreational value.

D 4.

INGESTION a.

Hilk Samples from allking animals Semimonthly when Gama isotopic" and I-131 in 3 locations within 5 km animals are on analysis semimonthly when distance having the highest pasture, nionthly at animals are on pastur--

dose potential.

If there are other times monthly at other tis

U TABLE 3.12.1-1 (Continued)

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RADIOLOGICAL ENVIRONMENTAL HONITORING PROGRAM Humber of E'

Representative 5

Exposure Pathway Samples and Sampling and Type and Frequency and/or Sample Sample Locations

• Collection Frequency of Analysis E

a.

Hilk none, then I sample from milking tj (cont'd) animals in each of 3 areas S to a km distant where doses g

are calculated to be greater than 1 arem per yr.

I sample from milking animals at a control location 15-30 km distant and in the least preva-lent wind direction.

b.

Fish and 1 sample of each of three Sample in season, or Gamma isotopic analysis

• Inverte-commercially and/or recrea-semiannually if they on edible portions.

37 brates tionally important species are not seasonal.

u' in vicinity of plant dis-charge area.

t 1 sample of each of three

+

"'()

species in areas not influ-w q-enced by plant discharge.

s 9

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c.

Food Samples of 3 different kinds Monthly during Gamma isotopic" and I-131 Products of broad leaf vegetation grown the growing season.

analysis.

(wg }7, near each of two different q) locations near the site boundary of highest predicted annual Sfs average ground level D/Q if milk sampling is not performed.

C TABLE 3.12.1-1 (Continued) m M

RADIOLOGICAL ENVIRONMENTAL MONIl0 RING PROGRAM n

Humber of Representative E

Exposure Pathway Samples and and/or Sample Sample Locations

• Sampling and Collection Frequency Type and Frequency i

of Analysis c.

Continued e

5 1 sample of each of the similar broad leaf vegetation grown Monthly during the 15-30 km distant near the least growing season.

Garaa isotopic" and 1-131 analysis.

prevalent wind direction, if milk sampling is not performed.

E e

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x D) 3 Or1 e

DT h

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a TABLE 3.12.1-1 (Continued) gi TABLE NOTATION m

The 00CM shall include, in a table and figures, specific parameters of distance and direction sector from g;

a-gg the centerline of one reactor, and additional description where pertinent, for each sample location in Table 3.12.1-1.

Refer to NUREG-0133 " Preparation of Radiological Effluent Technical Specifications f r Nuclear Power Plants," October 1978, and to Radiological Assessment Branch Technical Position, Revision 1, c:

je November 1979.

Deviations are permitted'from the required sampling schedule if specimens are unobtainable due to hazardous conditions, seasonal unavailability, malfunction of automatic sampling equipment, or other

-4 legitimate reasons.

If specimens are unobtainable due to sampling equipment malfunction, every effort shall so be made to complete corrective action prior to the end of the next sampling period.

All deviations from the sampling schedule shall be documented in the Annual Radiological Environmental Operating Report pursuant to Specification 6.9.1.7.

It is recognized that, at times, it may not be possible or practic e o to obtain samples of the media of choice at the most desired location or time.

In these ins ances suitable q

alternative media and locations may be chosen for the particular pathway in question and appropri te substitu-g tions made within 30 days in the radiological environmental monitoring program.

In the xt Seo4ainual Radio-active Effluent Release Report, pursuant to Specification 6.9.1.8, identify the cause the unavailability of samples for that pathway and identify the new location (s) for obtaining replacement s,mples, and also include i

{h the report a revised figure (s) and table for the ODCH reflecting the new location (s)J

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b-One or more instruments, such as a pressurized icn chamber, for measuring and recordin ate continuou y may be used in place of, or in addition to, integrating dosimeters.

For the purposes of this

~ le, a no-

-a luminescent dosimeter (ItD) is considered to be one phosphor; two or more phosphors in a packet are onsidered as two or more dosimeters.

Film badges shall not'be used as dosimeters for measuring direct radiation.

The 40 stations is not an absolute number.

The number of direct radiation monitoring stations may be reduced according to geographical limitations; e.g...at an ocean site, some sectors will be over water so that the number of dosimeters may be reduced accordingly.

The frequency of analysis or readout for TLD systems will depend upon the characteristics of the specific system used and should be selected to obtain optimum dose information with minimal fading.

c-The purpose of this sample is to obtain background information.

If it is not practical to establish control I

locations in accordance with the distance and wind direction criteria, other sites that provide valid back-ground data may be substituted.

d-Airborne particulate sample filters shall be analyzed for Gross beta radioactivity 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or more after sampling to allow for radon and thoron daughter decay.

If gross beta activity in air particulate samples is greater than ten times the yearly mean of control samples,. gamma isotopic analysis shall be performed on the individual samples.

c TABLE 3.12.1-1 (Continued}

g; TABLE NOTATION (Continued) n Gamma isotopic analysis means the identificatinn and quantification of gamma emitting radionuclide m

e-

[l that may be attributable to the effluents from the facility.

.f-

" downstream" sample shall be taken in an area beyond but near the mixin The lE

-4 an estuary must be taken far enough upstream to be beyond the plant influence.

" Upstream" samples in w

Composite samples shall be collected at intervals which are very short (e.g g-compositing period (e.g., monthly).

., hourly) relative to the h-where the hydraulic gradient or recharge properties are suitable for contam oses in areas i -

The dose shall be calculated for the maximum organ and age group, using the methodology an the ODCM.

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i RADIOLOGICAL ENVIRONMENTAL MONITORING

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3/4.12.2 LAND USE CENSUS kTIONFOROPERATION LIMITING CO 3.12.2 A land use census shall be conducted and shall identify within a distance of 8 km (5 miles) the location, in each of the 16 meteorological sectors, of the nearest milk animal, the nearest residence and the nearest garden

• of greater than 50 m2 (500 ft2) producing broad leaf vegetation.

APPLICABILITY:

At all times.

ACTION:

a.

t th a land use census identi ying a location (s) that yields a 6alculated dose or dose commitment greater than the values currently

,/6eing calculated in Specifica ion 4.11.2.3, identify the new location (s) f in the next I

to Specification 6.9.1.8.nual Ra io ctive Effluent Release Report, pursuant i

b.

land use sus i ntifying a location (s that yields a calculated ment (via the same exposure) pathway dose do omm greater than at a location frca which samples are curre)ntly being 20 percent obtained in accordance with Specification 3.12.1, add the new loca-tion (s) to the radiological environmental monitoring program within 30 days.

The sampling bca s), excluding the control station

?

location, having th owest ca

-aloseordosecommitment(s),

3 y

g via the same expos e pathway, e det ed from this monitoring W

g program after ob 31 of the year in wh h this 1Lnd use ccqsus was conduct Pursuant to Specification 6.

1.8, identify the new d

g')

N location (s in the next GeeMhual Radioactiv 3 Effluent Release Report and include in the report a revised fiilure(s) and table e

u for the 000 reflecting the new location (s).

c.

The provision of Specification 3.0.3 ar t applicable.

SURVEILLANCE REQUIREME

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J 4.12.2 At 1 once per 12 months, the land use census shall be conducted during the season, using that information that will provide the best results, s local agriculture authorities.by a door-to-door survey or aerial survey or by consulting The results of the land use census shall be-included in the Annual Radiological Environmental Operating Report pursuant to Speciff. cation 6.9.1.7.

• In lieu of the garden census, broad leaf vegetation sampling of at least three different kinds of vegetation may be performed at the site boundary in each of two different direction sectors with the highest predicted D/Qs. Specifications for broad leaf vegetation sampling in Table 3.12.1-1, 4e shall be followed, including analysis of control samples.

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RIVER BEND - UNIT 1 3/4 12-13 Amendment No. 47

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4 i

3/A.11 RADI0 ACTIVE EFFLUENTS BASES 3/4.11.1 -LIQUID EFFLUENTS 3/4.11.1.1 CONCENTRATION This specification is provided to ensure that the concentration of radio-active materials released in liquid waste effluents to UNRESTRICTED AREAS will be less than the concentration levels specified in 10 CFR Part 20, Appendix B, 1

i Table II, Column 2.

This limitation provides additional assurance that the levels of radioactive materials in bodies of water in UNRESTRICTED AREAS will result in exposures within (1) the Section II.A design objectives of Appendix I, 10 CFR Part 50, to a MEMBER OF THE PUBLIC and (2) the limits of

{

10 CFR Part 20.106(e) to the population.

The concentration Ifmit for dissolved or entrained noble gases is based upon the assumption that'Xe-135 is 3

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 Protection (ICRP) Publication 2.

l The required detection capabilities for radioactive materials in liquid waste samples are tabulated in terms of the lower limits of detection (LLDs).

Detailed discussion of the LLD, and other de,tection limits can be found in HASL Procedures Manual, HASL-300 (revised annually); Currie, L. A., " Limits for Qualitative Detection and Quantitative Determination - App 1tcation to Radiochemistry," Anal. Chem. 40, 586-93 (1968); and Hartwell, J. K., "Detec-tion Limits for Radioanalytical Counting Techniques," Atlantic Richfield

-Hanford Company Report AkH-SA-215 (June 1975).

l 3/4.11.1.2 OOSE This specification is provided to implement the requirements of Sections II.A, i 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 state-ments provide the required operating flexibility and at the same time implement the guides set forth in Section IV.A of Appendix I to assure that the releases of radioactive material in liquid affluents to UNRESTRICTED AREAS will be kept "as low as is reasonably achievable." Also, for fresh'watar sites with drinking water supplies that can be potentially affected by plant operations, there is reasonable assurance that the operation of the facility will not i

result in radionuclide concentrations in the finished drinking water that are in excess of the requirements of 40 CFR Part 141.

The dose calculation method-ology and parameters in the 00CM implement the requirements in Section III.A i

of Appendix I that conformance with the guides of Appendix I be shown by calculational procedures based on models and data, such that the actual exposure of a MEMBER OF THE PUBLIC through appropriate pathways is unlikely to be substantially underestimated.

The equations specified in the 00CM for calculating the doses due to the actual release rates of radioactive materials Fyr-m C+HvME RIVER BEND - UNIT 1 8 3/4 11-1

4 RADIOACTIVE EFFLUENTS BASES

~~-~

/

3/4.11.1.2-COSE (Continued)

Hju 6 NG3 h 4 b MIN Cuide 1.100, "Celcelation of Annuel Ceses to-Man fica Rcuttne-Reactcr Effluents-for-the-Purpose-ef-Evehating-GespHence-w+th 10 CF", Part-54, Appendix I," Revi+fon 1, October 1977, and in Regulatory Guide 1.113, "Estima-ting Aquatic Dispersion of Effluents from Accidental and Routine Reactor Releases for the Purpose of Implementing Appendix I," April 1977.

3/4.11.1.3 LIQUID RADWASTE TREMMENT SYSTEM The esent that th app ffate-part ons of this system be used when Npeci fie provide's'1Xfurance that the releases of radioactive materials in liquid effluents will be kept "as low as is reasonably achievable".

This speci-fication implements the requirements of 10 CFR Part 50.36a, General Design Critarion 60 of Appendix A to 10 CFR Part 50 and the design objective given in Section II.0 of Appendix I to 10 CFR Part 50.

The limits governing the use of appropriate portions of the liquid radwaste treatment system were specified as a suitable fraction of the. dose design objectives set forth in Section II. A of Appendix I,10 CFR Part 50, for liquid effluents.

3/4.11.1.4 LIQUID HOLDUP TANXS The tanks listed in this Specification include those unprotected outdoor

~

tanks that are not surrounded by liners, dikes, or walls capable of holding the tank contents and that do not have tank overflows and surrounding area drains connected to the liquid radwaste treatment systie.

Restricting the quantity of radioactive material contained in the specified tanks provides assurance that, in the event of an uncontrolled release of the tanks' contents, the resulting concentrations would be less than the limits of 10 CFR Part 20, Appendix B, Table II, Column 2, at the nearest potable water supply and the nearest surface water supply in an UNRESTRICTED AREA.

3/4.11.2 GASEOUS EFFLUENTS 3/4.11.2.1 DOSE RATE This specification is provided to ensure that the dose, at any time at and beyond the SITE BOUNDARY, from gaseous effluents will be within the annual dose limits of 10 CFR Part 20 to UNRESTRICTED AREAS.

The annual dose limits are the doses associated witt the concentrations of 10 CFR Part 20, Appendix B, Table II, Column 1.

These limits provide reasonable assurance that radioactive material discharged in gaseous of fluents will not result in the exposure of a MEMBER OF THE PUBLIC in an UNRESTRICTED AREA, either within or outside the SITE BOUNDARY, to annual average concentrations exceeding the limits specified in Appendix B, Table II of 10 CFR Part 20.

For MEMBERS OF THE PUBLIC who may at times be within the SITE BOUNDARY, the occupancy of that MEMBER OF THE PUBLIC RIVER BENO - UNIT 1 B 3/4 11-2

RADI0 ACTIVE EFFLUENTS BASES 3/4.11.2.1 DOSE RATE (Continued) will usually be sufficiently low to compensate for any increase in the atmo-soberic diffusion factor above that for the SITE BOUNDARY.

Examples of cal-culations for such MEMBERS OF THE PUBLIC, with the appropriate occupancy factors, shall be given in the 00CM.

The specified release rate Ifmits re-strict, at all times, the corresponding gamma and beta dose rates above back-ground to a MEMBER OF THE PUBLIC at or beyond the SITE BOUNDARY to less than or equal to 500 mrems/ year to the total body or to less than or equal to 3000 mress/ year to the skin.

the corresponding thyroid dose rate above background to a child lation pathway to less than or equal to 1500 mrems/ year.

The required detection capabilities for radioactive materials in gaseous effluent samples are tabulated in terms of the lower limits of detection (LLDs).

Detailed discussion of the LLD, and other detection limits can.be found in HA.SL Procedures Manual, HASL-300 (revised annually); Currie, L. A., " Limits for Qualitative Detection and Quantitative Determination - Appliation to Radio-chemistry," Anal. Ches 40, 586-93 (1968); and Hartwell, J. K, " Detection Limits for Radicanalytical Counting Techniques," Atlantic Richfield Hanford Ccmpany Report ARH-SA-215 (June 1975).

3/4.11.2.2 DOSE - NOBLE GASES III.A and IV.A of Appendiv I, 10 CFR Part 50.This specificatioa is provided tion implements the guides set forth in Section II.B of Appendix I.The Limiting C The ACT!ON statw.ents provide the required operating flexibility and at the same time imple-ment the guides set forth in Section IV. A of Appendix I to assure that the releases of radioactive material in gaseous effluents to UNRESTRICTED AREAS 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 uides of Appendix I be shown by calculational procedures based on models ate hw s

e calculation methodology and parameters established in the ODCM for calculating the doses due to the actual release rates of radioactive noble gases in gaseous effluents are consish nt with the methodology provided in Regehte y Ca h:

/@kG NH 1.100, p.0 A # g "foc-th:

Geleulettee-of-AnmNh4-064eS-to--Man fMm Routirt Relta445 Of ReSct0" EfMU*"t?

i aurp ;c cf Eycl a t hg C:mpl ure: with 10 CFn Part 50, Appea @

I,"

Revisic6 1, Octeu r % 77, and in Regulatory Guide 1.111, " Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases i

from Light-Water Cooled Reactors," Revision 1,.-July 1977.

provided for determining the air dose at and Aeyond the he 00CM eq(uations /

BOUNO are based i

upon the histor hal averag atmo erJr/chndition L

RIVER BEND - UNIT 1 B 3/4 11-3

RADI0 ACTIVE EFFLUENTS SASES 1

l 3/4.11. 2. 3-DOSE - IODINE-131.100INE-133. TRITIUM, AND RADIONUCLIOES IN PARTICULATE FORM This specification is provided to implement the requirements of Sections II.C III.A and IV.A of Appendix I, 10 CFR Part 50.

The Limiting conditions' for Operation are the guides set forth in Section II.C of Appendix I.

The ACTION statements provide the required operating flexibility and at the same time implement the guides set forth in Section IV. A of Appendix I to assure that the releases of radioactive materials in gaJe luents to UNRESTRICTED be kep as is sonably ach able."

ODCM calculational methods spe in the 5 lance uir nts implement requirements in Section III. A of Appendix I that conform a with the guides f Appendix I be shown by calculational procedures based on models and data, su h actual. expours of a MEMBER OF THE PUBLIC through appropriate pat ys is unlikely to be substantially underestimated.

The ODCM calculational. method-ology and parameter) for calculating the desea due to the actual release rates j

of the subject materf als are consistent with tne methodology provided in I Nd% M S,> > 1 Regtriatorj Ci,1G 1.I&9; 2Gelcsistica of Annuel Oe:e; t." n fre.;; R ; tin; R:1ceses n J keA \\ of-Reactor-Effluenti for the purpose-of-Ev:!"ati g C---!ience -ith 10 CF= Part 50, 3

7 iI ' Appendh I," Rev+:i:n 1, October 10&, and in Regulatory Guide 1.111. " Methods for i

\\

Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases. from Li ht-Water-Cooled Reactors," Revision 1 July 1977.

The tions also prov d or determining the actual doses based upon thechi rical average atmo eric c tions.

The releas ra acifications f

",11ne-131, odine-

, tritium, and ra

- ide particulate

.- witu a1f i.,es greater than 8 days, are dependent upon the existing radionuclide pathways to man, in the areas at and beyond the SITE BOUNDARY.

The pathways that were examined in the development of these calculations were:

(1) individual inhalation of airborne radionuclides, (2) deposition of radionuclides onto green leafy vegetation with subsequent consumpti v man, (3) deposition onto grassy areas where milk animals 9

and meat producing of graze with consumption of the milk and meat by man, a

and (4) deposition on L.; ( ound with subsequent exposure of man.

3/4.11.2.4 WO 3/4.11.2.5 GASEOUS RADWASTE TREATMENT ANO VENTILATION EXHAUST TREATMENT The OPERABILITY of the GASEOUS RADWASTE TREATMENT (OFFGAS) SYSTEM and the VENTILATI0f6 EXHAUST TREATNENT SYSTEM ensures that the systems will be availaole for use whenever gaseous effluents require treatment prior to release to the envi ronment. The requirement that the appropriate pcrtions of these systems be used, when specified, provides reasonable assurance that the releases of

. radioactive materials in gaseous effluents will be kept "as low as is reason-ably achievable." This specification implements the requirements of 10 CFR Part 50.36a, General Design Criterion 60 of Appendix A to 10 CFR Part 50, and the design objectives given in Section II.D of Appendix I to 10 CFR Part 50.

The specified limits governing the use of appropriate portions of the systems were specified as a suitable fraction of the dose design objectives set forth in Sections II.B and II.C of Appendix I, 10 CFR Part 50, for gaseous effluents.

)

RIVER BEND - UNIT 1 B 3/4 11-4

Tu 3

I ts

.l l

ADMINISTRATIVE CONTROLS ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT (Continued) the reasons for the missing results. The missing data shall be submitted as soon as possible in a supplementary report.

i i

The reports shall also include the following:

a summary description of the radiological environmental monitoring program;-at least two legible _ maps

• covering all sampling locations keyed to a table giving distances and directions from the centerline of the reactor plant; the Msults of liccnsee participation-in the Interlaboratory Comparison Program, required by Specification 3.12.3; discussion of all deviations from the Sampling Schedule of Table 4.12.1-1; and d

u

.11 m isn ' -

required by Table 4.12.1-1 was not

,J0 WANNUAL EFFLUENT RELEASE REPORT A

6. 9.1. 8 Routine.SeetannualRadioactiveEgfluentReleaseReport/coveringthe operation within 4 #pf the unit during the previous' months of operation shall be submittad-g Uays after Januar

_pp-ijjeg4m_ w y 1 : d 2:1y 1 of each year.

TM. ; c M ef ^2: fir;t ^-

a-.. a 4 4.e s

..<*4

. m.

1, r

TheJestbnual Radioactive Effluent Release Reporty shall include a sum i

the quantities of radioactive liquid and gaseous effluents solid waste g,

i leased f the facility as outlined in ".

atory Guide. 21. ".^^.

ri ng,

,a oporting R twity ir.

11 Releases of Radio-active Materials L1 and Ga sents from Light-Water-Cooled Nuclear Power Plants," Revis on 1, June 1974, with data summarized on a quarterly basis following the format of Appendix 8 thereof.

For solid westes, the fomat for Table 3 in Appedix 8 shall be aupplemented with three additional categories:

c f solid s (as defines CFR Part a1h i of r (e.g.,

SA, T ype 8, rge ty and ICATI or abso t

(e.g., cament, urea fo deityde).

j The nual Radioe::tive Effluent Re1pse Report 0; L : tu^_f O w; eftr 2 x x r; 1 ;' n:'. ; n: shall include 1

--x? summary of hourly esteorological I

data collected over the previous year. This-ename4. summary any be'efther 'n the fom of an hour-by-hour listing on sognetic tape of wind spead, wind direc-tion and atmospegrts stability, and precipitation (if measured), or in the form of joint f tributions of wind speed, wind direction, and atmospheric stability.

te if(port shall include an assessment of the radiation doses re due to the redi ufd and gaseous affluents r station during the ymvfous calendar year.fC.h -

gaged from the unit or

. m.O shall also include an assesamont of the redtation deses frea radtosctive liqufd and gaseous effluents 80ne map shall cover stations near the SITE BOLSAARY; a second shall faclude the more distant stations.

I.

" c. ;;;. ;f :t in %. ;; 'M "'r' "'" ;

- f r':--^-' **"-- ^In Ef'h: ^

- h!:::: "g:3, O.; ik;.__.. it,^.!= ;f n^ ^f ': ^"^ mi ;f -

i;'-~' -^-- :':.!::? i'.; n ;'t L f:L ^_tt i.; L rinf f:' ^^ 'l g-7-~ ;:: ::p;t.

j RIVER SDC - UNIT 1 6-18 ev, e-e+#

r--

,v

, - =. -

.v-v 4-+e-e

O o

e, RECElvgp ADMINISTkATIVE CONTROLS m

1

>3 GEiffANNUAL EFFLUENT RELEASE REPORT (Continued) sg to MEMBERS OF THE PUBLIC due to their activities inside the SITE BOUNDARY (Figure 5.1.3) during the report period.

All assumptions used in making these assessments (i.e., specific activity, exposure time and location) shall be in-cluded in these reports.

The assessment of radiation doses shall be performed ON MANUAL (ODCM A

The Sem4/nnual Radioactive Effluent Release Report t: 5: ::b;itt:d 50 d:y: c' tar i

Je.~erj 1 :' :::P./: r shall also include an assessment of radiation doses to the likely most-exposed MEMBER OF THE PUBLIC from reactor releases and other i

i nearby uranium fuel cycg,pugsjin@gges from primary effluent pathways and direct radiation) Mr r.: F-~

cr.

__. r - to show conformance with 40 CFR Part 190, Environmental Radiation Protection Standards for Nuclear Power Operation.

Acceptable methods for calculating the dose contribution from liquid and gase us ef fluents are given in Pggry Cj{dy.y^yev.1, October.1077.

,g The,Seerpnnual Radioactive Effluent Release Reportdhall include a list and description of unplanned releases from the site to UNRESTRICTED AREAS of radio-active materials in gaseous and liquid effluents made during the reporting period.

A The Gempnnual Radioactive Effluent Release Report / shall include any changes made during the reporting period to the PROCESS CONTROL PROGRAM (PCP) and to the ODCM, as well as a listing of new locations for dose calculations and environmental monitoring ide ified by the lend use cens pursuant to ecifi-cation 3 12*2 y

J SPECIAL REPORTS 6.9.2 Special reports shall be submitted in the following manner:

Special reports shall be submitted to the U.S. Nuclear Regulatory a.

Commission, Document Control Desk, Washington, DC 20555, with a copy to the Regional Office of the NRC and a copy to the NRC Resi-dent Inspector, within the time period specified for each report, b.

Special reports in regard to Corbicula will be submitted to the NRC within 30 days of identification of infestation.

In accordance with the settlement agrtement dated October 10, 1984, these reports shall describe the level of infestation, affected systems and measures taken to prevent further infestation.

CORE OPERATING LIMITS REPORT 6.9.3.1 Core operating limits shall be established prior to startup from each reload cycle, or prior to any remaining portion of a reload cycle, for the 3

following:

~

The AVERAGE PLANAR LINEAR HEAT GENERATION RATES (APLHGR) for a.

1 Specification 3.2.1.

RIVER BEND - UNIT 1 6-19 Amendment No.17,42 1

1

9 y.

o ADMINISTRATIVE CONTROLS HIGH RADIATION AREA (Continued) 6.12.2 In addition to the requirements of Specificatio'n 6.12.1, accessible areas with radiation levels such that a major portion of the body could receive in I hour a dose greater than 1000 mrem shall be provided with locked doors to prevent unautnorized entry, and the keys shall be ruaintained under the adminis-trative control of the Control Operating Foreman on duty and/or the radiation protection supervision.

Doors shall remain locked except during periods of access under an approved RWP that specifies the dose rate levels in the imme-diate work area and the maximum allowable stay time for individuals in that For accessible areas that are located within large areas, such as the area.

containment, where no enclosure exists for purposes of locking and no enclo-sure can be reasonably constructed around the individual areas, and within which radiation levels are such that r tajor portion of the body could receive in 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> a dose in excess of 1000 mrem,* then that area shall be roped off and conspicuously posted, and a flashing light shall be activated as a warning device.

In lieu of the stay time specification of the RWP, continuous surveil-lance, direct or remote (such as use of closed circuit TV cameras), may be made by personnel qualified in radiation protection procedures to provide positive exposure control over the activities within the area.

6.13 PROCESS CONTROL PROGRAM (PCP) 6.13.1 The PCP shall be ap the Commission prior to imp [lementati

'N 6.13.2 Licensee-initia d changes to the PC :

A 1.

Shall be submitted to the Commission in the Seeiennual Radioactive Effluent Release Report.f.or the period i. which the chenge( O wcr mace.

This submittal shall contain:

Sufficiently det led informati tttallv mnnne the rationale or_the change 4 utlenant additional or ' supplemental information;.

b.

A determination that the change did not reduce the overall confor-mance of the solidified waste product to existing criteria for solid wastes; and d.-

Documentation of the fact that the change has been reviewed and found. acceptable pursuant to Specification 6.5.2.

2.

Shall become effectiv.e upon review and acceptance pursuant to Speci-ficatich 6.5.2.

^ Measurement made at < 18 inches from source of radioactivity.

RIVER BEND - UNIT 1 6-22

e ADMINISTRATIVE CONTROL 6.14 0FF

(

eME CALCULATION MANUAL (00CM) w.

4 6.14.1 ThMOOf shall be approved by the Commission prior to implementation.

6.14.,2 'L see-t han Dgethe y V^

1.

Shall be submitted to the Commission in the Seedennual Radioactive Effluent Release Report fr-th perled-ifFWhiCh-th64h;C;i%)==_l made eft:th:.

This submittal shall contain:

Sufficiently detailed infortsation to totally support t i

a.

ratiop e for the change without benef N dditional or suppi hta r information.

InformatiorLs itted sS6Utd contrit of a package of thole pages-of-the-00CM to be changed, with each page numbered and provided with an approval and date box, together with appro-priate analyses or evaluations, justifying the change (s);

b.

A determination that the change will not reduce the accuracy or-reliability of dose calculations or setpoint determinations;.and 1

i 4

Documentation of the fact that the change has been reviewed and c.

found acceptable pursuant to Specification 6.5.2.

2.

Shall become effective upon review and acceptance pursuant to Speci-fication 6.5.2.

6.15 MAJOR CHAMES TO RADI0 ACTIVE LIQUID, GASEOUS AND SOLID WASTE TREATMENT SYSTEMS 6.15.1 Licensee-init1~atedTsiifors hah ~toWradioactive waste-system (liquid (gaseous and solid):

}

1.

Shall be reported to the Commission in the See& annual Radioactive

('

Effluent Release Report fee tM:7slad i-9'e tM evaluattoa.nf_

+h> ~ha y wesw eviewed ano approved pursuant to Specification 6.5.2.

?

The discussion of each change shall contain:

A summary of the evaluation that led to the determinatfoTt at N

/

a.

1 cduld be made in aceptdance wif A 1 (CFR Part 50.59.

ficiently d'etailad_information to totally support the reason

.. TIsr the change without benefit of additional or supplemental information; A detailed description of the equipment, components and processes c.

involved and the intarfaces with other plant systems; RIVER BEND - UNIT 1 6-23

. -