ML20128B003

Forwards Revised Environ TS for Radwaste Treatment & Monitoring Sections to Conform to STS Under Reg Guide 4.8

ML20128B003
Person / Time
Site:	Monticello
Issue date:	03/25/1975
From:	Benaroya V Office of Nuclear Reactor Regulation
To:	Regan W Office of Nuclear Reactor Regulation
References
NUDOCS 9212030534
Download: ML20128B003 (29)

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e S a r 7s N cFet ':n. 5"4f 3 U. Eernn, Chief Environrental Projects Branch No. 4, RL ENVIRO'0DITAL TECHNICAL SPECIFICATIONS TOR ?DNTICELLO MFCLEAR C1METATING STATIO'i Plant Matt.c: lionticello Licensing Stare:

ITL Docket Nunber:

50-263 Responsible Branch: EPb f4 Project Leader:

E. Bevan tequented Conpletion Date:

F. arch 19, 1975 Description of Response: Environmenta: Technical Specifications

eviev Statun:

Completc The encloacd Envirourental Technical Specifications for the radioactive vante trentrent and monitorinr. eections for %nticello h,ve been revised to confere to the Standard Technical Specifications under Lego).atory Guid 4.8, presently in preparatim1.

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Victor nenaroyn, Chief Effluent Treatment Systemn Prnnch Division of Technica3 Keviev office of Nuclear Reactor Eerulation DISTRIB'? TION:

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PROPOSED TEClINICAL SPECIFICATIONS FOR MONTICELLO NUCLEAR GENERATING STATION.

_ Docket Number 50-263 2.4 LIlf1 TING CONDITIONS FOR OPERATION Radioactive Effluents Objective:

To define the limits and conditions for the controlled-release of radioactive materials in liquid and gaseous effluents to the environs to ensure that these releases are as lov as practicable.

These releases should not result in radiation exposures in unrestricted areas greater than a few percent of natural background exposures.

The concentrations of radioactive materials in effluents shall be within the limits specified in 10 CFR Part 20.

To ensure that the releases of radioactive material above background to unrestricted areas be as _ low as practicabic as defined in Appendix I to 10 CFR Part. 0, the following design objectives apply:

5 For liquid wastes:

n.

The annual dose above background to the total body or any organ of an individual.from all reactors at a site should not exceed 5 mrca in an unrestricted area, b.

The annual total quantity of radioactive materials in liquid vastc.. excluding tritium and dissolved gases, discharged from each reactor chould not exceed 5 Ci.

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+

• 1 For gaseous' wastes:

c.

The annual total quantity of noble Eases above background dis-charged from the site should result in an air dose due to gan=a radiation of less than 10 mrad, and an air dose due to beta radiation of less than 20 mrad, at any location near ground 1cvel which could be occupied by individuals at or beyond the boundary _

of the site.

d.

The annual total quantity of all radioiodines and radioactive caterial in particulate forms with half-lives greater than eight days, above background, from all reactors at a site should not result in an annual dose to any organ of an individual in.an unrestricted area from all pathways of exposure in excess of 15 mrem, The annual total quantity of iodine-131 discharged from each.

c.

reactor at a site should not exceed 1 C1.

2.4.1 specifications for Liquid'uaste Effluents The concentration of radioactive materials released in liquid a.

vaste effluents from all reactors at the site shall not exceed the valuc specified in 10 CFR Part 20, Appendix B Table II, Column 2, for unrestricted areas.

b.

The cumulative release of radioactive materials in liquid vaste effluent excluding tritium and disso".ved gases, shall not exceed 10 C1/ reactor / calendar quarter.

n c.

The cumulative release of radioactive materialsnin liquid vaste effluents, excluding tritium and dissolved gases, shall'not cxceed 20 C1/rcactor in any 12 consecutive months.

d.

The equipment installed in the liquid radioactive vaste. system shall be maintained and shall be operated to process radioactive liquid vastes prior to their discharge when the projected cumulative release could exceed 1.25 Ci/rcactor/ calendar quarter, excluding tritium and dissolved gases.

c.

The maximum radioactivity to be contained in any liquid radwaste tank that can be. discharged directly to the environs shall not exceed 10 Ci, excluding tritium and dissolved gases.

f.

• If the cumulative release of radioactive materials in liquid eff)uents, excluding tritium and dissolved gases, exceeds-2.5 Ci/ reactor / calendar quarter, the licensec shall made.an investigation-to identify the causes for such releases, define and initiate a program of action to reduce such releases to the design objective levels listed in Section 2.4, and report these action.s to the_.

NRC in accordance with Specification 5.6.2.c(1).

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g.

An unplanned or uncontrolled offsite release of radioactive materials in liquid effluents in excess-of 0.5 curies requires-notification.

This notification shall be in accordance with Specification 5.6.2.c(3).

2.4.2 Specifications for Licuid Waste Sampling and Monitorine a.

Plant records shall be maintained of the radioactive concentration and volume before dilution of liquid waste intended for discharge and the average dilution flow and length of time over which each discharge occurred.

Sample analysis results and other reports shall be submitted as required by Section 5.6.1 of thesc Specifications.

Estimates of the sampling and analytical errors associated with each reported value shall be included.

b.

Prior to release of each batch of liquid waste, a sampic shall be taken from that batch and analyacd for the concentration of

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l cach significant ga 7.a energy peak in accordance with Table 2.4-l' to demonstrate compliance with Specification 2.4.1 using the flow rate into which the waste is discharged during the period of discharce, c.

Sampling and analysis of liquid radiccetive waste shall be perforced in accordance with Tabic 2.4-1.

Prior to taking-sampics from a conftering tank, at 1 cast two tank volumes shall be recirculated.

d.

The radioactivity in liquid wastes shall be continuously uonitored and recorded during release.

Whenever these nonitors are inoperabic for a period not to exceed 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, two independent sampics of each tank to be discharged shall be analyzed and two I

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~5-plant personnci shall independently check valving prior to the discharge.

If these conitors are inoperable for a period exceeding 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, no release from a. liquid waste tank shall be made and any release in progress shall be terminated.

e.

The flow rate of liquid radioactive waste shall be continuously measured and recorded during release.

f.

All liquid effluent radiation monitors shall be calibrated at least quarterly by.means of a radioactive source which has been calibrated to a National Bureau of Standards source.

Each monitor shall also have a functional test monthly and an instru-ment check prior to mcking a release.

Bases:

The release of radioactive materials in liquid waste effluents to 1

i unrestricted areas shall not exceed the concentration limits specified in 10 CFR Part 20 and should be as low as practicable j

in accordance with the requirements of 10 CFR Part 50.36a.

These specifications provide reasonable assurance-that the resulting annual dose to the total body or any organ of an individual in an i

I unrestricted area vill not exceed 5 mrom.

At the same time, these.

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specifications permit the ficxibility of operation, compatible with considerations of health.and safety, to assure that the public.

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d sual operating-is provided a dependabic source of power un er unu temporarily result in releases higher.than conditions which eif the design objective levels but still within the concentration

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It is expected that by using.

limits specified in 10 CFR Part 20.

this operational ficxibility under unusual operating conditions, and exerting every effort to keep levels of radioactive material the annual releases will in liquid wastes as low as practicabic, not exceed a small fraction of the concentration limits specified in 10 CFR Part 20.

The design objectivca have been developed based on operating experi-ence taking into account a combination of variables including defective fuel, primary system 1cahage, and the performance of the various vaste

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50 treatment systens, and are consistent with Appendix I to 10 CFR Part Specification 2.4.1.a requires the licensee to limit the concentratien -

of radioactive materials in liquid waste effluents rcleased from the cite to 20, Appendix E, Tabic 11, Column 2, for.

ICvels specified in 10 CFR Part l

This specification provides assurance that no unrestricted areas.

member of the general public will be exposed to liquid contain!7g i

radioactive materials in excess of limits considered permissible

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, 4 Specifications 2.4.1.b and 2.4.1.c establish the upper limits for the release of radioactive caterials in liquid effluents.

The intent-of these Specifications.is to permit the licensee the flexibility of operation to assure that the public is provided a dependable source of power under unusual operating conditions which may temporarily result in releases higher than the levels normally achievable when the plant and the liquid vaste treatment systems are functioning; as designed.

Releases of up to these levels will result in concentrations of radioactive material in liquid vaste effluents at small' percentages of the limits specified in 10 CFR Part 20.

4 Specification 2.4.1.d requires that the licensee maintain 'and operate the equipment installed in the liquid vaste systems to reduce the release l

of radioactive caterials in liquid effluents to as lov as practicabic consistent.with the requirements of 10 CFR Part 50.36a.

Normal use and maintenance of installed' equipment in the liquid waste rystem provides reasonabic assurance that the quantity released will not exceed the design objective.

In order to keep releases of radioactive materials as low as practicable, the specification requires operation-of < cquipment. whenever ~it appears that the projected cumulative' dis-charge rate vill execed one-fourth of this design objective ' annual quantity during any calendar quarter.

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I Specification 2.4.1.e restricts the amount of radioactive caterial that could be inadvertently released to the environment to an amount that vill not execed the Technical Specification limit.

In addition to limiting conditions for operation listed under Specifications 2.4.1.b and 2.4.1.c, the reporting requirements of Specification 2.4.1.f delineate that the licensec shall identify the cause whenever the cumulative release of radioactive materials in liquid vaste effluents exceeds one-half the design objective annual quantity during any calendar quarter and describe the proposed program of action to reduce such releases to design objective levels on a tirely basis.

This report rust be filed within 30 days following the calendar quarter in which the release occurred as required by-Specification 5.6.2 of these Technical Specifications.

Specification 2.4.1.g provides for reporting spillage or release events which, while below the limits of 10 CFR Part 20, could result in releases higher than the design objectives.

The sampling and tonitoring requirements given under Specification 2.4.2 provide assurance that radioactive materials in liquid wastes are properly contcolled and conitored in conforcance with the requirements of Design Criteria 60 and 64.

These requirements provide the data for the licensec and the Concission to evaluate the plant's performance i

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relative to radioactive liquid vastes released to the environment.

Reports on the quantitics of radioactive materials released in liquid vaste effluents are furnished to the Commission according to Section 5.6.1 of these Technical Specifications.

On the basis of such reports and any additional information the Commission may obtain from the licensee or others, the Commission may from tine to time require the licensee to take such action as the Commission deems appropriate.

The points of release to the environment to be monitored in-Section 2.4.2 include all the monitored release points as provide'd for in Tabic 2.4-3.

2.4.3 Specifications for Gascous Uaste Effluents The terms used in these Specifications are as follows:

subscripts v, refers to vent releases s, refers to stack releases 1, refers.to individual noble gas nuclide

- (Refer to Tabic 2.4-5 for the noble gas nuclides considered)

QT - the total noble gas release rate (Ci/sec)

Qi sum of the individual nobic gas radionuclides determined-

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to be present by. isotopic analysis e.,.

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Ea the average total body dose factor due to gamma emission (rem /yr per Ci/sec)

L = the average skin dose factor due to beta emissions (rem /yr per Ci/sec) li = the average air dose factor due to beta emissions (rad /yr per Ci/sec)

E = the average air dose factor due to gamma emissions (rad /yr per C1/sec)

The values of E, E,'.i and 5 are to be determined each time isotopic analysis is required as delineated in Specification 2.4.4.

Determine. the following using the results of the noble gas radionuclide analysis:

E=(1/QT)[Q1i E

L=(1/Q)f91i T

L li = (1/Q )

9M11 T

5 = (1/Q ) [91 i N

T 1

where the values of K, L, Mi and Ni are provided in Table 2.4-5, 1

i and are site dependent gamma and beta dose factors Q = the censured release rate of the radiciodires and radioactive tanterials in particulate forms vith half-lives greater than cightdays, n.

(1)- The release rate limit of noble gases from the site shall be such that 2.0 Q

+

9 11 Tv v Ts s and 0.33 QTv(E + 1 1 y)

+ 9Ts( s + 1.13 )

< 1 v

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1 l 4 (2) The release rate limit of all radiciodines and radioactive materials in particulate form with half-lives greater than-cight days, released to the environs as part of the gaseous vastes from the site shall be such that 5

+ 2.5 x lo' Q,1 1

3. 7 x 10 b.

(1) The average release rate of nobic gases from the site during any calendar quarter shall be such that 13 Q

+ S 11 Tv v Ts and 6.3 QE

+ Q II 11 gy g

(2) The average release rate of noble gases from the site during any 12 consecutive nonths shall be 25 Q u

+ Q N

~<1 gy Ts q and 13 Q

+ O 1

Tv v Ts (3) The average release rate per site of all radiciodines and radio-active caterials in particulate form with half-lives greater than eight days during any calendar quarter shall be such that 5

4 13 3.7 x10

+

5 x10 q y

J (4) The average release rate per site of all radioiodines and radioactive materials in particulate form with half-lives Lrcater than eight days during any perioT of 12" consecutive months shall be such that 5

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25 3. 7 x10 Q

+ 2.5x10 Q 11 y

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(5) The account of iodine-131 released during any calendar quarter shall not exceed 2 Ci/rcactor.

(6) The amount of iodine-131 released during any period of 12 consecutive months shall not execed 4 C1/ reactor.

c.

Should any of the conditions of 2.4.3.c(1), {2) or (3) listed below exist, the licensec shall make an investigation to identify the causes of the release rates, define and initiate a progran of action to reduce the release rates to design objective levcis listed in Section '.4 ar.3 report these actions to the NRC within 30 days from the end of the quarter during which the releases occurred.

(1)

If the average release rate of nobic gases from the site during any calendar quarter is such that Q,y5

+ Q 1

50 3 y Ts s or 25 Q Ii

+ Q ii

>l Tv v Ts s (2)

If the average release rate per site of all radiciodines and radioactive materials in particulate form with half-lives greater than eight days during any calendar quarter is such that 3,7 x10 Q + 2.5 >1rI q

>1 5

50 y

(3)

If the amount of iodine-131 released during any calendar quarter is greater than 0.5 Ci/r,cactor.

d.

During the release of gascous unstes from the pr'inary system vaste gas holdup system the effluent nonitors listed in Tabic 2.4-4 shall be operating and set to alarm and to ir.itiate the

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automatically closure of the vaste gas discharge valve prior

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j to exceeding the limits specified in 2.4.3.a above. The capability of each automatic isolation valve shall be demonstrated quartsrly.

e.

If no sain condenser vacuum system offgas monitor is operating, t

releases from the offgas system shall be terminated within 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br />.

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If the gross radioactivity rate of noble cases from the main condenser vacutuu system exceeds 260,000 uC1/see for a period greater than 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />, notify the NRC in accordance with Specification 3.6.2.c(4).

g.

The drywell shall be purged through the standby gas treatment system or released to the environment at a rate in confornance with Specification 2.4.3.c(2) and (3) based on a containment '

nampic analysis defined in Table 2.4-2.

h..At 1 cast two hydrogen monitors in the offgan Ifnc downstream of the recombiners shall be operable during power operation..If:

the hydrogen concentration reaches an alarm set point of four percent by volume, the offgas flow through the baseline nobic gas retention equipment shall be stopped by closing -the valves i

downstream of the recombiners.. Whenever either of these monitors I

is inoperabic during power operation, a program shall be initiat ed.to bring the activity releases within two percent -

of the limits in Specification 2;4.3.a(1), and grab sarepics shall be taken and analyzed for hydrogen concentration each shift.- Calibration of the monitoring system shall be performcd wechly.

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An unplanned or uncontrolled offsite release of radioactive materials in gaseous effluents in er. cess of 5 curies of noble gas or 0.02 curie of radiciodine in gaseous form requires a

notification. This notification shall be in accordance with Specification 5.6.2.c(3).

?.4.4 Specifications for Caseous Maste Sampling and Monitoring a.

Pltnt records shall be maintained and reports of the sampling and analyses results shall be submitted in accordance with Section 5.6 of these specifications.

Esticates of the sanpling and analytical error associated with each reported value should be included.

b.

Caseous releases to the environment, except for the turbine building ventilation roof vents, shall have the flow continuously measured and recorded and shall be continuously nonitored for gross radioactivity. Uhenever these monitors are inoperable, grab sarples chall be taken and analyzed daily for procs radioactivity.

If these monitors are inoperable for more than seven days, these releases shall be terminated.

Gaccous releases from the turbine building roof vents shall be determined by daily sampling and analysis for noble gases, and for radiciodine and radioactive urterial in particulate forma with half-lives greater than eight dayc. The daily sauples shall be taken at the intake of each operatinC roof vent exhaut,ter. The "Qy" and "Q" used.',n the equations given in Specifications 2.4.3 shall include the se analysis results, and I

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shall be. based on the measured flow rate or a design flow t

rate of 12,500 cfm for each operating roof vent exhaunter.

k The damper position and roof vent exhauster operating condition shall be checked and recorded each shift.

c.

An isotopic analysis shall be mada of a representativo sample of gaseous activity, at the discharge of-the stecm jet air ejectors and at a point prior to dilution and dischargo.

(1) within one month of initial criticality, (2) at leant monthly thereafter, (3)' following each refueling outage, and (4) if the gasects vaste monitors indicato an increase of greater thar 50% in the steady state fission cas relcanc after factoring out increases due to power changes.

d..All waste gas effluent monitors chall be calibrated at Icast I

quarterly by means of, a known radioactive source which has bec'n calibrated to a National Bureau of Standards sourec.

Each monitor shall have a functional test at least monthly and instrument check at.leest daily..

P c.

Sampling and analysis of radioactive material in gaseous vaste, including particulate forms and radiciodines shall be performed-in accordance with Tabic 2.4-2.

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l Essen:_ The release of radioactive materials in gaseous waste effluents to unrestricted areas chall not exceed the concentration limits specifiedin10CFRPart2bandshouldbeaslowaspracticalin i

accordance with the requirements of 10 CFR Part 50.36a.

These t

t specifications provide reasonabic assurance that the resulting annual air doce from the site due to gamma radiation will not execed 10 mrad, and an annual air dose from the site due to beta radiation vill not excced 20 crad from nobic gases, that no individual in an unrestricted area will receive an annual dose to the total body greater than 5 nrem or an annual skin doce greater than 15 mrem from fission product noble gases, and that the annual dose to any organ of an individual-from radiciodines and radioactive material in particulate form with half-lives greater than cicht days u111,not execed 15 mrem per site.

t At the same time these specifications permit the ficxibility of operation, compatibic with considerations of health and safety, to assure that the public is provided.with a dependabic sourec~ of power e

a under unusual operating conditions which may temporarily result in' releases higher than the design objective icvcis but still within the concentration limits specified in 10 CFR Part 20, 4 Even with this operational ficxibility under unusual operating condttions, if-the licensec exerts every effort to keep icvels of'rndioactive material -

e, in gaseous vaste effluents as low as.practicabic, the annual releases-t will not.cxceed a cmall fraction of the concentration limits specified in 10 CFR Part 20.-

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The design objcetives have been developed based on operating experience taking into account a combination of system variabics including defective fuel, primary system leakage, and the performance of the various vaste treat ment rystems.

Specification 2.4.3.n(1) ilmits the release rate of nobic gases from the site so that the corresponding annual gamma and beta dose rate above background to an individual in an unrestricted aren vill not exceed

l 500 mrem to the total body or 3000 mrce to the skin in compliance with the limits of 10 CPR Part 20.

For Specification 2.4.3.a(1), gamma and beta dose f acturs for the individual nobic gas radionuclides have been calculated for the picnt gaseous release points and are provided in Tabic 2.4-5.'

The expressions-used to calculate these dose factors are based on dose models derived in Section 7 of Meteoro1ory and Atomic Encrcy-1968 and model-i techniques'provided in Draft Regulatory Guide 1.AA.

t Dose calculations have been made to determine the site boundary location with the highest anticipated dose rate from nobic cases using on-nite meteorological data and the dose expressions provided in Draft Regulatory Guide 1.AA.

The doce expression considers the release point location, building vake effe~ cts, and the physical cha:acteristics of.

the radionuclides, e

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The offsite location with the highest anticipated annual dose from ralcased noble gases is 700 meters in the SSE direction.

1 The reicase rate Specifications for a radiciodinc.and radioactive natcrial in particulate form with half-lives greater than eight. days are dependent on existing'radionuclide pathuays to man. The pathways which were examined for these Specifications are:

1) individual inhalation of airborne radionuclides, 2) deposition of radionuclides onto green Icafy e

vegetation with subsequent consdmption by man, and 3) deposition onto grassy areas where milch animals grare with consumption of the milk by' man. 1!cthods for estimating doses to the thyroid via these pathways are described in Draft Regulatory Guide 1.AA.

The offsite location with the highest anticipated thyroid dose rate from radiofodines and radioactive paterial in particulato form with half-lives greater than eight days was determined using on-site meteorological data and the c>.pressions described in Draft Regulatory Guide 1.AA.

Specificatiori 2.4.3.a(2) limits the release rate of radiciodines and-radioactive material in particulate form with half-lives greater than cicht days sn that the corresponding annual thyroid dose via the o

most restrictive pathway is less than 1500 mrem.

l Tor radioiodines and radioactive material in particulate form with-L half-lives greater than eight days, the most re'strictive location 1s-L a

dairy farm located 3700 meters in the N2 direction l-3 3

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(vent K/Q = 4.h 10 sec/m ; stach X/@ 2.5 x1r sce/m ).

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, +,. -.,,.,, +,,,,-

an-,.-.n+---.--w,,-n,nd,,,

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Specification 2.4.3.b establishes upper offsite Icvels for the releases I

of nobic gases and radiciodines and radioactive material in particulate

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form with half-lives greater than eight days at twice the design objective 1

annual quantity during any calendar quarter, or four times the design objective annual quantity during any period of 12 consecutive months.-

h in addition to the limiting conditions for operation of Specifications:

2.4.3.a and 2.4.3.b, the reporting requirements of 2.4.3.c provide that the cause shall be identified whenever the release of gascous offluents exceeds one-half the design objective annual quantity during-nny calendar quarter and that the proposed program of action to reduce such release rates to the design objectives chall be doccribed.

Specification 2.4.3.d and 2.4.3.c are in accordance with Derftn Criterion 64.

Specification 2.4.3.f is intended to monitor the performance of the core.

An increase in the activity levels of gaseous releases may be the re'sult of defective fuel.

Since core performance is of utmost inportance in the resulting doses from accidents, a report must be flied =

within 10 days following the specified increase in gaseous radioactive releases.

Specification 2.4.3.g requires that the primary containment atmosphere roccive treatment for the removal of gaseous _ iodine and particulates prior to its release.

Specification 2.4.3.h requires that hydrogen concentration in'the system shall be monitored at all times.

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Specification 2.4.3.1 provides for reporting release events which, while below the limits of 10 CFR'Part 20, could result in releases higher than the design objectives.

The sampling and tronitoring requirements given unccr Specificat' ion 2.4.4 provide assurance that radioactive materials released in gaseous vaste cffluents are properly controlled and monitored in conformance with the requirements of Design Criteria 60 and 64. Thesc requirements provide the data for the licensee and the Comission to.

cvaluate the plant's performance relative to radioactive unste effluents.

released to the environment.

Reports on the quantitics of radioactive i

materials released in cascous effluents are furnished to the Comission on the basis of Section 5.6.1 of these Technical' Specifications. On the basis of such reports and any additional infomation the 'Co:nission may obtain f rom the licensee or others, the Cor nission may from time I

to time require the licensee to tche such action as the Comission deems appropriate.

The points of relcace to the environment to be monitored in Section 2.4.4 1

include all the monitored relcace points as provided for in Tabic,2.4-4.

2.4.5 _Syecificationn for Solid Wante llandline, and Disposal 11casurements shall be made to determine,or estimate the total a.

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curic quantity and principic radionuclice composition of all radio-active solid vaste shipped offsite; b.

Reports of the radioactive solid waste ship:ichts, voluces, principle radionuclides, and total curic quantity, shall be-submitted in accordance with Section 5.6.1.

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i Bares: The requirements for solid radioactive vaste handling and disposal given under Specification 2.4.5 provide assurance that solid i

radioactive materials stored at the plant and-shipped offsite are packaged in conformance with 10 CTR Part 20, 10 CFR Part 71, and 49 CFR Parts 170-178.

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TABLE 2.41 ilAOl0 ACTIVE LIQUID SAMPLING AfJD ANALY$l$

Detectatde Llovid -*

Samsding Type of Concentrations sovese f requency Activirr Ana'ysis fuCdmila A. Monitor Tank fieleases EachDatch Principal Garnma Emittets S x 10

One Batch / Month Dissolved Gases' 10~8 Weekly Comrosite" Ba La 1/.0,1131 10~'

-St89 5 x 10

6 Monthly Composite' H3 10-8' Gross a 10-'

Ouarterly Composite" St 90 6 x 10

D. Primary Coolant Weekly 1131,1133 10-4 a

'The detectebility limits for activity ana!ysis are based on the technical feasibility and on the potential significance in e the environmtnt of the cuantitics released. For some nuclides, lower detection limits may tc readily achievable,and '

When nuchdes are mcatu ed below the stattd hmits, they should also be reported.

r I 'or tortain mixtures of g3mma emitters, it mcy not be totsible to measure redionuchdes in conctntretions near t' heir I

sensltivity litnits when othcr nuclides are present in the sample 'n much greater concentrations. Under these c.rcum-stances, it will be more appropriate to calculate the concentrations of such radionucl; des using meatus id ratios with those radionuclides which are routinely identified and measured.

" A composite sampie is one in which the Quantity of liquid sampled is proportional to the quantity of liquid v.aste

(;ischargert,

+

1. The power level and cleant.p or purification flow rate at the sarnple time shall also be tsported.

' lor dissolved nobte gases in w:ter, assume a MPC of 4 x 10 SpCi/ml of water.

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f TABLE 2.4 2 lIADIDACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS i

DeteCisble Geseous

$ampling Type of Concentrations Source Frequency tctivity Analysis (mci /m0' Containment Referes Each Release Principal Gamma Emitters 10 4 l

b 4

H3 10 b

D. Enyltonmental Release Points Monthly Principal Gamma Emitters 10 4. c (Gas Samples)

H3 10-0.

Weekly (Charecal Sampic) 1131 10~lU Monthly (Charcoal Sample) 1133.1135 10-10 Wec kly (Particulates)

Principal Gamma Emitters (at least ior Ba.La 140,1131) 10 Monthly Composite' Sr.S9

• 10~ll (Particulato)

Gross a 10~I I.

Ouarterly Composite' Sr.00 10~jj (Perticu'ates) e The above detectatnoty hm-ts for activity ena% sis a<e t,ased on technitet feasibdity and on the potential s'9nibconce in the env'ron-ment of the Quantities f edeawd. f of some riuchoes. fower Ottection hmits may be reMdy achtenable, and when nuctsdes are measured belph the stated l* mats, they should a'so be reDofled.

DAnalyses shef t also te pe<f ormed following tecn ref uehns, startup.or sirviilar operational occurrence which could af ter the misture of f adionVchdes.

I cf or tertain min tures of gamma emitters. it rnay not t>e poss bie toinessure radionuchdes at levels ritar their sensuivity hmits whea other nuchden are present m the samp'e at much highst levils, Unoer thete Ctrtumstances. It wdl be more appfopriate to Calculate the levets of such radionuchdes using observed tat os with those radionuchdes which are measurable.

CIWhen the a<cra;9 dailV C'c's5 FM'00ctiv'ty ve' ease rate etceeds that gwen m ?.4.3.c.(1) or where the steady 4 tate geoss radioaedvity telease rate incremes by (,0*4 over the prev 600s cortc5DOOOlng por.et level steady state release f ate, the nodine arid particulate Cohection device shall be temowd and anah red to cetarmine the snange in iodine 131 anc particulate release rate. The analys's shall be done daily following such chan;e untd it is shown that a pattern esists which can be used to precact the telease rate;stier which it may revtrl to r,ettly sampien; frequency,

'To te representative of the aser:3e Quan teties and concentrat;ons of f adioactive materials in particalate forret relcased in Saseous ef-fluents,sampics should be co>lectcJ *n proporl'on to the rate of flow of the ef fluent stiesm.

4 4

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TABLE 2.4-3 EO! LING WATER REACTOR LIQUID WASTE SYSTEM LOCATION OF PROCESS AND EFFLUENT T40NITORS AND SAfiPLERS REQUIRED BY TECHNICAL SPECIFICATIONS E**85"**"st f*'..

Auto Centrol I Gt75 l

flar' art M to isoff,o,

Cn W e s S. wig,r*

G<oss

' U.sso# W ismop.c Process $tvee*n ce P*fene Polet Afym

• je t* ort +te.w srf,ve, Actrve ry f

Gases A'pha H3 Analyses f

1 Hig'i Purity Waste Sampfe (Test) Tank 8 X

X X

X X

X X

j Floor Drem Waste Samp'e (Test) Tank X

X X

X X

X X

[ Chemica: Waste Sampfe (Test) Tank X

X X

X X

X X

b X

X X

X X

X

'X l

Detergent Waste Cottector Tank Primary Coolant System X

X Liquid Radwaste Discharge Pipe X

X X

Service Water Dischatp Pipe X

X X

Outdoor Str[ren* Tanks (pote<1tiaffy

. radioactive)

X X

X X.

Component Coofing System X

X X

Pgn y w g',ygt,gh,p(gegpuretfYht* Story fney r*Cf bM e eta $W * ('est) tank. TM mass *d f~M Mit be rmstad dwWy to t% We* story 'ersk of 10 th9 %

deFire w.pste s mp?* (test) tank.

V. SaVy?*d. > 'd ** fd*wed F or to te'*s'e t% ovg% the f%f redWase d*x$seja pW. N da'ee9eM b,n e vnt tr.*.11s the contents of '*** &+erynt wnte coffector tank a+= sW i

WJst* syst$tt f**uS! tJe destrJned Wit *1 etther 3 sp!it tank or tWo SepM7*e eO !PCliOrt Of s.W!T e tiestI tJnbs to pent isolat*M Of the 13nh3 for mineetg, savvO eet), enrj attafyseg price to I

?

f

retease, e

a N

l

i f

i~

TABLE 2.4-4 DOf LING WATER REACTOR CASEOUOWASTE SYSTEM LOCATION OF PROCESS AND EFFLUENT MONITORS AND SAMPLERS REQUIRED BY TECHNICALSPECIFICATIONS Cr

• trem.m at hiiation Au*o Coateof to Con %sous

$ m de i

' P ocass Strew oc ff*? ease Point Atarm isot/gm Valve

?.*on et or Statwsn Notge Gas t

Par %ta+e it3 Alphe Condenser / Air Eiector (before gas treatment system)

X X

X X

Offr,as Treatnen* Systen Effluent X

X X

X X

X X

Main Stack X

X X

X X

X X

X Building Ventitation Systems i

Reactor Containment Building

.X -

X X

X X

X X

X

'X Radwaste Buitding" X

X X

X X

X X.

X Turbine Bui! ding toof Vents' X

X X

X X

X Fuel Handfing & Storega Buifding' X

X X

X X

X X

X z

Auxiliary Building

• X X

X X

X X

X X

D Mechanical Vacuum Pump X

X X

X

.X X

X X

t Turbina Gtand Saal Ccndense,b X

X X-X X

X X

X

• f eay o< ett of the tmisdia; v-atitation systems e e rout.d to e sWe re -eee point. tw e-d for e coatiavovs moeite, et the ind.vidi,ar tru.* ding enheust 6schose point to the mairi brJst (fuet it etimma*e-f. One contmu us monitor et the finst re'me @t is sufficieat.

a em boema'If, the offgJses from the mer_hanical WPeuum pumn vet!I tw 6sr}3tffed IMo e Nhe3 der dowwnstreem of the furtpone gfend sp3I Condenser vent, and the need f0F two sy9-tem mon.to.s on exw s,sta.I.5 etninaeed. one continuous menso< st the emat retease point is surt.c.ent.

"W r

Tcbic 2.4-5' GAMMA AND EETA DOSE FACTORS FOR L

l "ontIcello Dese Factors fer Vent Dose Factors for Stack Noble Gas K

L Mv U

iy yy i

gy Kig Li3 M,

N Radien clide Total Body Skin Ecta Air Ca

.a Air Total Body Skin Ecta Air Ca:ma Air g

f3

( C1/nec 1rea/yr )

[ren/yr}

rad /yrT

[ rad /yr rem /yr

\\ rem /yr}

/

/ rad /yr}

radlyrh

\\C1/sec/

Ci/sec)

'CL/sce Ci/sce Ci/sec /

kCi/sec /

Ci/sec)

Kr-83m

-4 2.0 x.10 0

1.6 0.13 2.0 x 10~

0 0.063 5.3 x 10-3

~;

Kr-85m 2.0 8.0 11 2.1 0.59 0.32 0.43 0.62

-3 Kr-85 0.023 7.4 11 0.024 8.6 x 10 0.29 0.43 9.1 x 10-3 Kr-87 6.6 54

'57 6.9 2.5 2.1 2.3 2.7 Kr-88 15 13 16 16 6.3 0.52 0.64 6.6 i

Kr-89 9.4 56 58 9.9 2.1 2.2 2.3 '

2.2 i

(

Xe-131a 0.69 2.6

-6.1 0.89 0.15 0.10 0.24 0.18 Xe-l3'32 0.54 5.5

'8.1 0.75 0.12 0.22 0.33 0.14 -

Xc-133 0.63 1.7 5.8 0.79 0.13 0.067 0.23' O.14

-xe-135m 3.8 3.9

4. 't 4.1 1.2 0.16 0.16 1.3 Xc-135 l_2.9-10 14~

3.0 0.94 0.41 0.54' 0.99 I

.1

^

1

.67 70

.1.2 0.25 2.7 2.8 0.26

[

Ic-137

, o. 7

b i

5.6.2 c.

Nonroutine Radioactive Effluent Reports (1)

BWR Liquid Radioactive Wastes Report.

If the cummulative releases i

of radioactive materials in'11guid effluents, excluding tritium and dissolved gases, should exceed one-half the desfEn objective annual quantity during any calendar quarter, the licensee shall make en-investigation to identify the causes of such releases and define and initiate a program of action to reduce such releases to the design objective levcis.

A written report of these actions shall be sub.

mitted to the NRC within 30 days from the end of the quarter during which the release occurred.

(2)

BWR Cascous Radioactive Wastes Report.

Should the conditions (a),

(b), or (c) listed below exist, the licensee shall make en invcst-igation to identify the causes of the release rates and define and initiate a program of action to reduce the release rates to design objective leveIs.

A written report of these actions shall be sub-mitted-to the NRC within 30 days from the end of the quarter during which the releases occurred.

(a)

If the average release rate of nobic gases for the site during-any calendar quarter exceeds one-half the design obejetive annual quanity.

i (b)

If the average release rate per site of all radioiodines and radioactive materials in particulate form with-half-lives greater than eight days during any calendar quarter exceeds one-half the design objective annual uantit).,

1

U >M N tb

,t 2-(c)

If the amount of iodine-131 released during any calendar quarter is greater than 0.5 Ci/ reactor.

(3)

BUR Unplanned or Uncontrolled. Release Report.

Any unplanned or un-controlled offsite release of radioactive materials in excess of 0.5 Curie in liquid or in excess of 5 Curies of nobic gases or 0.02 Curic nf radioiodines in gaseous form requires notification.

1his notification must be made by a written report within 30 days to the URC.

The report shall describe the event, identify the causes of the unplanned or uncontrolled release and report actions taken to prevent recurrence.

L (4)

BUR Cascous Radioactive Waste Report.

If the gross _ radioactive rate of nobic gases fron the main condenser vacuum systen exceeds 260,000 uCi/sec for a period greater than 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />, a'vritten

-report shall'bc subnitted to the NRC within 10 days, identifying the causes of activity measured downstream of the main condenser vacuum system prior to holdup and at a point upstream of the point of release.

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