ML18005A304

Proposed Tech Specs,Deleting Tables 4.11-1,4.11-2,3.12-1, 3.12-2 & 4.12-1 Re Radioactive Effluent & Radiological Environ Monitoring Programs

ML18005A304
Person / Time
Site:	Harris
Issue date:	02/16/1988
From:	CAROLINA POWER & LIGHT CO.
To:
Shared Package
ML18005A303	List: ML18005A302 ML18005A304
References
NUDOCS 8802240132
Download: ML18005A304 (49)

Text

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INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE RE UIREMENTS SECTION 3/4. 11 RADIOACTIVE EFFLUENTS 3/4. 11. 1 LIQUID EFFLUENTS Concentrat1on............

TABLE 4.11-1 lOELc.T'F9)

PRMRAMo o f oDws

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D Liquid Radwaste Treatment System.........................

Liquid Holdup Tanks............................

3/4. 11. 2 GASEOUS EFFLUENTS PAGE 3/4 11-1 3/4 11-2 3/4 11-5 3/4 11-6 3/4 11-7 ose Rate......................................

D TABLE 4.11-2~~~. (~=.~~<<>)

Dose - Noble Gases................

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3/4 11-8 3/4 11" 9 3/4 11-12 Dose - Iodine-131, Iodine-133, Triti Material in Particulate Form........

um, and Radioactive Gaseous Radwaste Treatment System..........

Explosive Gas Mixture......................

Gas Storage Tanks........;.........

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TABLE 3.12-1 TABLE 3.12"2 TABLE 4.12"1 AMI"LES.. ( PC<P..<03......

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3/4. 12.2 LAND USE CENSUS.............

3/4. 12.3 INTERLABORATORY COMPARISON PROGRAM............-..........

3/4. 11. 3 SOLID RADIOACTIVEWASTES.................................

3/4.11.4 TOTAL DOSE 3/4. 12 RADIOLOGICAL ENVIRONMENTAL MONITORING 3/4. 12. 1 MONITORING PROGRAM.......................................

3/4 11-13 3/4 11"14 3/4 11-15 3/4 11"16 3/4 11-17 3/4 11"19 3/4 12-1 3/4 12-3 3/4 12-9 3/4 12-10 3/4 12-13 3/4 12-14 R

gDOC~ 880216 880224013 CK 05000400 PDR '~

SHEARON HARRIS - UNIT 1 X11

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DEFINITIONS HASTER RELAY TEST

1. 18 A HASTER RELAY TEST shall be the energization of each master relay and verification of OPERABILITY of each relay.

The HASTER RELAY TEST shall include a continuity check of each associated slave relay.

MEMBER S

OF THE PUBLIC 1.19 MEMBER(S) OF THE PUBLIC shall include all persons who are not occupa-tionally associated with the plant.

This category does not include employees of the licensee, its contractors, or vendors.

Also excluded from this category are persons who enter the site to service equipment or to make deliveries.

This category does include persons who use portions of the site for recre-,

ational, occupational, or other purposes not associated with the plant.

OFFSITE DOSE CALCULATION MANUAL 1.20 The OFFSITE DOSE CALCULATION MANUAL (ODCM) shall contain the methodology and parameters used in the calculation of offsite doses due to radioactive gaseous and liquid effluents, in the calculation of gaseous and liquid effluent monitorin Alarm/Trip Setpoints, and in the conduct of the Environ-mental adiolo ical Honitoring Program.(REi4lP)

OPERABLE - OPERABILITY 1.21 A system, subsystem, train, component or device shall be OPERABLE or have OPERABILITY. when it is capable of performing its specified function(s),

and when all necessary attendant instrumentation, controls, electrical

power, cooling or seal water, lubrication or other auxiliary equipmeni that are required for the system, subsystem, train, component, or device to perform its function(s) are also capable of performing their related support function(s).

OPERATIONAL MODE - MODE 1.22 An OPERATIONAL MODE (i.e.,

MODE) shall correspond to any one inclusive combination of core reactivity condition, power level, and average reactor coolant temperature specified in Table 1.2.

PHYSICS TESTS 1.23 PHYSICS TESTS shall be those tests performed to measure the fundamental nuclear characteristics of the reactor core and related instrumentation:

(1) described in Chapter 14.0 of the FSAR, (2) authorized under the provisions of 10 CFR 50.59,.or (3) otherwise approved by the Commission.

PRESSURE BOUNDARY LEAKAGE 1.24 PRESSURE BOUNDARY LEAKAGE shall be leakage (except steam generator tube leakage) through a nonisolable fault in a Reactor Coolant System component body, pipe wall, or vessel wall.

SHEARON HARRIS - UNIT 1

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3/4. 11 RADIOACTIVE EFFLUENTS 3/4.11.1 LIQUID EFFLUENTS CONCENTRATION LIMITING CONDITION FOR OPERATION 3.11.1.1 The concentration of radioactive material released in liquid effluents to UNRESTRICTED AREAS (see Figure 5.1-3) shall be limited to the concentrations specified in 10 CFR Part 20, Appendix B, Table II, Column 2 for radionuclides other than dissolved or entrained noble gases.

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

APPLICABILITY: At all times.

ACTION:

With the concentration of radioactive material released in liquid effluents to UNRESTRICTED AREAS exceeding the above limits, immediately restore the concen-tration to within the above limits.

SURVEILLANCE REOUIREMENTS 4.11.1.1.1 Radioactive liquid wastes shall be sampled and analyzed according to the sampling and analysis program

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4. 11.1.1.2 The results of the radioactivity analyses shall be used in accordance with the methodology and parameters 'in the ODCH to assure that the concentrations

--at the point of release are maintained within the limits of Specification

3. 11.1.l.

SHEARON HARRIS - UNIT 1 3/4 11-1

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TABLE 4.11-1 C><<<~>)

RADIOACTIVE LI UID WASTE SAMPLING AND ANALYSIS PROGRAM

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m LIQUID RELEASE TYPE SAMPLING FREQUENCY MINIMUM ANALYSIS FREQUENCY TYPE OF ACTIVITY ANALYSIS LOWER LIM OF OETEC ON (LLO),

(NCP/ml) 1.

Batch Waste Release Tanks p

p Each Batch Each Batch Principaj3gamma Emitter s' 5xl0"7 I-131 lxl0-6 a.

,Waste Monitor Tanks b.

Maste Evaporator Condensate Tank p X, One Batch/M I

Dissol vied and lxlO.-s

'ntrafned Gases (Gamma Emitters) lx10-s lx10-7 p

M')

-3 Each Batch Composite Gross Alpha c.

Secondary Waste Sample Tank d.

Treated Laundry and Hot Shower Tanks p

Each Batch Q (4),

Sr-89, Sr-90 Compo te Fe-55 Sx10-8 lx10-6 2.

Continuo'~

6 W

6 7

4 pa) 3gamma 5x10-Releases Contgtiuous Composite Em&ters a.

Cooling Tower Meir J

M(7)

Grab Sample M(7)

Dissolved and lx10-s Entrained Gases (Gamma'Emjtters)

I-131 q

lx10"6 M

6 7

H 3 Continuous Composite Gross Alpha q67S89S9 Continuous Composite Fe-55 lxl0-s 0

7 5x10 lx10-6 I'dg<S 3/+.II Z +bros< 3/4 II-+ /qua been e//c'IBWCJ',

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SHEARON HARRIS= - UNIT 1 3/4 11-2

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TABLE 4. 11-1 Continued TABLE NOTATIONS (1)The LL is defined,'or purposes of these specifications, as the s allest concent tion of radioactive material in a sample that will yiel a net

count, ab ve system background, that will be detected with 95Ã robabi lity with only probability of falsely concluding that a blank ob ervation represents "real" signal.

For a particul measurement

system, which may include ra ochemical separation:

LLD =

Where:

4.66 sb E

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~ 2.2 x 10' Y ~ exp (-Qt)

LLD = the "a priori" lo r limit of det ction (microCurie per unit mass or volume),

sb = the standard deviation f the ackground counting rate or of the counting rate of a blank p e as appropriate (counts per minute),

E = the counting efficiency oun per disintegration),

V = the sample size (units f mass o

volume),

2.22 x 10' the number f'isintegrats ns per minute per microCurie, Y = the fractional r iochemical yield, when applicable, A, = the radioactiv decay constant for the p

ticular radionuclide (sec-~),

and bt = the clap d time between the midpoint of sam le collection and the time of ounting (sec).

Typical v ues of E, V, Y,,and bt should be used in t calculation.

. It should b

recognized that the LLD is defined as an a

rior (before the fact) mit representing the capability of 'a-measurement s

tern and (f

f )ill f p

A bat release is the discharge of liquid wastes of a discrete vol e.

Prio to sampling for analyses, each batch shall be isolated, and th

'tho oughly mixed by a method described in the ODCM to assure resentative sampling.

SHEARON HARRIS - UNIT 1 3/4 11-3

TABLE 4. 11-1 Continued TABLE NOTATIONS Continued t

C The pwincipal gamma'mmiters for which the LLD specificatiorr applies include the following radionuclides:

Mn-54, Fe-59, Co-58, Co-60,

-65, Mo-99, C

134, Cs-137, and Ce-141.

Ce-144 shall also be measure ut with a

LLD of 5 10-This list does not mean that only these nuc des are to be considered.

Other gamma peaks that are identifiable, to ether with those of the h ove nuclides, shall also be analyzed and repor ed in the Semiannual Radi active Effluent Release Report pursuant to ecifica-

'ion 6.9.1.4 in e format outlined in Regulatory Guide l. 1, Appendix B, Revision 1, June 1

4.

A composite sample is e in which the quantity of li uid sampled is proportional to the quan ity of liquid waste discha ed and in which the method of sampling employ results in a specimen hat is representative of the liquids released.

A continuous release is the dis arge of liqu d wastes of a nondiscrete volume, e.g.,

from a volume of a stem tha has an input flow during the continuous release.

To be representative of the quantities nd concentrations of radioactive materials in liquid effluents, sample s ll be collected continuously in proportion to the rate of flow of t eff ent stream.

Prior to analyses, all samples taken for the composit shall b

thoroughly mixed in order for the composite sample to be r resentative of the effluent release.

The point monitors a potentia release pathway on and not an actual release pathway.

The poten al contamination poin are in the Normal Service Water (NSW) System Action under this speci ication is as follows:

a) If the NSW mo >tors in Table 3.3-12 are OPERABL and not in

alarm, then o analysis under this specification required

',but weekly omposites will be collected.

b) If an N

monitor is out of service, then the weekly a

lysis for princi al gamma emitters will be performed.

c) If NSW monitor is in alarm or if the principal gamma emi er a

lysis indicates the presence of radioactivity as defined s

e 00CM, then all other analyses of this specification shall performed at the indicated frequency as long as the initiating conditions exist.

SHEARON HARRIS UNIT 1 3/4 11"4

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RADIOACTIVE EFFLUENTS 3/4. 11.2 GASEOUS EFFLUENTS OOSE RATE LIMITING CONOITION FOR OPERATION

3. 11.2.1 The dose rate due to radioactive materials released in gaseous effluents from the site to areas at and beyond the SITE BOUNOARY (see Figure 5.1-1) shall be limited to the following:

a.

For noble gases:

Less than or equal to 500 mrems/yr to the whole body and less than or equal to 3000 mrems/yr to the skin, and b.

For Iodine-131, for Iodine-133, for tritium, and for all radio-nuclides in particulate form with half-lives greater than 8 days:

Less than or equal to 1500 mrems/yr to any organ.

APPLICABII ITY:

At all times.

ACTION:

With the dose rate(s) exceeding the above limi.s,.immediately restore the release rate to within the above limit(s).

SURVEILLANCE 'RE UIREMENTS 4.11.2.1.1 The dose rate due to noble gases in gaseous effluents shall be determined to be within the above l.imits in accordance with the methodology, and parameters in the OOCM.

4.11.2.1.2

. The dose rate due to Iodine-131, Iodine-133, tritium, and all radionuclides in particulate form with half-lives greater than 8 days in gaseous effluents shall be determined to be within the above limits in accordance with the methodology and parameters in the 00CM by obtaining representative samples and performing analyses in accordance with the sampling g

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SHEARON HARRIS - UNIT 1 3/4 11-8

TABLE 4. 11-2

( D~lefe>J RADIOACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS PROGRAM GASEOUS EASE TYPE NIHIHUM SAMPLIHG ANALYSIS FREQUENCY FREQUENCY TYPE OF ACTIVITYANALYSIS LOWER LIMIT 0 1

DETECTION (LL (IiI'ml) 1.

Waste Gas torage Tank P

Each Tank Grab Sam le P

Each Tank Principal Gamma Emitters

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onta>nment Purge or Vent 3 ~

a.

Plant Vent Stack b.

Turbine Bldg Vent Stack, Waste Pro-cessing Bldg Vent Stacks 58 5A P

3 P

ach PURGE Each PURGE Gr Sample H(3) ~ (

(5)

Grab Sample M

Grab Sample Principal Gamma Emitt~e.s II-3 oxide Principal'Ga 5 Emitters 2)

H-oxide rincipal Gamma Emitters II-3 ox de Turb ne Bldg.

Vent Stack) lx10-lx10-~

lx10-~

lxlO-e lx10-i lxlO-4.

All Release Types as listed in 1., 2.

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and 3 ~ above Continuous (6 Charcoal Sample I-131 I-133 lx>O->>

xlO-1 0 ntinuous Continuous 6

Continuous (6 W

Par tIcul a te Sam le M

Composite Par-ticulate Sam le Q

Composite Par-ticulate Sample Principal Gamma Emitte Gross Alpha Sr-09, Sr-90 lxlo->>

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TABLE 4. 11-2 Continued TABLE NOTATIONS The LLO is defined, for purposes of these specifications, as:. the smallest ncentration of radioactive material in a sample that will yield a net

couqt, above system background, that will be detected with 95K probability with%only 5X probability of falsely concluding that a blank observation repreh'ents a "real" signal.

For a par icular measurement

system, which may include radiochemic separation:

LLO 4.66 sb E

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V

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.22 x 10' Y

~ exp (-Alt)

Where:

e LLO = the "a priori'ower limit of detectio (microCurie per unit mass or volume),

sb = the standard deviat1 n of the bac round counting rate or of the counting rate of a blan sample appropriate (counts per minute),

E = the counting efficiency (c s per disintegration),

V = the sample size (units f mass volume),

2.22 x 10

= the number f disintegrati s per minute per microCurie, Y = the fractional r diochemical yield, wh applicable, A, = the radioac ve decay constant for the pa icular radionuclide (sec-~)

and At = the apsed time between the midpoirst of sampl collection and the tim of counting (sec).

Typi 1 values of E, V, Y, and dt should be used in the lculation.

It sh ld be recognized that the LLO is defined as an a priori (b fore the act) limit representing the capability of a measurement syste and (t

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TABLE 4. 11-2 Continued TABLE NOTATIONS Continued The principal gamma emitters for which the LLD specificatioh applie include the following radionuclides:

Kr-87, Kr 88, Xe-133, Xe-133 Xe-135, and Xe"138 in noble gas releases and Mn-54, Fe-59, Co-58 Co-60, Zn-65, Mo-.99, I-131, Cs-134, Cs-137, Ce-141 and Ce-144 in Iodi and particulate, releases.

This list does not mean that only these uclides are to be consi4ered.

Other gamma peaks that are identifiable, ogether with those of the ove nuclides, shall also be analyzed and r orted in the Semiannual Rad active Effluent Release Report pursuant o Specification 6.9.1.4 in the rmat outlined in Regulatory Guide 1.2

, Appendix B, Revision 1, Dune 74.

Sampling and analysis shall also be performed fo owing shutdown, startup, or a THERMAL POWER cha e exceeding 15K of RAT THERMAL POWER within a 1-hour period.

Tritium grab samples shall e taken at 1

st once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> when the (4) refueling canal is flooded.

(5)" Tritium grab samples shall be ta en at least once per 7 days from the ventilation exhaust from the spen fuel pool area, whenever spent fuel is.

in the spent fuel pool.

The ratio of the sample flo rate to t e sampled stream flow rate shall be known for the time period overed by ea dose or dose rate calculation made.in accordance with ecifications

3. 1.2.1, 3.11.2.2, and 3.11.2.3.

Samples shall be ch ged at least once per 7 ays and analyses shall be completed within hours after changing, or ter removal from sampler.

Sampling shall a

o be performed at least once er 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> for at least 7 days followi each shutdown, startup, or THE L POWER change exceeding

, 15K of RATED ERMAL POWER within a 1-hour period nd analyses shall be completed w

hin 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> of changing.

When sample col.lected for 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> are analy d, the corresponding LLDs may be increase by a factor of 10.

This re rement does not apply if:

(1) analysis show that the DOSE EgUIVA NT I-131 concentration in the reactor coolant h

not increased more han a factor of 3; and (2) the noble gas monitor s

ws that effluent activity has not increased more than a factor of SHEARON HARRIS - UNIT 1 3/4 ll-ll

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3/4. 12 RADIOLOGICAL ENVIRONMENTAL MONITORING 3/4. 12. 1 MONITORING PROGRAM LIMITING CONDITION FOR OPERATION (g g hAF')

3.12.1 The Radiological Environmental Monitoring Progr~ shall be conducted lff APPLICABILITY: At all times.

ACTION:

RfPP a.,

With the not being d

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Pf the Commission, in the Annual Radiological Environmental Operating Report required by Specification 6.9.1.3, a description of the reasons for not conducting the program as required and the plans for preventing a recurrence.

b.

far Z&fP With the level of radioactivity as the result of plant effluents in lin medium at a specified location exceeding the reporting levels of 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 reduce radioactive effluents so that the potential annual dose" to a MEMBER OF THE PUBLIC is less than the calendar year limits of S ecifications 3.11.1.2 3.11.2.2, or 3.11.2.3.

When more than f

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medium, this report shall be submitted if:

concentration 1

concentration 2

reporting eve 1

reporting eve 2

When radionuclides other than those in 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 from all radio-nuclides is equal to or greater than the calendar year limits of Specification 3.11.1.2, 3.11.2.2, or 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 required by Specification 6.9.1.3.

"The methodology and parameters used to estimate the potential annual dose to a

MEMBER OF THE PUBLIC shall be indicated in this report.

SHEARON HARRIS - UNIT 1 3/4 12-1

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RADIOLOGICAL ENVIRONMENTAL MONITORING MONITORING PROGRAM LIMITING CONDITION FOR OPERATION ACTION Continued C.

+he Zdep With milk or fresh leafy vegetation samples unavailable from one or

, identify specific locations for obtaining replacement samples and add them.t"- ti e P~~

within 30 days, M;

The s ecific locations from which samples were unavailable may then be de eted rom Pursuant to Specification 6.14, submit in the next Semiannual Radioactive

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Effluent Release Report documentation for a change in the ODCM including a revised figure(s) and table for the ODCM reflecting the new location(s) with supporting information identifying the cause of the unavailability of samples and justifying the selection of the new location(s) for obtaining samples.

d.

The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE RE UIREMENTS 4.12;1 The radiological environmental monitoring samples shall be collected

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analyzed pursuant to the requirements of

+he RewP.

SHEARON HARRIS - UNIT 1 3/4 12-2

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TABLE 3.12-1 (~el

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RADIOLOGICAL ENVIRONHENTAL MONITORING PROGRAH" Cl ENPOSlJRE PATIMAY AND/OR SAHPLE 1.

Direct Radiation NUHBER OF REPRESENTATIVE PLES AND SAH LOCATIONS SAHPLING AND COLLECTION FRE UENCY Forty rout>

monitoring stations quarterly.

either with tw r more dosimeters or with one instr nt for measuring and records dose rate continuously, place s

follows:

An inner,'ring of stations, one in each meteorological sector in the general area of the SITE BOUN An outer ring of stati

, one in each meteorologica ector in the 6-to 8-. km nge from the site; and The ance of the stations be placed in special interest areas such as population centers, nearby residences,

schools, and in one or two areas to serve as control stations.

TYPE AND QF E

UENCY OF NALYSIS amma dose, quarterly.

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tA EXPOSURE PATIMAY AHD/OR SAMPLE 2.

Airborne Radioiodine and Particulates NUMBER OF REPRESEHTAT IVE SAMPLES AND PLE LOCATIONS Sampl from five locations:

Three samples om close to the three SIT OUNDARY locations, in diffe t

sectors, of the highes calculated annual average ground-level D/Q; SAMPLING AND COLLECTION FRE UENCY Continuous sampler oper-a tion with s amp 1 e co+ c-tion weekly, or m r4 frequently if r uired by dust loadin One sample from the vicinity of a community having the highest ca lated annual avera ground-level D/Q; and One sampl rom a control

locati, as for example 15 to 30 distant and in the least valent wind direction.

TABLE 3. 12-1 Continued RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM TYP AND FREQUFNCY OF ANALYSIS Radioiodine Cannister:

I-DT anaiysis weekly.

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Gross be ta rad

> oac tivity analysis following filter-change; and

.(3) gamma isotopic analysis of composite (by location) quarterly.

3.

waterborne a.

Surfac Ground One sample upstream.

One sample downstream.

Samples from one or two sources only if likely to be affected Composite sample over 1-month period. (6)

Quarterly.

Gamma otopic analysis (4) monthly.

Cbmposite for tritium ana s is quarterly.

Gamma isotopic nd tritium analysis qu terly

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TABLE 3. 12-1 Continued RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM NUMBER OF REPRESENTATIVE EXPOSURE PA AY SAMPLES AND AND/OR SAMPLE SAMPLE LOCATIONS 3.

waterborne (Con nued)

SAMPLIHG AND COLLECTION FRE UEHCY TYPE AND+ EqUENCY OF tfALYSIS c.

Drinking d.

Sediment from Shoreline e

s amp 1 e in the vicinity of e nearest downstream munic l water supply intake from the pe Fear River.

One sample fro a control location.

One sample in the vicinity of the cooling tower blowdown discharge in an area with existing or potential rec ational value.

Composi e sample over 2-week period when (6)

I-131 analysis is per-formed; monthly co posite otherwise miannually.

I-131 analysis on each composite when the dose calculated for the con- ~

sumption of the water is greater than 1 mrem per year Composite (D) for gross beta and gamma isotopic analyses monthly.

Composite for tritium analysis quarterly.

Gamma isotopic analysis semiannually.

Ingestion a.

Hilk Samples from lking animals in three 1

ations within 5 km distanc aving the highest dose poten al.

If there are none, th one sample from milking ima'ls in each of three areas between 5 to 8 km distant where doses are calculate(g)o be greater than 1 mrem per yr.

One sample from milking animals at a control location 15 to 30 km distant and in the least prevalent wind direction.

Semimbnthly when animals are on pasture; monthly at other times.

Gamma isotopic and I-131 analysis semi-onthly when animals are on pasture; monthly t other times.

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TABLE 3. 12-1 Continued Cl ENPOSURE PATIIMAY AND/OR SAHPLE 4.

Ingestion (Continued)

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAH I

NUHBER OF REPRESENTATIVE SAMPLES AND SAMPLE.LOCATIONS SAMPLING AND COLLECTION FRE UENCY TYPE AND FREQUQ CY OF ANALY 8 I

CA b.

Fish and Inverte-brates c.

Food Products One s

le of Sunfish, Cat" fish, an arge-Houth Bass species in cinity of plant discharge area.

One sample of same ecies in areas not influenced plant discharge.

Samples of three different kinds of broad leaf vegeta-tion grown nearest each of two different offsite loca-tions of highest predicted annual average ground level 0/g if milk sampling is not performed.

One sample of each of e

similar broad leaf geta-tion grown 15 to km dis-tant in the le t prevalent wind direct n if milk sam-pling is t performed.

Sample in season, or semiannually if they are not seasonal.

Honthly d ng growin eason.

Honthly during growing season.

G a isotopic analysis (4) on edible port.iona.

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Gamma isotopic and 1-131 (4) analysis.

Gamma isotopic and I-Q analysis.

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TABLE 3. 12-1 Continued TABLE NOTATIONS C

Specific parameters of distance and direction sector from the enterline of one. reactor, and additional description where pertinent, s all be pro-vided far each and every sample location in Table 3.12-1 in table and figure(s)gin the OOCM.

Refer to NUREG-0133, "Preparation f Radiological Effluent Tychnical Specifications for Nuclear Power Plan

," October

1978, and to Radihlogical Assessment Branch Technical Positio

, Revision 1, November 197 Oeviations are permitted from the req 'red sampling schedule if sp cimens are unobtainable due to circum ances such as hazardous condi

ons, seasonal unavailability, and alfunction of auto-matic sampling e

ipment.

If specimens are unobt nable due to sampling equipment malfunct'on, effort shall be made to c piete corrective actioa prior to the end of he next sampling period.

1 deviations from the sampling schedule sha 1

be documented in the nual Radiological Environ-mental Operating Repor pursuant to Specific ion 6.9.1.3.

It is recog-nized that, at times, i may not be possibl or practicable "to continue to obtain samples of the me a of choice at e most desired location or time.

In these instances suitabl alternative edia and locations may be chosen for the particular pathway question nd appropriate substitutions made within 30 days in the Radiolo ical En ronmental Monitoring Program.

Pur-suant to Specification 6.14, s

mit n the next Semiannual Radioactive Effluent Release Report documen t n for a change in the ODCM including a revised figure(s) and table for he OOCM reflecting the new location(s) with supporting information ide i

ing the cause of the unavailability of samples for that pathway an jus fying the selection of the new loca-tion(s) for obtaining samples (2)

One or more instruments, s

h as a pres rized ion chamber, for measuring and recording dose rate c n inuously may e used in place of, or in addi-tion to, integrating do meters.

For the rposes of this table, a

thermoluminescent dosi ter (TLD) is conside ed to be one phosphor; two or more phosphors in packet are considered two or more dosimeters.

Film badges shall n

be used as dosimeters fo measuring direct radiation.

'The 40 stations i not an absolute number.

The number of direct radiation monitoring statio s may be reduced according to g graphical limitations;

, e.g.,-at an oce

site, some sectors will be over ter so that the number of dosimeters ay be reduced accordingly.

The frequ ncy of analysis or readout for T systems will depend upon the characte istics of the speci-fic system ed and should be selected to obtain optim dose information within min'mal fading. )

(3)

Airborn particulate sample filters shall be analyzed for oss beta radio tivity 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 r don and thoro daughter decay.

If,gross beta activity in air particu te samples is eater than 10 times the yearly mean of control

samples, g

a is topic analysis shall be performed on the individual samples.

(4),'Gamma isotopic analysis means the identification and quantification of gamma-emi'tting radionuclides that may be attributable to the effluen s

from the facility.

SHEARON "HARRIS - UNIT 1 3/4 12-7

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TABLE 3. 12-1 Continued TABLE NOTATIONS Continued (5)

The "ups earn sample" shall be taken at a distance beyo significant influence the discharge.

The "downstream" sample all be taken in an area beyond t near the mixing zone.

"Upstream" mples in an estuary must be taken r enough upstream to be beyond t plant influence.

Salt water shall be s

led only when the receivin ater is utilized for recreational activi 'es.

(6)

A composite sample is o

in which the antity (aliquot) of liquid sampled is proportional to the qu tity of f wing liquid and in which the method of sampling employed results in a ecimen that is representative of the liquid flow.

In this program osite sample aliquots shall be collected at time intervals that are ve ort (e.g., hourly) relative to the compositing period (e.g.,

m thly) 'n order to assure obtaining a

representative sample.

(7)

Groundwater samples all be taken when t s source is tapped for drinking or irrigation purp es in areas where the h

raulic gradient or recharge properties are i'table for contamination.

(8)

The dose s

1 be calculated for the maximum organ nd age group, using the meth ology and parameters in the ODCM.

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TABLE 3.12-2 COel~ 4>)

REPORTING LEVELS FOR RAOIOACTIVITY CONCENTRATIONS IN ENVIRONMENTAL SAMPLES ANALYSIS MATER (pci/1)

IROORNE PARTICULATE GASES (pCi/m3)

FISN (pCi/kg, wet)

K pc j/1)

FOOD PRODUCTS (pCi/kg, wet)

N-3 Hn"54 Fe-59 Co-58 Co-60 Zn-65 7r Hb-95 1-131 Cs-134 Cs"137 Ba-La-140 20,000*

1,000 400 1,000 300 300 400 2k*

30 50 200 0.9 10 20 30,000 10, 0,000 10,0 20,000 1,000 2,000 60 70 300 100 1,000 2,000 "For dri ng water samples.

This is 40 CFR Part 141 value.

If no drinking water pathway exists, a value of 3

, 00 pCi/l say be used.

no drinking water pathway exists, a value of 20 pCi/1 may be used.

Pd P/+ lg-O'aa bee~ 4'8/eW.

gc'~R + <~8 /chic'Ac, (oy. (g / &v'i~cn~pnfg I /'~.

<<en'e R'oy. a~

r'n +he 08CQ

gr

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TABLE 4. 12-1 (Oe~<<~>~

DETECTION CAPABILITIES FOR ENVIRONMENML SAMPLE ANALYSIS LOWER LIMIT OF DETECTION LLD WATER e

ANALYSIS (pCi/l)

Gross Beta 4

ll-3 2000*

AIR NE PARTICULATE OR G

S (pCi/m~)

0.

F ISll HILK (pCi/kg, wet)

(pCi/I)

FOOD P

UCTS SEDIMENT (p

g, wet)

(pCi/kg, dry)

Hn-54 Fe-59 15 30 130 Co-58,60 15 Zn-65 30 Zr-Nb-95 15 ED 1-131 i%A

0. 07 130 260

. 60 Cs-134 Cs-137 Ba-. La-140 15 18

0. 05

0. 06 130 150 15 18 15 gO 80 150 180 "If no nking water pathway exists, a value of 3000 pCi/1 may be used.

""I no drinking water pathway exists, a value of 15 pCi/l may be used.

Edged p/4.

!2-r'a Philo~ j Z(W V-)2. Rave dep~ d'e(el'. /eA-6 H8e if~6~;u~cy.ca

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E~~~<<1 F Al01e ]dry'ng p opia.n in /AD g3p~

TABLE 4.12-1 Continued TABLE NOTATIONS (l)This list does not mean that only these nuclides are to be conk red.

Other eaks that are identifiable, together with those of the a ove nuclide shall also be analyzed and reported in the Annual R

iological Environme tal Operating Report pursuant to Specification 6.9

.3-(2)Required det tion capabilities for thermoluminescent dos'ters used for environmen al measurements shall be in accordance wi h the recommenda-

'tions of Regula ry Guide 4.13.

For a particular measurement ystem, which ay include radiochemical separation:

4.66 LLD E

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V

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2. 22 exp(-Abt)

Where:

(3)The LLD is defined, for purposes of these specifica

ons, as the smallest concentration of rad active material in a sample hat will yield a net

count, above system ba kground, that will be det ted with 95~ probability

'ith only 5X probabilit of falsely concluding hat a blank observation represents a "real" signa LLD

= the "a priori" lower mit of de ction (picoCuries per unit mass or volume),

sb.

= the standard devi ion of the backgro d counting rate or of the counting. rate of a blank sample as app riate (counts per minute),

E

= the counting fficiency (counts per disint ration),

V

= the sampl size (units of mass or volume),

2.22 = the nu er of disintegrations per minute per pic

uric, Y

= the ractional radiochemical yield, when applicable, e radioactive decay constant for the particular radio uclide sec-~),

and ht

= the elapsed time between environmental collection, or end o

the sample collection period, and time.of counting (sec).

ypical values of E, V, Y, and ht should be used in the calculation.

SHEARON HARRIS - UNIT 1 3/4 X2-11

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TABLE 4. 12-1 Continued TABLE NOTATIONS Continued It should be re ized that the LLD is defined a

n a priori (before the fact) limit represen the capability of a surement system and not as an a

osteriori (after the limit f a particular measurement.

AnaTyses sha be performed in s armer that the stated LLOs vill be achieved under routine conditio Oc

'onally background fluctuations, unavoidable small sample si

, the presenc interfering nuclides, or other uncontrollable c'tances may render the LDs unachievable.

In such cases, the ntributing factors shall be ident and described in the Annual sological Environmental Operating Report pu nt to Specifica 6.9.1.3.

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RADIOLOGICAL ENVIRONMENTAL MONITORING 3/4. 12.3 INTERLABORATORY COMPARISON PROGRAM LIMITING CONDITION FOR OPERATION 3.12.3 Analyses shall be performed on all radioactive part of an Interlaboratory Comparison Program that has Commission, that correspond to samples required by

+be APPLICABILITY: At all times.

ACTION:

materials, supplied as been approved by the ZQQi~lagica I'c.'<oa.nr~fs f

~ +AC 0@CA.

a.

With analyses not being performed as required

above, report the

. corrective actions taken to prevent a recurrence to the Commission in the Annual Radiological Environmental Operating Report pursuant to, Specification 6.9. 1.3.

b.

The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE REOUIREMENTS

4. 12.3 The Interlaboratory Comparison Program shall be described in the ODCM.

, A summary of the results obtained as part of the above required Interlaboratory Comparison Program shall be included in the Annual Radiological Environmental Operating Report pursuant to Specification 6.9.1.3.

SHEARON HARRIS - UNIT 1 3/4 12-14

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3/4. 11 RADIOACTIVE EFFLUENTS BASES 3/4.11.1 LI UID EFFLUENTS 3/4. 11. l. 1 CONCENTRATION This specification is provided to ensure that the concentPation of radioactive materials released in liquid waste effluents to UNRESTRICTED AREAS will be less than the concentration levels specified in 10 CFR Part 20, Appendix B, Table II, Column 2.

This limitation provides additional assurance that the levels of radioactive materials in bodies of water in UNRESTRICTED AREAS will result in exposures within:

(1) the Section II.A design objectives of 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 limit for dissolved or entrained noble gases is based upon the assumption that Xe-135 is the controlling radioisotope and its MPC-in air (submersion) was converted to an equivalent concentration in water using the methods described in International Commission on Radiological Protection (ICRP) Publication 2.

~ i 3/4. 11. 1. 2 DOSE Thss specification is provided to implement the requirements of Sections II.A, III.A, and IV.A of Appendix I, 10 CFR Part 50.

The Limiting Condition for Operation implements the guides set forth in 'Section II.A of Appendix I.

The ACTION statements provide the required operating flexibility and at the same time implement the guides set forth in Section IV.A of Appendix I to assure that the releases of radioactive material in liquid effluents to UNRESTRICTED AREAS will be kept "as low as is reasonably achievable."

The dose calculation methodology and parameters in the ODCM implement the requirements in Sec-tion III.A of Appendix I that conformance with the guides of Appendix I be shown by calculational procedures based on models and data, such that the actual exposure of a MEMBER OF THE PUBLIC through appropriate pathways is unlikely to be substantially underestimated.

The equations specified in the ODCM for cal-culating the doses due to the actual release rates of radioactive materials in liquid effluents are consistent with the methodology provided in Regulatory Guide 1.109, "Calculation of Annual Doses to Man from Routine Releases of Reac-tor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I," Revision 1, October 1977 and Regulatory Guide 1. 113, "Estimating Aquatic Dispersion of Effluents from Accidental and Routine Reactor Releases for'he Purpose of Implementing Appendix I," April 1977.

SHEARON HARRIS - UNIT 1 B 3/4 11-1

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RADIOACTIVE EFFLUENTS BASES DOSE RATE Continued above background to a child via the inhalation pathway to less than or equal to 1500 mrems/year.

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3/4.11.2.2 DOSE - NOBLE GASES This specification is provided to implement the requirements of Sections II.B, III.A and IV.A of Appendix I, 10 CFR Part 50.

The Limiting Condition for Opera-tion implements the guides set forth in Section I'.B of Appendix I.

The ACTION statements provide the required operating flexibility and at the same time implement the guides set forth in Section IV.A of Appendix I to assure that the releases of radioactive material in gaseous effluents 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 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 appro-priate pathways is unlikely to be substantially underestimated.

The dose cal-culation 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 consistent with the methodology provided in Regulatory Guide 1. 109, "Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I,"

Revision I, October 1977 and Regulatory Guide 1.111, "Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light-Water Cooled Reactors,"

Revision 1, Ju1y 1977.

The ODCM equations provided for determining the air doses at and beyond the SITE BOUNDARY are based upon the historical average atmospheric conditions.

3/4. 11. 2. 3 DOSE - IODINE-131 IODINE-133 TRITIUM AND RADIOACTIVE MATERIAL N

AR ICULA RM This specification is provided to implement

.he 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'adioactive materials in gaseous effluents to UNRESTRICTED AREAS will be kept "as low as is reasonably achievable."

The ODCM calculational methods specified in the Surveillance Requirements implement the requirements SHEARON HARRIS - UNIT 1 B 3/4 11-3

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3/4. 12 RAOIOLOGICAL ENVIRONMENTAL MONITORING BASES 3/4. 12. 1 MONITORING PROGRAM The Radiological Environme'ntal Monitoring Program required by this specification provides representative measurements of radiation and of radioactive materials in those exposure pathways and for those radionuclides that lead to the highest potential radiation exposure of MEMBERS OF THE PUBLIC resulting from the plant operation.

This monitoring program implementsSection IV.B.Z of Appendix I to 10 CFR Part 50 and thereby supplements the Radiological Effluent Monitoring Program by verifying that the measurable concentrations of radioactive materials and levels of radiation are not higher than expected on the basis of the effluent measurements and the modeling of the environmental exposure pathways.

Guidance for this monitoring program is provided by the Radiological Assessment Branch Technical Position on Environmental Monitoring, Revision 1, November 1979.

'he initially specified monitoring program will be effective for at least the first 3 years of commercial operation.

Following this period, program changes may be initiated based on operational experience.

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3/4.12.2 LANO USE CENSUS this specification is provided to ensure that changes in the use of areas at and beyond the SITE BOUNOARY are identified and that modifications to the Radiological Environmental Monitoring Program are made if required by the results of this census.

The best information from the door to-door survey, from aerial survey or from consulting with local agricultural authorities shall be used.

This census satisfies the requirements of Section IV.B.3 of Appendix I to 10 CFR Part 50.

Restricting the census to gardens of greater than 50 mz provides assurance that significant exposure pathways via leafy vegetables'will

~

be identified and monitored since a garden of this size is the minimum required to produce the quantity (26 kg/year) of leafy vegetables assumed in Regulatory Guide 1. 109 for consumption by a child.

To determine this minimum garden size, the.following assumptions were made:

(1) 20K of the garden was used for growing broad leaf vegetation (i.e., similar to lettuce and cabbage),

and (2) a vegeta-tion yield of 2 kg/m~.

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