ML19347F960

ETS (Radiological for Facility).Nonradiological Environ Protection Plan Encl

ML19347F960
Person / Time
Site:	Trojan File:Portland General Electric icon.png
Issue date:	05/14/1981
From:	Office of Nuclear Reactor Regulation
To:
Shared Package
ML19347F955	List: ML19347F954 ML19347F956 ML19347F960 ML19347F962 ML19347F965
References
NUDOCS 8105260716
Download: ML19347F960 (60)

Text

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APPENDIX B - PART I RADIOLOGICAL ENVIRONMENTAL TECHNICAL FPECIFICATIONS FOR TROJAN hTCLEAR PLA!Tf COLUMBIA COUNTY, OREGON DOCKET NO. 50-344 UNITED STATES NUCLF.AR REGULATORY CC10'.ISSICN OFFICE OF NUCLEAR REACTOR REGULATION m==

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TABI.E OF CONTEITS Page FO REWO RD..........................

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1. 0 LIMITING CONDITIONS FOR OPERATION 1-1 1.1 Radioactive Effluents..................

1-1 1.1.1 Objective...................

1-1 1.1.2 Specifications for Liquid Waste Effluents...

1-2 1.1.3 Specifications for Liquid Waste Sampling and Monitoring.................

1-4 1.1.4 Basis.....................

1-5 1.1.5 Specifications for Caseous Waste Effluents..

1-8 1.1.6 Specifications for Caseous Wasta Sampling and Monitoring.................

1-13 1.1.7 Bases 1-14 1.1.8 Specifications for Solid Waste Handling and Di s po s al..................

1-18 1.1.9 Bases.....................

1-18 2.0 ENVIRCNMENTAL SURVEILLANCE FROGRAMS.............

2-1 2.1 Radiological Environmental Monitoring.

2-1 2.1.1 Applicability.

. 2-1 2.1.2 Objective.

2-1 2.1.3 Specification.

2-1 2.1.4 Reporting Requirement.

2-3 2.1.5 Basis.

. 2-3 2.1.6 References.

2-7 3.0 ADMINISTk _ IVE CONTROLS...................

3-1 3.1 Action to be Taken if an Environmental Limit for Operation is Exceeded................

3-1 l

3. 2 Specification...

3-1 3.3 Action to be Taken if Environmental Surveillance Program Report Levels are Violated..........

3-1 3.2.1 Spe cifica tion.................

3-1 i

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TA3LE OF CONTENTS

2. age, 3.4 Records...........,

3_2 3.4.1 Specification.................

3-2 l

l 3.5 Re po rting Raquirement s................,. 2 l

3.5.1 Routine Re po rts................

3-2 3.5.2 No n-Rou t ine Re po r t s..............

3-3 3.5.3 Csanges....................

3-5 1

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LIST OF TABLES Number Subjece 2-1 Basic Radiological Monitoring Program 2-2 Iocations of ?amples Collection Sites for Radiological Monitoring Program 2-3 Design Objectives for Radionuclide Concentrations in Environmental Samples 2-4 Camme And Beta Dose Factors For Trojan Nuclear Plant 3-1 Radioactive Liquid Sampling And Analysis 3-2 Radioactive caseous Waste Sampling And Analysis 3-3 Pressurized Water Reactor Liquid Waste System location of Process And Effluent Monitors And Samplerf Required By Technical Specifications 3-4 Pressurized Water Reactor Caseous Waste System Location of Process And Effluent Monitors And Samplers Required By Technical Specifications e

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4 RADIOLOGICAL ENVIRONMENTAL TECHNICAL SPECIFICATICNS FOREWORD Theis Technical Specifications define Plant controls and report-ing requirements necessary to assure a minimized Plant impact on the surroundings in accordance with the NEPA environmental review.. The scope of these specifications is in accordance with requirements of 10 CFR 50.50.

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1.0 LIMITING CONDITIONS FCR OPERATION 1.1 Radioactive' Effluents 1.1.1 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 low as are reasonably achievable.

These releases should not result in radiation exposures in ucrestricted areas greater than a fev percent of natural background exposures. The concentrations of radioactive materials in effluents shall be within the limits specified in 10 CFR Part 20.

1 To ensure that the releases of radioactive sacerial above background to unrestricted areas be as low as are reasonably achievable, the following design objectives apply:

For liquid vastes:

a.

The annual dose above background to the total body or any organ of T individual from all reactors at a site should not exceed 5 mram in an v.nrestricted area.

b.

The annual total quantity of radioactive materials in 11guld vaste, excluding tritium and dissolved gases, discharged from each reactor should not exceed 5 C1.

l For gaseous vastes:

l c.

The annual total quar.tity of noble gases above back-ground discharged from the site should result in an

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air dose due to gnama radiation of less than 10 mead, and an air dose due to beta rsdiation of less than 20 mead, at any location near gr.und level which could be occupied by individuals at or beyond the boundary of the site.

d.

The annual total quantity, above background, of all radioiodines and radioactive material in particulate 4

forms with half-lives greater than eight days, from all reactors at a site should not result in an i

l l

annual dose to any organ of an individual in an unrestricted area from all pathways of exposure in excess of 5 mram.

i e.

The annual total quantity of iodine-131 discharged l

from each reactor at a site should not exceed 1 C1.

l 1.1.2 Seecifications for Liquid Waste Effluents a.

The concentration of radioactive materials released in liquid t'asce effluents from all reactors at the site shall not exceed the values specified in 10 CFR part 20, Appendix B, Table II, Column

• 2, for unrestricted areas.

b.

The cumulative release of radioactive materials in liquid waste effluents, excluding tritium and dissolved gases, shall not exceed 10 C1/ reactor /

calendar quarter.

c.

The cumulative release of radioactive materials in liquid waste affluents, excluding tritium and dissolved gases, shall not exceed 20 C1/ reactor in any 12 consecutive menths.

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d.

During release of radioactive vastes, the effluent control monitor shall be set to alarm and to ini-tiate the automatic closure of each waste isolation valve prior to exceeding the limits specified in i

1.1.2.a above.

The operability of each antematic isolation valve, e.

I in the liquid radvaste discharge lines shall be t

demonstrated quarterly.

l i

f.

The equipment installed in the liquid radioactive I

waste system shall be maintain'ed and shall be oper-ated to process radioactive liquid wastes prior to their discharge when the projected cumulative release could exceed 1.25 C1/ reactor / calendar quarter, exclud-ing tritium and dissolved gases.

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g.

The maximum radioactivity to be contained in any liquid radwaste tank that can be discharged directly to the envirens shall not exceed 10 C1, excluding tritium and dissolved gases.

h.

If the cumulative release of radioactive matarials in liquid effluents, excluding tri-tum and dissolved gases, exceeds 2.5 C1/ reactor / calendar quarter, tne i

1 licensee shall make an investigation to identify the causes fer such releases, define and initiate 4 1

program of action to reduce such releases to the design objective. levels listed in Section 1.1, and re port these actions to the NRC in accordance with Specification 3.5.2.a(1).

1.

An unplanned or uncontrolled offsite release or radio-active materials in liquid effluents in excess of 0.5 curies tra-a.res notification. This notification shall be in accordancs with Specification 3.5.2.a(3).

1-3

1.1.3 Specification for Liouid Waste Sampling and !!onitoring a.

Plant records shall be maintained of the radioactive concentration and volume before diluation of liquid waste intended for discharge from mo'nitor tanks 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 3.5.1 of these 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 sanple shall be taken from the batch and analyzed for the concentration of each significant gamma energy peak in accordance with Table 3-1 to demonstrate compliance with Specification 1.1.2 using the flow rate into which the waste is discharged during the period of discharge.

c.

Sampling and analysis of liquid radioactive vaste shall be performed in accordance with Table 3-1.

Prior to taking samples from a sonitoring tank, at lesse two tank volumes of entrained fluid shall be recirculated.

d.

The radioactivity in liquid wastes shall be continu-ously monitored and recorded during release. Whenever these monitors are inoperable for a period not to l

exceed 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, two independent samples of each tank to be discharged shall be analyzed and two plant l

personnel shall independently check valving prior to l

the discharge.

If these monitors 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 1-4 i

waste tank shall be made and any release in progress shall be terminated.

e.

De flow rate of liquid radioactive waste being dis-charged from monitor tanks 'shall be continuously measured and recorded during release.

f.

All. liquid offluent radiation monitors shall be calibrated at least quarterly by means of a radio-active source traceable to the National Bureau of Standards. Each monitor shall also have a functional test monthly a'nd an instrument check prior to making a release.

3 De radioactivity in steam generator blowdown shall be continuously monitored and recorded. De flow race 'shall be determined and logged whenever steam generator blowdown is being discharged to the river.

Wenever the radioactivity monitors are inoperable, the blowdown flow shall not be directly released to the environment.

1.1.4 Basis ne release of radioactive materials in liquid waste effluents to unrestricted areas shall not exceed the concentration limits specified in 10 CFR Part 20 and should be as low as is reasonably achievable in accordance with the requirements of 10 CFR Part 50.36a. Dese specifications provide reasonable assurance that the resulting annual dose to the total body or any organ of an individual in an unrestricted area will not exceed 5 mrem. At the same time, these specifications pernic l

the flexibility of operation, compatible with consideration of health and safety, to assure that the public is provided a dependable scurce of power under unusual operating conditions which may temporarily result in releases higher than the design 1-5

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objective levels but still within the concentration limits specified in 10 CFR Part 20.

It is expected that by using this operational flexibility under unusual operating conditions, and exerting every effort to keep levels of radioactive material in liquid wastes as low as practie=ble, the annual releases will not exceed a small fraction of the concentracion limits specified in 10 CFR Part 20.

The design objectives have been developed based on operating l

experience taking into account a combination of variables including defective fuel, primary system leakage, primary to secondary system leakage, steam generator blowdown and the performance of the various vaste creatment systems, and are consistent with 10 CFR Part 50.36a.

Specification 1.1.2.a requires the licensee to limit to con-centration of radioactive materials in liquid waste effluents released from the site to levels specified in 10 CFR Part 20, Appendix B, Table II, Column 2, for unrestricted areas. This specification provides assurance that no member of the general public will be exposed to liquid containing radioactive mate-rials in excess of limits considered permissible under the Commission's Regulations.

Specifications 1.1.2.b and 1.1.2.c establish the upper limits for the release of radioactive materials in liquid effluents.

The intent of these Specifications is to permit the licenses the flexibility of operation to assure that the public is provided a dependable source of power under unusual operating l

l conditions which may temporarily result in eleases higher than the levels normally achievable when the plant and the liquid waste treatment systems are functioning as designed. Releases of up to these levels will result in concentrations of radio-active material in liquid vaste effluents at small percentages of the limits specified in 10 CFR Part 20.

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Consistent with the requirements of 10 CFR Part 50, Appendix A, Design Criterion 54, Specifications 1.1.2.d and 1.1.2.e require operation of suitable equipment to control and monitor the 4

releases of radioactive materials in liquid t.aates during any period that these releases are taking place.

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Specification 1.1.2.f requires that the licensee maintain and operate the equipmert installed in the liquid vsste sistems to reduce the release of radioactive materials in liquid effluants to as low as is reasonably achievable consistent with the requirements of 10 CFR Part 50.36a. Normal use and naistenance j

of installed equipment in the liquid waste system provides reasonable assurance that the quantity released will not excaed the design objective. In order to keep releases of radioactive materials as low as are reasonably achievable, the specifica-a tion requires operation of equipment whenever it appears that the projected cumulative discharge rate will exceed one-fourth of this design objective annual quantity during any calendar quarter.

Specificatiog 1.1.2.g restricts the amount of radioactive mate-rial that could be inadvertently released to the environment to" an amount that will not exceed the Technical Specification limit.

In addition to limiting conditions for operation listed under Specifications 1.1.2.b and 1.1.2.c the reporting requirements of Specification 1.1.2.h delineate that the licensee shall iden-tify the cause whene,ver the cumulative release of radioactive materials in liquid waste affluents exceeds one-half the design i

objective annual quantity during any calendar quarter and f

describe the proposed program of action to reduce such releases to design objective levels on a timely basis. This report must be filed within 30 days following the calendar quarter in which the release occurred as required by Specification 3.5.2 of j

these Technical Specifications.

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l Specification 1.1.2.1 provides for reporting spillage or release events which, while below the limits of 10 CTR Pa t 20, could result in releases higher than the design objectives.

The sampling and monitoring requirements given under 3pecifica-tion 1.1.3 provide assurance that radioactive materials in liquid wastes are properly controlled and monitored in conform-ance with the requirements of Design Criteria 60 and 64.

These requirements provide the dats for the licensee and the Commis-sion to evaluate the plant's performance relative to radio-

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active liquid uastes released to the environment. Reports on the quantitles of. radioactive materials released in liquid waste effluents are furnished to the Commission according to Section 3.5.1 of these Technical Specifications. On the basis of such reports and any additional information the Commissica may obtain from the licensee or others, the Commission may from l

time to time require the licensee to take such actions as the Commission deems appropriate.

The point of release to the environment to be monitored in I

i Section 1.1.3 include all the monitored release points as provided for in Table 3-3.

I 1.1.5 Soecifications for Caseous Waste Effluents The terms used in these specifications are as follows:

subscripts v, refers to vent releases 1, refers to individual noble gas nuclide (Refer to Table 2-4 for the noble gas nuclides considered)

Q = the total noble gas release rate (C1/sec)

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a

Q sum of the individual noble gas radionuclides

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determined to be present by isotopic analysis E = the average total body dose factor due to gamma emission (rem /yr per Ci/sec) 5 = the average skin dose factor due to beta emissions (res/yr per Ci/sec) 5 = the average air dose factor due to beta emissions (rad /yr per C1/sec) 5 = the average air dose factor due to gamma emissions

-(rad /yr per Ci/sec)

The values of I, E, E and 5 are to be determined each time iso-topic analysis is required as delineated in Specification 1.1.6.

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

Y = (1/Q )

QK 7

gg i

II = (1/Q )

QL 7

gg i

II - (1/Q )

Qu 7

gg i

3 = (1/Q )

QN 7

gg i

where the values of K, L, M and N are provided in Table 2-4, g

g g

g and are site dependent gamma and beta dose factors 1-9

Q = the measured release rate of the radioiodines and radioactive nacerials in particulate forms with half-lives greater than eight days.

a.

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

,i 1 and g(E,+1.di,)

i1 0.33 (2) The release race limit of all radiciodines and radioactive material in particulate form with half-lives greater than eight days, released to the environs as part of the gaseous wastes from the site shall be such that 5

7.9 x 10 Q, i1 b.

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

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11 and 6.3 b i, i1 l

(2) The average release race of noble gases from the site during any 12 consecutive months shall be such that N

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i1 and 13 g i, i1 (3) ne average release race per site of all radio-iodines and radioactive materials in particulate form with half-lives greater than eight days during any calendar quarter shall be sue i that 0

1.1 2.4 x 10 g iI (4) ne average release rate per site of all radio-iodines and radioactive nacerials in particulate form v.'.th half-lives greater than eight days during ray period of 12 consecutive nonths shall be such that 6

25 2.4 x 10 ig (5) ne anount of fodine-131 released during any calendar quartet shall not exceed 2 C1/ reactor.

l (6) ne anount of iodir.e-131 released during any

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period of 12 consecutive nonths shall not exceed j

4 C1/ reactor.

Should any of the conditions of 1.1.5.c(1), (2) or (3) c.

listed below exist, the licensee shall nake an'investi-gation to identify the causes of the release rates, define and initiate a program of action to reduce the release rates to design objective levels listed in Section 1.1,and reporr these actions to the NRC within 30 days from the end of the quarter during which the releases occurred.

1-11 4

(1) If the average release race of noble gases from the site during any calendar quarter is such that 50 Q Y,

>l g7 or (II, 25

<1 (2) If the average release rate per site of all radioiodines and radioactive materials in par-ticulate form with half-lives greater than eight days during any calendar quarter is such that 6

50 2.4 x 10 q yg y

(3) If the amount of iodine-131 released during any calendar quarter is greater than 0.5 C1/

reactor.

d.

During the release of gaseous vastes from the pri=ary system waste gas holdup system the affluent control

=onitor shall be operating and set to alarm and to initiate the automatic closure of the vaste gas dis-charge valve prior to exceeding the limits specified in 1.1.5a above. The operability of each automatic isolation valve listed in Table 3-4 shall be demon-strated quarterly.

e.

The maximum activity to be contained in one vaste gas storage tank shall not exceed 150,000 curies (considered as Ie-133).

b 1-12 V

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l ase of An unplanned or uncontrolled offsite re e I

in radioactive materials in gaseous ef fluents0.02 curie of f.

excess of 5 curies of noble gas or ification.

radiciodine in gaseous form requires not ith This notification shall be in accordance w Specification 3.5.2.a(3).

and Monitoring Soecifications for Caseous L'aste Sampling 1.1.6 rts of the Plant records shall be maintained and repobmitted in accord-sampling analyses results shall be su a.

Esti-ifications.

ance with Section 3.5 of these Specl error associated i

mates of the sampling and analyt cabe included.

with each reported value should from the t

Caseous releases to the environment, excephaust and as note b.

turbine building ventilation ex ly moni--

Specification 1.1.6.c, shall be continuousnd the flow measure tored for gross radioactivity akhenever these monitors are or controlled.

d analyzed daily able, grab samples shall be taken anIf these monitors are for gross radioactivity.

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

the pri=ary During the release of gaseous vastes from oss activity vaste gas holdup system, the gr c.

system collection device, and the monitor, the iodine be operating.

particulate collection device shall l be calibrated All vaste gas effluent monitors shal radioactive at least quarterly by means of a kncvnau of Standards.

d.

source traceable to the National Bure t at least Each monitor shall have a functional tes least daily.

monthly a'nd instrument check at N

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e.

Sampling and analysis of radioactive sacerial in gaseous waste, including particulate forms and radiciodines shall be performed in accordance with Table 3-2.

1.1.7 Bases The release of radioactive materials in gaseous waste efflu-ents to unrestricted areas shall not exceed the concentration limits specified in 10 CTR Part 20 and should be as low as is reasonably achievable in accordance with the requirements of 10 CTR Part 50.364.

Thesa specifications provide reasonable assurance that the resulting annual air dose from the site due to gamma radiation will not exceed 10 mrad, and an annual air dose from the site due to beta radiation will not exceed 20 mrad from the noble gases, that no individual in an unrestricted area vill receive an annual skin dose greater than 15 mrem from fission product noble gases, and that the annual dose to any organ of an individual from radioiodines an>! radioactive material in particulate form with half-lives greater than eight days will not exceed 15 mres per site.

The ASL3 took notice of the arrangeeent =ade between the intervenor and the applicant. The Staff's position is that the annual dose to an individual from iodine and particulates should not exceed 15 mres. Even though the numerical values of the Staff's design objectives and those in these Technical Specifications are different, at the request of the applicant the lower limit of 5 area per year has been imposed. At the same time these specifications permit the flexibility of operation, compatible with considerations of health and safety, to assure that the public is provided with a dependable source of power under unusual operating conditions which may tempo-rarily result in releases higher than the design objective levels but still within the concentration limits specified in 1-14

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i 10 CTR Part 20.

Even with this operational flexibility under 4

unusual operating conditions, if the licensee exerts every effort to keep levels of radioactive sacerial in gaseous waste effluents as low as practicable, the annual releases will not exceed a small fraction of the concentration limits specified in 10 CFR Part 20.

The design objectives have been developed based on operating

• experience taking into account a combination of system vari-ables including defective fuel, primary system leakage, primary to secondary system leakage, steam generator blevdown and the perfor=ance of the various waste treatment systems.

Specification 1.1.5.a(1) limits the release rate of noble gases from the site so that the corresponding annual gacma and beta dose race above background to an individual in an unrestricted area vill not exceed 500 mrom to the total body or 3000 ares to the skin in compliance with the limits of 10 CFR Part 20.

Por Specificacic : 1.1.5.a(1), gamma and beta dose factors for the individual noble gas radionuclides have been calculated for the plant gaseous release points and are provided in Table 1-5.

The expressions used to calculate these dose factors are based on dose models derived in Section 7 of Meteorology, and Atomic Energy-1968 and model techniques provided in Draf t Regulatory Guide 1. AA.

Dese calculations have been made to determine the site boundary location with the highest anticipated dose race from noble gases using onsite meteorological data and the dose expressions provided in Draf t Regulatory Guide 1. AA.

The dose expression considers the release point location, building waka effects, and the physical characteristics of the radionuclides.

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The offsite location with the highest anticipated annual dose from released noble gases in 662 meters in the north direction (vent X/Q = 1.3 x 10-5,,,j,3),

The release rate Specifications for a radioiodine and radio-active material in particulate form with half-lives greater than eight days are dependent on existing radionuclide pathways to man. The pathways which were examined for these Specifica-tions are: 1) individual inhalation of airborne radionuclides,

2) deposition of radionuclides onto green leafy vegetation with subsequent consumption by man, and 3) deposition onto grassy areas where milch animals gra:e with consumption of the milk by man. Methods for estimating doses to the thyroid via these pathways are described in Draf t Regulatory Guide 1. AA.

The offsite location with the highest anticipated thyroid dose rate from radiciodines and radioactive material in particulate form with half-lives greater than eight days was determined using onsite meteorological data and tha expressions described in Draf t Regulatory Guide 1. AA.

Specification 1.1.5.a(2) limits the release rate of radio-1 iodines and radioactive material in particulate form with half-lives greater than eight days so that the corresponding annual thyroid dose via the most restrictive pathway is less chan 1500 mrem.

For radioiodines and radioactive material in particulate form with half-lives greater than eight days, the most restrictive location is a dairy farm located 3200 meters in the south

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direction (vent X/Q = 2.2 x 10 sec/m ).

Specification 1.1.5.b establishes upper offsite levels for the releases of noble gases and radioiodines and radioactive mate-rial in particulate form with half-lives greater than eight days at twice the design objective annual quantity during any calen-dar quarter, or four times the design objective ataual quantity 1-16

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e during any period of 12 consecutive months.

In addition to the limiting conditions for operation of Specifications 1.1.5.a and 1.1.5.b, the reporting requirements of 1.1.5.c' provide that the cause shall be identified whenever the release of gaseous effluents exceeds one-half the design objective annual quantity during any calendar quarter and that the proposed program of action to reduce such release ratas to the design objectives shall be described..

Specification 1.1.5.d requres that suitable equipment to noniter and control the radioactive gaseous releases are operating during any period these releases are taking place.

Specification 1.1.5.e limits the maximum quantity of radio-active gas that can be contained in a waste gas storage tank.

The calculation of this quantity should assume instantaneous ground release, a X/Q based 15 percent meteorology, the average gross energy is 0.19 Mev per disintegration (considering Xe-133 to be the principal emitter) at exposure occurring at the minimum site boundary radius using a semi-infinite cloud model.

The calculated quantity will limit the offsite dose above wackground to 0.5 rem or less, consistent with Commission guidelines.

Specification 1.1.5.f 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 monitoring requirements given under Specifi-cation 1.1.6 provide assurance that radioactive materials l

released in gaseous waste affluents are properly controlled and nonitored in confor=ance with the requirements of Design Criteria 60 and 64 Thes2 requiremanes provide the data for the licensee and the Cor;..tsarn to evaluate the plant's per-formance relative te **>; tctA<a waste ef fluents released to the environment.

,c se the quantities of radioactive 1-17 4

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=aterials released in gaseous effluents are furnished to the Commission on the basis of Section 3.5.1 of these Technical Specifications. On the basis of such reports and any addi-tional information the Commission may obtain free the licensee -

or others, the Commission may from time to time require the licenses to take si i action as the Commission deems appropriate.

The points of release to the environment to be monitored in Section 1.1.6 include the monitored release points as provided for in Table 3-4 Specification 1.1.6.b excludes monitoring the turbine building ventilation exhaust since this release is expected to be a negligible release point. Many PWR reactors do not have turbine building enclosures. To be consistent in this require-nent for all PWR reactors, the monitoring of gaseous releases from turbine building is not required.

1.1.8 Seecifications for Solid Waste Handling and Discosal a.

Measurements shall be made to decernine or estimate the total curie quantity and pr..nciple radionuclide composition of all radioactive solid vaste shipped offsite.

b.

Reports of the radioaccive solid vaste shipments, volumes, principle radionuclides, and total curie quantity, shall be submitted in accordsnee with Section 3.5.1.

1.1.9 Bases The requirements for solid radioactive waste handling and disposal given under Specification 1.1.8 provide assurance that.

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

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2.0 ENVIRONMENTAL SURVEILLANCE PROGRAMS 2.1 Radiological Environmental Monitoring 2.1.1 Applicability Applies to radiological monitoring outside the Plant security fence for the purpose of establishing population dose.

2.1.2 Obiective The objective of the radiological monitoring program is to quantify concentrations of radioactive materials and direct radiation levels in the Plant environs in order to verify that as a result of Plant operations, persons in unrestricted areas are not exposed to concentrations of radioactive materials or radiation levels greater than those specified in 10 CFR 20.

In addition, these measurements will provide assurance that offsite doses resulting from radioactive materials in Plant effluents are as low as practicable.

2.1.3 Specification The basic program of sample collection, sample a.

analyses and radiation dose measurements shall be conducted in accordance with Table 2-1.

Milk samples shall be obtained monthly from the dairy animals

-located at 2.0 miles south-southwest of the Plant (location 17A, Figure 3-1).

If the required milk samples cannot be obtained by 2-1

the licensee, the licensee shall certify this condi-tion in writing to the Director, Division of Licensing.

If the milk-producing animal is at this location and the licensee cannct obtain the required samples, the licensee shall sciple green forage monthly, as close as possible to this location.

However, if the milk producing animal (or animals) is no longer located at 2.0 miles south-southwest of the Plant, the licensee shall obtain monthly milk sanples from the milk-producing animals actually in the area of' highest dose potential.

b.

The gross beta and alpha radioactivity analyses, as well as the I-131 analyses in silk, listed in Iable 2-1 shall be initiated within eight days after the samples are collected.

c.

For I-131 activity levels in milk at or above 0.5 pC1/1, the overall error (one sigma confidence level) of the analysis shall be within + 25%. The analytical detection limits listed in Table 2-1 shall apply to the date of sample collection.

d.

Sample collections and radiation measurements required to meet the schedule given in Table 2-1 shall be conducted at locatic ns which are identified in Table 2-2 and Figures 3-1 and 3-2.

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e.

Deviations are permitted from the required sampling schedule if biological specimens are not obtained or if due to the malfunction of an automatic sampler.

If the latter, corrective actions shall be completed prior to the end of the next sampling period. All 2-2 e

deviations from the sampling schedule shall be described in the semiannual reports.

f.

A continual awareness shall be maintained of the

' locations of individual alik cows and goats, and dairy farms within a five-mile radius of the Plant.

If goats are being milked for human consumptica, the milk will be sampled and analyzed as available. The results of this surveillance program will be reported on an annual basis.

If estimated annual thyroid-doses resulting from the consumption of milk produced at the identified locations exceed 5 mrem /yr based on measured releases of radioiodine in gaseous efflu-eat and annual average meteorological dispersion, the location of highest estimated dose vill be added to the milk sampling schedule of Table 2-1.

2.1.4 Reporting Requirements.

If concentrations of radioactive materials in envirocmental samples at individual sampling locations, when averaged over a calendar quarter, exced those values set forth in Table 2-3, a determination vill be mee to identify whether such concentra-tions are attributable to Plant operation.

If attributable to Plant operation, a report will be submitted to the Director of Licensing in accordance with reporting requirements cited in Section 3.5.2.b.

If not attributable to Plant operation, the rationale for this conclusion shall be included in the annual re po rt.

2.1.5 Basis Sample types included in the radiological monitoring program correspond to those which, if ingested or contacted externally, would result in human exposure from their radioactivity.

Sample frequency is such that both short-term changes from 2-3

intermittent releases and long-term accumulations from continu-ous low-level releases will be' detected. Sampling locations are appropriate for identifying the source of radioactivity in the environment. Analyses selected will ensure detection of all nuclides of significance which are.potentially contained in

~

liquid gaseous effluents. Analytical detection limits are as low as practical, and are sufficient to ensure that doses to the whole body and individual body organs of the highest exposed offsite individuals which are attributable to Plant operation are less than 5 mrem /yr.

Specification a) sets forth a mininum program of environmental

~

radiological surveillance to be conducted during reactor operation. This minimum program is less comprehensive than the preoperational monitoring program described in the Trojan l

Environmental Report and the Trojan FSAR, and reflects experience gained during the preoperational program. The sampling sites and sample types of the required monitoring program set forth in Table 2-1 correspond to those included in the precoerational program.

The analytical detection limits given in Table 2-1 are based on the practicability of routine radioactivity measurement tech-niques, and in all cases will be sufficient to quantify radio-nucilde concentrations which would result in conservatively estimated whole body and individual organ doses of 5 mrem /yr, l

as indicated in Table 2-3.

The detection limits for gamma spectrometric analyses are based on the detectability of 100 pC1/ sample / isotope, by either NaI or Celi techniques, and the analysis of the following mass of samples:

3 Air 300 m Water 41 F. ilk 21 s

2-4

i o

Soil 1 kg dry Terrestrial vegetation 2 kg wet Terrestrial Animals 2 kg wet All other Biota 1 kg vec The detection limits for gross beta and gross alpha radioactiv-icyanalysisarebasedonthedetectabilityof0.5pCI/ sample using low background beta and alpha counting techniques, and the analysis of the following mass of samples:

3 Air 300 m Water 11 bu I g dq Biota 5 g we t The detection limits for Sr-89 and Sr-90 are based on the cetectability of 0.5 pC1/ sample / isotope by a radiochemical separation and subsequent low background beta counting, and the analysis of the following mass of samples:

Milk 0.5 1 Soil 50 g dry Terrestrial vegetation 0.5 kg vet All other Biota 0.1 kg wet The detection limit for I-131 in milk is based on the detect-ability of 0.5 pC1/ sample by a radiochemical separation and subsequent low background beta counting, and the analysis of one liter of milk.

Specification b) ensures that unidentified radionuclides having short half-lives; eg, I-131, will be detected by gross radio-activity measurements, by minimizing radioactive decay between sample collection and analysis.

2-5

~

~

O

=

Specification c) ensures that Os analytical detection limits are adequate for dose estimation at 5 mrem /yr levels, under the assumption that no radioactive decay occurs between crop har-vest, fish catch, water withdrawal, etc., and human consumption or external exposure.

Specification d) requires that a consistent set of locations be sasoled, and that these locations carespond insofar as is practicable with those included in the preoperational monitoring.

program.

Specification e) will permi: deviations from the required-sampling program during circumstances which are beyond the control of monitoring personnel.

Specification f) requires a continus1 assessment of the poten-tially 'important environmental exposure pathway involving the transfer of radioiodine, into the slik of cows gra:ing on open pasture.

The reporting requirement and supporting report levels set forth 'n Table 2-3 require quarterly reporting of radionuclide concentrations in environmental nedia at levels which, if sustained, would result in offsite doses in excess of 5 mren/yr.

The derivation of the report levels given in Table 2-3 corre-spend with the method of assessing offsite doses from radio-active materials in estimated gaseous and liquid affluents at Trojan 3,4, and is consistent with the recommendations of the Federal Radiation Council 5 and the Internacional Commission on Radiological Protection 6.

The following rates of consump-tion of various dietary items by the maximum exposed offsite l

individual have been assumed:

Water 2200 al/ day Milk 1000 al/ day i

1 2-6

Meat 200 g/ day Fish 50 g/ day Vegetables 200 g/ day 3

The breathing rate of an adult has been taken to be 20 m / day 3

and that for an infant to be 3 3 / day.

It has been assumed that an individual spends 4380 hr/yr out-of-doors and 500 hr/yr at shoreline locations.

Report levels for certain gross beta and gross alpha radio-activity naasurenents must of necessity be based on preopera-tional radioactivity levels because of the signifiant natural radioactivity content of these sanples.

The radiological nonitoring pr: gram will integrate fully with ongoing programs of the States of Oregon and Washington.

Quality assurance is achieved in part by a semiannual program of split sample analysis with the two state agencies and by participation in the EPA analytical quality assurance program.

Table 2-2 implenents condition (v) of the Initial Decision dated February 4, 1974. -Specification 2.2.3.f inple=ents condition (vi).

216 References 1.

ASER, Section 5.2.

2.

FSAR, Section 11.6.

3.

FSAR, Section 11.2.

4.

FSAR, Section 11.3.

l 2-7 I

[

4

5.

Federal Radiation Council, background nacerial for the Development of Radiation Protection Standards, Report 2 (1961).

6.

International Commission on Radiological Protection, report of Committee II on Permissible Dose for Internal Radiation, Publication 2 (1959).

u I

4 h

2-8 i

J

• A31.E 2-1 BASIC RADICLOGICAI. MONITC1 TING FROC2Rt Ramber of Analytical Detection *l Samoling Stations famole ? vee Freousnev Analysis 1.isit Onsite Offsite Terrestrial semples A;r Particulate Weekly Cross Beta 0.002 pC1/m3 2

6 Monthly Composite Cross Alp 0.002 pC1/m3 2

4 Comme Scan' O.3 pC1/m3/ isotope 2

4 Air Radiciodine Usekly I-131 0.1 pC1/m3 2

4 01 rect Radiation Q4arterly LD 1.23 mram/ quarter incrasse 8

10 Rainfall Monthly Cross 3 eta 0.3 pC1/1 1

2 Tritian 1000 pC1/1 1

2 I

G===

Scan

• 23 pC1/1/ isotope 1

2 Soil Semiannually Sr-89. St-90 0.01 pei/s (dry) 3 3

%==

Scan 50 pC1/kg/ isotope (vet) 3 3

Vegetation sesiannually Sr-89, Sr-90 3 pci/kg (wet) 2 3

Casas Scan 30 pC1/kg/ isotope (wet) 2 3

An11als

$esiannually

$r-89, $r=90 3 pC1/kg (wet) 2 3

Cacas Scan 30 pC1/kg/ isotope (wet) 2 3

S{IdI Man'hly St-69, Sr-90 1.0 pC1/1 0

Milk t

d]

I-131 0.3 pC1/1 0

5 Canaa $can 50 pC1/1/ isotope 0

3'dl A4ustic Samplea surface Veter Monthly Cross Beta 0.3 pC1/1 3

3 Tritium 1000 pC1/1 3

3 Caana Scan *I 25 pC1/1/ isotope 3

3 I

Well Water Qaarterly Cross Sete 0.3 pC1/1 3

Tritisen 1000 pC1/1 3

Caama Scan *I 25 pC1/1/ isotope 3

I Botton Sediment Sesiannually Canaa scan 0.1 pC1/3/isocepe (dry) 3 3

shoreline soil semiannually Camma scan 0.1 pC1/g/ isotope (dt7) 0 3

vegetation 3esiannua117 sr-ef, sr-90 5 pci/kg (wet) 2 3

I Cassa Scan 100 pC1/kg/ isotope (.et) 2 3

l Fish Samiannusily Sr-89, Sr-90

$ pci/kg (wet) 2 3

Camma Scan 100 pC1/kg/ isotope (vet) 2 3

[a] Analytical detection limit is defined bare as that conc entration that la three standard deviatiota above the everage concentration in a blank sample, and assures accuracy limits of +233.

3 (b) To be performed if groes beta exceeds 0.1 pC1/m.

(c] To be performed if gross beta exceeds 10 pC1/1.

[dl Includes one sample from a local milk processor (Standard Osiry. Isegvirv).

W W

e TABLE 2-2 LOCATIONS OF SAMPLZS COLIICTION SITES FCE RADIOLOGICAL MONITORLM FECCIAM Radial (s)

Radial (s)

Elevation Sample (b)

Site Mileese Direettoo (Feet) 1.a titude Longitude Types 1A Trojan Site 0.75 NW 20 4'

02' 52" 122' 53' 46*

b,d, h,j,1.s la Trojan Site 0.47 V

20 4*

02' 22*

122' 33' 38" b,b.j IC Trojan Site 0.65 su 60 46*

01' 58" 122' 53' 32" b,h 1D Trojaa Site 0.68 5

20 M*

01' $2" 122' 53' 09" h j,1.m 11 Trojan Site 0.75 5

20 46*

01' 49" 122' 53' 03*

b IF Trojan Site 0.48 S

20 46*

02' 01" 122' 53' 00*

a,b,c d.e IC Trojan ::ite 0.06 E

10 4*

02'25-122' 52' 56" i

15 Trojan Site 0.20 N

60 46*

02' 37*

122' 53' 03*

a,b 12 Trojan Site 0.56 NNW 20 46' 02' 54" 12 2 ' 53' 21*

a,b d.e IJ Trojan Site 0.60 NNW 20 46' 02' 57*

122* 53' 20*

b 2 tainier 3.84 NNW 25 46' 05' 22" 12 2

• 55' 51" b,e 3 Lindbe rg 1.96 nv 185 46' 04' 04

• 122 ' 53' 53*

b,d e,i 4A Prescott 0.56 NNW 20 46*

02' 54*

122' 53' 21" h

4C Frescott 1.33 NNW 200 46' 03' 31*

122' 53' 46*

b 5 Neer City 1.40 sv 725 46*

01' 44" 122' 54' 29*

a,b,d.e 63 Coble 1.28 Ssz 120 46*

01' 21" 122 ' 52' 42*

a,b.i 6c Coble 1.71 SW 48 0 4'

01' 24*

122' $4' 37*

h 7 Shiloh Basin 5.76 SW 400 45* 58' 29*

122' 57' 43*

b,3 8 Deer Island 6.72 5

25 45' 56' 40*

122' 51' 27*

b,d e 95 Woodland 11.1 SSE 20 45' 54' 18*

122' 45' 20*

b,c 10 talama 2.98 st 10 4*

00' 22*

122' 50' 41" b

11A ralama 0.69 ESE 10 4*

02' 01" 122' 52' 14*

b 218 Kalass tiver 1.44 E

20 46*

02' 37*

122' 51' 14*

a,b d.

i 12 Carrolla Bluff 1.78 NNE 150 4*

03' 50" 122' 51' 55" b

13 Vision Acres 3.35 NNE 80 46*

05' 16*

122' 52' 00*

b A4 tongview 7.83 NNW 10 46*

08' 57*

122' 56' 21" a,b 65 Totes Pole Dairy 13.6 NW 10 46

• 10' 33*

123' 05' 0)*

3 16 Smith Dairy 11.1 SSE 20 45* $4' 05" 122' 46' 08" f,g,1 17A Kandle Dairy 2.0 SSW 180 46*

00' 45*

12 2' 53' 30*

3.f A8 Standard Dairy-

--7.7 -

NNW 20 -

4*

08' 35*

122* - 55' 10" g --

19 Portland 37.5 3

280 45' 30' 50*

122' 40' 45' a

C01.ITMBIA RITTR SAMFLES Columbia cess-W.ter River Sectional Depth Sampit Site M11 ease Location (Feet) 1.atitude lacritude Types Cal tainier 68.3 West 30 46*

05' 26" 122' 55' 47" kol CRIA 4.6 West 30 46' 06' 02" 122' 57' 04" a

C12 Lindberg 69.6 West

• 13 4'

04' 44*

122' 54' 12" j,h C13 Trojan 72.4 Ves t 30 4'

02' 28" 122' 52' M*

h,j,k.1,a C16 E41ana 75.2 East 40 4*

00' 26*

122* 51' 00*

j,h C15 Voodland 81.5 East 40 45' 55' 10*

122' 48'

1)

• k,1,a (a) Measured f rom the Trojan Containment (b) Sample designations:

Terrestrial samples:

Aquatic aaspleet a Air particulate & radiciodine h Surface water b Direct radiation i Well water c Rainfall j Bottom sediment d Soil k Shoreline soil e Vegetation 1 Yegetation f Animals a Fish a Milk

• s-F

=

a t 2-3 DESIGN 08.*ECTIVZ3 TOR RADIONUCLI3E C0f;CENTRATIONS IN DNIRotetE.WAL SMtP!.E3 Tetreatrtal Aquat$e Heat Fish vege tatios Soil Sediment Vater Milk (pci/kg)

(pci/kg)

(pci/kg)

(pC1/3)

(pC1/3)

Air Nuclide (pC1/1)

(pC1/1)

Vet Uet Ve t Drv Dev (pC1/a3) 5-3 3 x 10' M4 NA NA NA ~

NA NA M

3r-69 NA 2 x 101 1 x 102 4

go2 1

102 sst gA xA St-90 NA 2 x 100 1 x 101 4 x 101 1 x 101 SSI NA NA camas Taitters:

Cr-51 7 x 103 2 x 10' 7 x 10' 3 z 105 a

104 4

gol 3 x 102 3

102 Ma-54 3 x 102 7 102 4

103 1

1o4 4 x 103 1

100 g a gol 3

100 Mn-56 3 x 102 7 go2 a s 1o3 g a go4 4

to3 7

go-1 6 x 100 7 x 101 Te-59 2 x 102 3 x 102 2 x 103 9 s 103 2 x 103 1 x 100 9 z 100 7 x 100 co-58 3 x 102 7: 102 4

103 g a goe 4

go3 g

100 1 x 101 7 x 100 Co-60 2 x 102 4

go2 2 x 103 7 x 103 2 x 103 5

10-1 4 x 100 g a 100 2n-65 3 x 102 7 a 102 4 x 103 1 x 10'

& z 103 2 x 100 2 x 101 7 x 100 Zr-95 2 x 102 5 x 102 2x 103 9 x 103 2 103 5 x 10-1 4 x 100 3 x 100 Mo-99 7 x 102 2 x 103 7x 103 3

10' 8 x 103 9 x 100 8 x 101 2 x 101 Ru-103 3 x 102 6 x 102 3 103 1

104 3 103 2 x 100 2 x 101 1 x 101 Ru-106 3 x 101 7 x 101 4 x 102 1

103 4 to2 4

goo 4

gol 7

10-1 I-131 3 x 10lI*I 8 x 10-1 5 x 10lI*I 2 x 102 5 x 10lI*I 3 x 100 2 x 101 3 x 10-1 Ca-134 3 x 101 7 x 101 4 x 102 1

103 4: go2 y

10-1 6 x 100 g a 100 Ca-137 7 x 101 2 x 102 7: 302 3: 103 3

go2 2 x 100 2 x 101 2 x 100 Ba-140 1 x 102 2 x 102 g a go3 4

go3 1

103 4: go-1 4

100 3: goo Ce-141 3 x 102 7 a 102 1 103 g

104 3 x 103 1 x 101 1 z 102 2 x 101 Ce-144 3 x 101 7 x 101 4 x 102 g a 103 4 x 102 2 x 101 2 x 102 5 x 10-1 Crose Beta 9 x 10.g[b] SSI SSI SSI

$$I SSI S3I 1 x 10.g[b]

0I'I S$3I

$$I SSI

$5I SSI SSI 1 x 10-2[a]

Cross Alpha 9 x 10

[a] Saeed on minimum practicable detection limit.

st

[b] Sased on design' objective for St-90, which is not routinely analysed.

[c] Sased on design objective for Pu-239, whian is not routinely analysed.

NA - Not analyzed routinely.

$$2 - Statistically significant increase above average concentration determined during ;reoperational monitoring program (E + 3e). Yalues to be specified upon completion of preoperational monitoring program.

r O

TABLE 2-4 GAMMA AND BETA DOSE FACTORS FOR TROJAN NUCLEAR PLtNT Dose Factors for Vent Kiy Liv My Niy i

Total Body Skin Beta Air Gamma Air Noble Gas rem /yr res/yr rad /yr Radionuclide C1/sec) gC1/see) gC1/see) grad /yr)

C1/see Kr-83m 5.6 x 10-4 0

3.9 0.34 Kr-853 5.5 20 26

5. 8 Kr-d5 0.064 18 26 0.068 Kr-87 18 130 140 19 Kr-88 42 32 39 45 Kr-89 13 140 140 14 Xa-131m

2. 0

6. 4 15

2. 6 Ia-133m

1. 6 13 20

2. 2 Xa-133

1. 8 4.1 14

2. 3 Ia-135m 8.I 9.5 9.9 9.0 s

Ia-13!

8.1 25 33

8. 6 Ia-137

1. 6 160 170

1. 7 Xa-138 20 55 64 21 h

~

emo----

,.o_

~.

s

3.0 ADMINISTRATIVE CONTROLS 3.1 Action to Be Taken if a Limiting condition for Operation is Exceeded 3.2 Specification a.

Any occurrence of exceeding a limiting condition for operation shall be reported immediately to and investi-gated by the Plant General Manager or persons designated by him.

b.

The Plant Review Board shall review and prepare a rertre for each occurrence. This report shall, include an evaluation of the cause of the occurrence and recommendations to prevent a recurrence.

c.

The Plant General Manager or designated alternate shall forward reports and evaluations of each cccurrence prepared by the Plant Review Board to the Nuclear Operations Board.

d.

The Plant General Manager shall notify the Director, NRC Region V of each occurrence, by telephone and telegraph, within 24 hr. of the occurrence. A written report shall be submitted within one week of the occurrence to the Director, NRC Region V (copy to Director, Division of Licensing).

i 3.3 Action to be Taken if Environmental Surve'.11ance Program Re > ort Lavels are Violated 3.3.1 Specification a.

In the event that report levels as described in Section 2 are reached, the Plant Review l

l e

3-1 l

4

Board shall review the data and prepare a report, including recommendations, to the Nuclear Operations Board.

b.

The Plant General Manager shall notify by written report the Director, NRC Region V (copy to Director, Division of Licensing), including data summary and analysis. This report shall be submitted within 30 days of the identification of the violation.

~

3.4 Records 3.4.1 Specification All records of data collected in conformance with these Technical Specifications including strip charts, chemical analysis resulta, and other documentation of monitoring activities shall be retained for the life -of the -facility. --

3.5 Reporting Requirements _

3.5.1 Routine Reports a.

Environmental Radiological Surveillance Recort A report on environmental surveillance programs for the previous year of operation shall be submitted prior to April 1 of each year.

The report shall be a summary and interpretation of che results of the environmental activitics for the previous year, including a comparison with preoperational studies, and an assessment of the observed impacts of the plant operation on the environment.

3-2

b.

Radioactive Effluent' Release Raoort A report on the radioactive discharge released from

.the unit during the previous six months of opera-tion shall be submitted to the Director, Office of Inspection and Enforcement, Region V (with a copy to the Director of Nuclear Reactor Regulation) within 60 days af ter January 1 and July 1 of each' year. The report shall include a summary of the quantities of radioactive 11guld and gaseous efflu-ents and solid waste released from the unit as out-lined in NRC Regulatory Guide 1.21,. Revision 1, issued June 1974, ~&asuring, Evaluating, and Report-ing Radioactivity in Solid Wastes and Releases of Radioactive hearials in Liquid and Gaseous Efflu-ents from Light-Water-Cooled Nuclear Power Plants",

with data summarized on a quarterly basis following the format of the Regulatory Guide.

3.5.2 Non-Routine Reports l

I a.

Radioactive Discharge l

(1) PWR Liquid Radioactive Wastes Report.

If the cumulative releases of radioactive mate-rial in 11guld effluents, excluding tritium and dissolved gases, should exceed one-half the design objective annual quantity during any calendar quarter, the licensee shall make an investigation to identify the causes of such releases and define any initiate a pro-

[

gram of action to reduce such releases to the I

I design objective levels. A written report of these actions shall be submitted to the NRC within 30 days from the end of the quarter during which the release occurred.

3-3 I

w w

=-

(2) FWR gaseous Radioactive Wastes Report. Should the conditions (a), (b), or (c) listed below exist, the licensee shall make an investiga-tion to identify the causes of the release rates and define and initiate a program of action to reduce the release rates to design objective levels. A written report of these actions shall be submitted to the NRC within' 30 days from the end of the quarter during which the releases occurred.

(a)

If the average release rate of noble gases for the site during any calendar quarter exceeds one-half the design objective annual quarterly.

(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 s

one-half the design objectives annual quantity.

(c) 7.f the enount of iodine-131 released during ar.y calendar quarter is greater than 0.5 C1/ reactor.

(3) PWR Unplanned or Uncontrolled Release Report.

Any unplanned or uncontrolled.offsite release of radioactive materials in excess of 0.5 curie in liquid or in excess of 5 curies of noble gases or 0.02 curies of radiciodines in gas-ecus form requires notification. This noci-fication must be made by a written reporr

'n 3-4 N~

' ~ ~ ~~

' T:2

~~

~~

within 30 days to the NRC.

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

b.

Radiological Environmental Monitoring 1

(1) If a measured level of radioactivity in "impor-tant pathway environmental medium samples"*

indicates that the resultant annual dose to an individual from these levels could equal or exceed 4 or 8 times ** the design objectives given in Table 2-3, a plan will be submitted within one week advising the NRC of the pro-posed action to ensure the plant related annual doses will be within the design objective.

(2) If samples of critical pathway environmental media collected over a calendar quarter show total levels of radioactivity that could result in accumulated plant related doses to g

an individual for that quarter of 1/2 the annual design objectiva, the results shall be reported and a plan submitted and implemented within 30 days to limit conditions so that the annual dose to an individual vill not exceed the design objective.

3.s.3 Changes a.

A report shall be made to the NRC prior to implementa-l tion of a change in plant design, in plant operation, As identified by the AEC Staff in the environmental statement.

Four times the design objective for doses received from ingestion of radiciodine and doses received from submersion in noble gases.

For all other pathways, eight times the design objective is the action level.

3-5 7 --

o or in procedures if the change would have a significant adverse effect on the environment

o. involves an environmental matter or question not previously reviewed and evaluated by the NRC.

The report shall include a description and eval-uation of the change and a supporting justification.

b.

Request for changes in environmental technical speci-fications shall be submitted to the Director of Nuclear Reactor Regulation for review and authoriza-tion.

The request shall include an evaluation of the impact of the change and a supporting justifica-tion.

I 3-6 j

l

- -.. +,

5

Sheet 1 of 2 1

3BLE 3-1 RADI0 ACTIVE LIQUID CAMPLING AND ANALYSIS Detectable Sampling Type of Liouid Source' Frequency Activity Analysis

~ Concentrations (uC1/ml)(*}

A.

Monitor Tank Each Batch Principal Gamma Emitters

- 5 x 10-7[b]

Releases III 10-3 One Batch / Month Dissolved Gases Weekly Ba-I.a-140, I-131 10-6 Compesite "I I

Monthly H-3 10-5 Composite "I I

Groas a 10-7 QuarterlyI"I Sr-89 5 x 10-8 Composite Sr-90 5 x 10-8 B.

Primary Weekly [d]

I-131 I-133 10-6 i

Coolant l

C.

Steam Weekly "I Principal Gamma Emitters 5 x 10-7(b]

I l

Cenerato r Blowdown Ba-I4-140, I-131 10-6 III 10-5 One Sample /

Dissolved Cases Month l

Monthly H-3 10-5 Composite *I I

Gross a 10-7 QuarterlyI St-89 5 x 10-8 Composits *I Sr-90 5 x 10-3 See Sheet 2 of 2 for footnotes.

l

. -,... -._.__.-.-.------..--~j

~ - - -

Sheet 2 of 2 TABLE 3-1 (Cont'd)

[a] The detectability limits for activity analysis are based on the technical feasibility and on the potential significance in the environment of the quantities released. For some nuclides, lower detection limits may be readily achievable, and when nuclides are measured below the stated limits, they should also be reported.

(b] For certain mixtures of gamma emitters, it may not be possible to measure radionuclides in concentrations near their sensitivity limits when other nuclides are present in the sample in much greater concentrations. Under these circumstances, it will be more appropriate to calculate the concentra-i tions of such radionuclides using measured ratios with those radionuclides which are routinely identified and measured.

(c] A composite sample is one in which the quantity of liquid sampled is proportional to the quantity of 11guld waste discharged.

(d] The power level and cleanup or purification flow rate at the sample time i

shall also be reported.

(e] To be representative of the average quantities and concentrations of radio-active materials in liquid effluents, samples should be collected in pro-portion to the rate of flow of the effluent stream. Prior to analyses, all samples taken for the composite should be thoroughly mixed in order for the composite sample to be representative of the average affluent release.

(f] For dissolved noble gases in water, assume a MPC of 4 x 10-5 m,C1/ml of water.

l 1

i Sheet 1 of 2 TABI.E 3-2 RADI0 ACTIVE CASECUS WASTE SA:1PLING AND ANAI.YSIS Detectable Sampling Type of Concentrations Caseous Source Frequency Activity Analysis (uC1/ml)[a]

A.

Vaste Gas Each Tank Principal Gamma Emitters 10-4I Decay Tank Releases H-3 10-6 3.

Containment Each Purge Principal Camma Emitters 10-'ICI Purge Raleases H 10-6 C.

Coedenser Monthly Prit.cipal Camma Emitters 10-4(b,c]

Air Ejector H-3 10-6 D.

Environment-1 Monthly (Cas Principal Camn Emitters 10-4(b,c]

Release Samples)

Points H-3 10-6 Weekly I-131 10-12 (Charcoal Sample)

Monthly I-133, I-135 10-10 (Charcoal Sample)

Weekly Principal Camma Emitters 10-11 (Particulates)

(3a and La-140, I-131 and others)

Cross a 10-11 Monthly Composite (d]

(Particulates)

Quarterly Sr-90 10-11 l

Composite [d}

(Particulate)

Sr-89 10-11 See Sheet 2 of 2 for focenotes.

_.-..---.,-.---...-.-_.,-:=.-... -.. -.

L-...

L::: :.

.L. ~-.. - -.E..

e.

Table 3-4 PRESSURIZED WATER REACTOR CASEOUS WASTE SYSTFM LOCATION OF PROCES' AND EFFLUENT HONITORS AND SAPC'11RS REQUIRED BY TECalNICAL SPECIFICATIONS Crab Auto Control to Continuous Sang.le Measbrement Process Stream or Release Poir.t Alarm Isolation Valve Monitor Station Noble Cas I

Particulate H-3 Alpha W4ste Cas Storage Tanks X

X X

X X

X X

X X

Condenser Air Ejector X

X X

X X

X X

X Vent Header System X

X X

X X

X X

X Building Ventilation Systems React < r Containment Building (whenever there is flow)

X X

X X

X X

X X

X i

Auxiliary Building, including X

X X

X X

X X

X

+

radwaste area Fuel llandling & htorage Building X

X X

X X

X X

X SteamGeneratorBlowdowgTank Vent or Condenser Vent X

X X

X X

X X

X h

Turbine Ctand Seal Condenser

• i Hogger Air Ejector" f

• If any or all of the process streams or building ventilation systeam are routed to a single release point, the need for a continuous monitor at the individual discharge point to the main exhaust duct is eliminated. One continuous monitor et the final release point is sufficient, i

bin some PWRs the steam generator blowdown tank vent is routed to the main turbine condenser, and the need for a continuous monitor at this release point is eliminated.

"When secondary activity exceeds 10 microcuries/al, effluent activity will be based on condenser air ejector measured activity and will be considered the same as condenser air ejector ef fluent corrected for steam flow and FSAR partition factors (FSAR pp.113-28 and 11.3-29).

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APPENDIX B - PART II TO FACILITY OPERATING LICENSE NO. NPF-1 TROJAN NUCLEAR PLANT PORTLAND GENERAL ELECTRIC COMPANY DOCKET NO. 50-344 PART II

' ENVIRONMENTAL PROTECTION PLAN (NON-RADIOLOGICAL)

TECHNICAL SPECIFICATIONS i

i i

- = -

4

TROJAN NUCLEAR PLANT ENVIRONMENTAL PROTECTION PLAN (NON-RADIOLOGICAL)

TECHNICAL SPECIFICATIONS

~ TABLE OF CONTENTS Section Page

1. 0 Objectives of t$e Environmental Protection Plan,........

1-1

2. 0 Environmental Protection Issues................

2-1 3.0 Consistency Requirements....................

3-1 3.1

~ Plant' Design and Operation...................

3-1 3.2 Reporting Related to the NPDES Permits and State Certification.

3-2 3.3 Changes Required for Compliance with Other Environmental Regulations........................

13-3 4.0 Environmental Conditions....................

4-1 1

4.1 Unusual or Important Environmental Events........... 4-1 l

4.2 Aerial Remote Sensing..................... 1 5.0 Administrative Procedures...................

5-1 5.1 Review and Audit.........

5-1 5.2 Records Retention.......................

5-1 5.3 Changes in Environmental Protection Plan............

5-2 l

5.4 Plant Reporting Requirements..................

5-2 l

f l

l l

l 1

-e

'l

1. 0 Objectives of the Environmental Protection Plan The Environmental Protection Plan (EPP) is to provide for protection of environmental values during construction and operation of the nuclear facility.

The principal objectives of the EPP are as follows:

1.

Verify that the plant is operated in an environmentally acceptable manner, as established by the FES and other NRC environmental impact assessments.

2.

Coordinate NRC requirements and maintain consistency with other Federal, State and local requirements for environmental protection.

3.

Keep NRC informed of the environmental effects of facility construction and operation and of actions taken to control those effects.

Environmental concerns identified in the FES which relate to water quality matters are regulated by way of the licensee's NPDES permit.

i l

l l

l l

l l

r 1-1 l

1

2. 0 Environmental Protection Issues In the FES-OL dated August,1973, the staff considered the environmental impacts associated with the operation of the Trojan Nuclear Plant.

Certain environmental issues were identified which required study or ifcense conditions to resolve anvironmental concerns and to assure adequate protection of the environment.

The Appendix B Environmental lechnical Specifications issued with the license included monitoring programs and other requirements to permit resolution of the issues. Prior to issuance of this EPP, the requirements, remaining in the ETS related to:

1.

Protection of the aquatic environment by limiting the rate of heat and by ifmiting temperature and rate of liquid effluents discharged to the Columbic never.

(ETS 2.1) l l

2.

Protection of aqsatic life from chlorine used in plant operations (ETS 2.2) l by dechlorination.

(ETS 2.2.1.2) 3.

Limits on the discharge of phosphate,. zinc, chromate, dissolved solids and l

acids and bases.

(ETS 2. 2. 2, 2. 2. 3 and 2. 2. 4) l l

l l

4.

Surveillance programs for thermal plume mapping, water quality impingement, 9ntrainment of ichthyoplankton and discharga toxicity to establish impact t

l of plant operation on the aquatic environient.

(ETS 4.1)

Aquatic issues are now addressed by the effluent limitations and monitoring i

requirements contained in the effective NPDES Permit issued by the State of 2-1

Oregon Department of Environmental Quality. The NRC will rely on this agency and the Oregon Department of Fish and Wildlife for regulation of matters involving water quality and aquatic biota, respectively.

2. 2 Terrestrial Issues The ETS also contained programs related to protection of the terrestrial environment, t

1.

Surveillance programs of vegetation composition, bird census, small and large mammal distribution, reptile and amphibian distribution and herbi-cide accumulation to investigate impact of plat.t operation on the terres-trial environment.

(ETS 4.1.2) 2.

A special surveillance progrcm to determine cooling tower plume characteristics and to assess its impact upon ground level visibility.

(ETS 4.3.1) 3.

Potential long term impacts on the vegetation associated with drift from the cooling tower.

(ETS 4.1.2)

The NRC requirements for issue 1 and 2 have been completed and are terminated by the appraisal prepared in conjunction with preparation of this EPP.

The requirements with regard to issue 3 are specified in Subsection 4.2.1 of this EPP.

2-2

< - -,,- -~-

,, ~ -,, - - -, -

,we.

3.0 Consistency Requirements 3.1 Plant Design and Operation The ifcensee may make changes in station design or operation or r2rform tests or experiments affecting the environment provided such changes, tests or experiments do 'not involve an unreviewed environmental question, and do no't involve a change in the Environmental Protection Plan.* Changes in' plant design or operation or performance of tests or experiments which do not affect the environment are not subject to the requirements of this EPP.

Activities governed by Section 3.3 are not subject to the requirements of this section.

Before engaging in construction or operational activities not requiring prior approval and which may affect the environment, the licensee shall prepare and recc-d an environmental evaluation of such activity. When the evaluation indicates that such activity involves an unreviewed environ-mental question, the licensee shall provide a written evaluation of such activities and obtain prior NRC approval. When such activity involves a change in the Environmental Protection Plan, such activity and change to the Environmental Protection Plan may be implemented only in accordance with an appropriate license amendment as set forth in Section 5.3.

A proposed change, test or experiment shall be deemed to involve an unreviewed environmental question if it concerns (1) a matter which may result in a significant increase in any adverse environmental impact previously evaluated 5

s

• This provision does not relieve the licensee of the requirements of 10 CFR

$50.59.

3-1

in the final environmental statement (FES) as modified by staff's testimony to the Atomic Safety and Licensing Board, supplements to the FES, environmental impact appraisals, or in any decisions of the Atomic Safety and Licensing Board; or (2) c. significant change in the types or a significant increase in the amounts of effluents or licensed power level LTn accordance with 10 CFR Part 51.5(b)(2f or (3) a matter no+, previously reviewed and evaluated in the documents specified in (1) of this Subsection, which may have a significant adverse environmental impact.

The licensee shall maintain records of changes in facility design or operation and of tests and experiments carried out pursuant to this Subsection. These records shall include a written evaluation which provides bases for the deter-mination that the change, test, or experiment does not involve an unreviewed i

environmental q;estion.

The licensee shall include as part of his Annual

~

Environmental Operating Report (per Subsection 5.4.1) brief descriptions, analyses, interpretations, and evaluations of such changes, tests and experi-ments.

3.2 Reporting Related to the NPDES Permits and State Certifications Violations of the NPDES Permit or the State certification (pursuant to Section 4

401 of the Clean Water Act) shall be reported to the NRC, Region V, by submittal of copies of the reports required by the NPDES Permit or certification.

Changes and additions to the NPDES Permit or the State certification shall be reported to the NRC, Region V, within 30 days following the date the change is approved.

3-2

^

e O

If a permit or certification, in part or in its entirety, is appealed and stayed, NRC Region V shall be notified within 30 days following the date the stay is granted.

NRC Region V shall be notified of changes to the effective NPDES Permit proposed by the licensee by providing a copy of the proposed change at the same time it is submitted to the permitting agency.

The licensee shall provide NRC Region V a copy of the application for renewal of the NPDES permit at the same time the application is submitted to the permitting agency.

3.3 Changes Required for Compliance with Other Environmental Regulations Changes in plant design or operation and performance of tests or experiments which are required to achieve compliance with other Federal, State, or local environmental regulations are not subject to the requirements of Section 3.1.

3-3

^

~*

.... = -

2 : -.. :..

.2

4.0 Environmental Conditions 4.1 Unusual or Important Environmental Events Any occurrence of an unusual or important event that indicatas or.:ould result in significant environmental impact causally related in plant operation shall be recorded and promptly reported to the NRC within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> by telephone, telegraph, or facsimile transmissions followed by a written report per Subsection 5.4.2.

The following are examples:

excessive bird impaction events, onsite plant or animal disease outbreaks, mortality or unusual occur-rence of cr.y species protected by the Endangered Species Act of 1973, fish kills, increase in nuisance organisms or conditions and unanticipated or emergency discharge of waste water or chemical substances.

No routine monitoring programs are required to implement this condition.

4.2 Aerial Remote Sensing Vegetation communities of the site and vicinity within one kilometer of the cooling tower in all directions shall be aerially photographed to detect and assess the significance of damage, or lack thereof, as related to cooling tower drift.

Photography shall be done by aerial overflight during late summer. Monitoring shall include a program of low altitude multi-spectral photography. The scale for full coverage shall be adequate to enable identification of vegetative damage over relatively small areas of terrain.

Some circumstances may warrant inspection of photographs discerning individual trees.

Such scale should be in the interval between 1:10,000 and 1:12,000 as appropriate to resolve impacted features.~

4-1

photographs shall be compared with preoperational photographs to ascertain changed vegetation.

Photographic interpretations shall include correlation of data from ground inspection surveys with areas of stress and non-stress as observed on the photographs for purposes of. verification of results.

A semi-annual aerial photographic monitoring program has been underway at the Trojan Plant for several years. The licensee shall continue this program every two years for three additional periods and a report shall be submitted summarizing the results of each overflight as part of the annual report following each aerial photographic monitoring period.

Reports of results shall encompass but not be limited to a description of the program, time of day, film types, spectral bands and one (1) set of color prints of the area within approximately one kilometer (1 km) radius of the cooling tower.

This requirement shall be terminated following submission of the results of the third additional overflight.

k 4-2

o 5.0 Administrative Procedures 5.1 Review and Audit 1

The licensee shall provide for review and audit of compliance' with the Environmental Protection Plan. The audits shall be conducted independently of the individual or groups responsible for perforaing the specific activity. A description of the organization structure utilized to achieve the independent review and audit function and results of the audit activities shall be maintained and made available for inspection.

5.2 Records Retention Records and logs relative to the environmental aspects of plant operation shall be made and retained in a manner convenient for review and inspection.

These records and logs shall be made available to NRC on request.

Records required by Section 3.1 shall be retained for the life of the plant.

All other records, data and logs relating to this EPP shall be retained l

for five years or, where applicable, in accordance with the requirements of other agencies.

5.3 Changes in Environmental Protection Plan i

l Request for change in the Environmental Protection Plan shall' include an j

assessment of the environmental impact of the proposed change and a supporting jusitification.

Implementation of such changes.in the EPP shall not commence 5-1

e prior to NRC approval of the proposed changes in the form of a licensa amendment incorporating the appropriate revision to the Environmental Protection Plan.

5.4 Plant Reporting Requirements 5.4.1 Routine Reports An Annual Environmental Operating Report describing implementation of this EPP for the previous year shall be submitted to the NRC prior to May 1 of each year. The initial report shall be submitted prior to May 1,1982.

The report shall include summaries and analyses of the results of the environmental protection activities required by Subsection 4.2 of this Environmental Protection Plan for the report period, including a comparison with preoperational studies, operational controls (as appropriate), and previous non-radiological environmental monitoring reports, and an assessment of the observed impacts of the plant operation on the environment.

If harmful effects or evidence of trends towards irreversible damage to the j

environment are observed, the licensee shall provide a detailed analysis of the data and a proposed course of action to alleviate the problem.

t I

The Annual Environmental Operating Report shall also include:

l t

A list of EPP noncompliances and the corrective actions taken to remedy a.

l them.

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5-2 i

,r

~

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b.

A list of all changes in station design or operation, tests, and experiments made in accordance with Subsection 3.1 which involved a potentially significant unreviewed environmental issue.

c.

A list of nonroutine' reports submitted in accordance with Subsection 5.4.2.

In the event that some results are not available by the report due date, the report shall be submitted noting and explaining the missing results. The missing data shall be submitted as soon as possible in a supplementary report.

5.4.2 Nonroutine Reports A written report shall be submitted to the NRC within 30 days of occurrence of nonroutine event.

The report shall (a) describe, analyze, and evaluate the event, including extent and magaitude of the impact and plant operating charac-teristics, (b) describe the probable cause of the event, (c) indicate the action taken to correct the reported event, (d) indicate the corrective action taken to preclude repetition of the event and to prevent similar occurrences involving similar components or systems, and (e) indicate the agencies notified and their preliminary responses.

Events reportable under this subsection which also require reports to other Federal, State or local agencies shall be reported in accordance with those reporting requirements in lieu of the requirements of this subsection.

The NRC shall be provided a copy of such report at the same time it is suliitted to the other agency.

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