ML18086A627

Ets,Part 1 - Radiological

ML18086A627
Person / Time
Site:	Salem
Issue date:	05/31/1981
From:	Public Service Enterprise Group
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Shared Package
ML18086A623	List: ML18086A622 ML18086A624 ML18086A626 ML18086A627 ML19346A119
References
NUDOCS 8106050149
Download: ML18086A627 (78)

Text

I APPENDIX B TO fAG_!_IJ_TY _OPERATING.J.ICENS~Ji~-75 SALEM NUCLEAR GENERATING.STATION UNIT 2 PUBLIC SERVICE ELECTRIC AND GAS COMPANY DOCKET NO; 50-311

. ~NVIRONMENTAL TECH_NICAL SPECIFICATIONS PART I - RADIOLOGICAL MAY 1981

ENV~RONMENTAL TECHNICAL SPECIF.ICATIONS.

PART I - RADIOLOGICAL TABLE OF CONTENTS Sec ti Qn Title Page 1.0 DEFINITIONS, ABBREVIATIONS AND NOTES., *. *.*,., *.*, *.*.*,.,.,... _. *

l. l-1

1. l 1.2 2.0

2. l 2.2 2.3

. 2. 3. l

2. 3. 2 2.3.3 2.3.4.

~' 3, 5.

3.0

3. l 3.1. l 3.1.l.l

3. 1.2 3.2 4.0

• , 5. 0

5. l 5.2 5.3

5. 3. l

. 5. 3. 2 DEFINITIONS * *.

NOTES....

LIMITING CONDITIONS FOR OPERATION THERMAL EFFLUENTS

• CHEMICAL EFFLUENTS RAD10ACTIVE.EFFLUENTS

• SPliCIFICATIONS FOR LIQUID WASTE EFFLUENTS.., * *

• SPECIFICATIONS FOR LIQµID WASTE SAMPLING AND MONITOR-ING.

SPECIFICATIONS FOR GASEOUS WASTE EFFLUENTS.*

~.*.*.*.*.*

• SPECiFICATIONS FOR GASEOUS WASTE SAMPLING AND MONITORING

. SPECIFICATIO~S FOR SOLID WASTE HANDLING AND DISPOSAL **

ENVIRONMENTAL SURVEILLANCE **

NON-RADIOLOGICAL SURVEILLANCE ABIOTIC. * *., *. *.*.

C*..

Meteorological Monitoring.*

BIOTIC * * * * * ******

RADIOLOGICAL SURVEILLANCE **

SPECIAL SURVEILLANCE AND STUDY ACTIVITIES *

• ADMINISTRATIVE CONTROLS RESPONSIBILITY. * ******

ORGANIZATION. * *.

REVIEW AND AUDIT..

.... '~ \\

'. ~- ~~-

~.

NUCLEAR REVIEW BOARD ( NRB) * * * * *1

• STATION OPERATIONS REVIEW COMMITTEE (SORC} **

i 1.1-1*

1.2-l

2. 1-1

2. 1-l

2. 2-l

2. 3-T

2. 3-2.

2. 3-4.

2. 3-8.

2 *. 3-13

2. 3-19 3.0-1

3. 1-1

3. 1-l

3. 1-1

3. 1-3 3.2-1 4.1-1

5. 1-1

5. l-l 5.2-1

5. 3-1

. 5. 3-1

5. 3-1

.ENVIRONMENTAL TECHNICAL SPECIFICATIONS PART 1 -

RADIOLOGICAL TABLE OF CONTENTS (Cont'd)

Section Title 5.4 ACTION TO BE TAKEN IF A LIMITING CONDITIONS FOR OPERATION IS 5.5 5.6 5.6.l 5.6.1.1

• 5.6. l.2 5.6.2 5.6.2.l 5.6.2.2 5.6.2.3

5. 6 *. 3 5.7 EXCEEDED PROCEDURES * * *

• PLANT REPORTING REQUIREMENTS *

• ROUTINE REPORTS * ** *

• Annual Environmental Operating Report **

Radlqactive Effluents ~elease Report

• NONROUTINE REPORTS ***********.***. ~.. ~

Nonroutine Envi~on~ental O~~ratirig Reports ***.*

• Nonroutine Radiological Environmental Operating Report.....,..... -* * ** -* * *

• Nonroutine Radioactive Effluent Reports.*.....

CHANGES I~ ENVIRONMENTAL TECHNICAL SP.ECIFlCATIONS **

RECORDS 'RETENTION. * * * * * * * * *,.

• ii Page

5. 4-1 5.5-1 5.6-1 5.6-1 5.6-1

5. 6-2 5.6-2 5.6-2

5. 6-3 5.6-5

• 5.6-6

5. 7-1

Table

2. 3-1

2. 3-2

2. 3-3

2. 3-4

2. 3-5 3,; 2-1 3.2-2 5.6-1 No.

LIST OF TABLES Title Radioactive Liquid Sampling and Analysis.

Radioactive Gaseous Waste Sampling and Analysis **

Liquid Waste System Specifications..........

Gaseous Wast~ System Specifications.......

Gamma and Beta Dose Factors * * *

• Operational Environmental Radiological Monitoring Program **

Sensitivity Levels for Environmental Sample Analyses.

Environmental Radi ol ogi cal Monitoring Program Summary

• iii Page

2. 3-20

2. 3-21

2. 3-22

2. 3-23

2. 3-24 3.2-6 3.2-9 5.6-8

Figure No.

5. *2-1 LIST OF FIGURES Title Page Organization Chart Showing Corporate Interrelationships. * *.

5.2-2 iv

1.0 DEFINITIONS, ABBREVIATIONS AND NOTES 1.1 DEFINITIONS 1

• CALIBRATION Use of a known quantity of a measured parameter to determine the accuracy of the measuring instrument.

2.

CONTROL STATION Sample location that is far enough away fro,m the station. that it will not be affected by radio 1ogica1 emi s s i ans or other s ta ti on releases.

3.

EMERGENCY NEED FOR POWER An emergency need for power shall be considered to exist if the system is unlikelyto meet the demand after the licensee has attempted to,_satisfy its requirements by operating all other available base load units.

4.

ENVIRONMENTAL SAMPLES Samples of soil, air, water, biota, or biological material

. c91le1cte? fo,r the purp9ses of analysis.

• 1.1-1

Supe,r.i;nten.dent:,: an e,v.ent whtch: ca.us.es: an adverse impact on the U~.e' Q;f; a, s;tmwl1a:'f~e~d; s.d:gnail: o.r che:~k sou.rce, to.' d'etermi ne LN:DlCATOR\\ STATION; S:ample; lo~Ga;tton: whe:ne:. any: ad.Vcer.s0e: env,fronmental e,ffe.cts r,esul:ti'ng_: from1 s~,tatton. opera<tion** co:uld bee. perceived.

9...

INSTRUMENT* CHE.CK.

10.

NORMAL OPERATION Steady state operation at any power level; includes operation with up to 10% of condenser tubes blocked.

11.

REPORT LEVEL The numerical level of an environmental parameter below which the environmental impact is considered reasonable baseq on available information *

12.,SPECIAL STUDY PROGRAMS Environmental study programs designed to evaluate the impact of station operation on an environmental parameter

• 1.1-3

~-I

1.2 NOTES

1.

The Environmental Technical Specifications are limitations, conditions and requirements which are considered necessary to addre?s *environinerital concerns.

2.

Each Monitoring Requirement shall be performed within the

. spec;ified time interval, unless otherwise noted, with a maximum allowable extension not to exceed 25% of the monitoring interval.

This extension also applies to all sampling, instrument check, calibra_tion and functional test frequencies.

These provisions provide allowable tolerances for perfonning

.monitoring activi-ties beyond those specified in the nominal monitoring interval. These tolerances are necessary to provide operational flexibility because of scheduling, per-1 formance considerations and env'ironmental influences.

~. 2... 1

2.0 LIMITING CONDITIONS FOR OPERATION 2.1 THERMAL EFFLUENTS See Appendix B Part II - Non-Radiological

• 2.1-1

2.2 CHEMICAL EFFLUENTS See Appendix B Part II - Non-Radiological

• 2.2-1

2.3 RADIOACTIVE EFFLUENTS Objective To define the limits and conditions for the controlled release of radioactive materials i.n liquid and gaseous effluents to the environs to ensure that these releases are as low as practicable. These releases should not result in radiation exposure~ in unrestricted areas greater than'a few percent of natural ~ackground exposures. The concentrations of radioactive materials in effluents shall be withtn 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 practicable, the following *design objectives apply:

For liquid wastes:

a.

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

b.

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

For gaseous wastes:

c.

The annual total quantity of noble gases above background discharged from the site should result in an air dose due to gamma radiation of less than

2. 3-1

TO mr.ad'.~; andl am ai:r dose' due-' to_* beta. radiation of less than 20 mrad, at. any* locat'f<:m, near-ground: level which** co.uld: be-occupied by indiViduals at* or beyond1 the: boundary of-the

• s..fte-.

d1 T*he' annua:ll tota\\13 quantity* of a~ll radi ofodines and... radfoacti ve: material in partfcuTat'e: forms*, with:. half'-1 ives greater than eight days, above b:ackground 1

, from-all reactors; at: a*. site should not result in an annual dose. to any.' organ~ of aff indl:V.fdual in-an-unrestricted area from all pathways* of* exposure fn. excess*. of: T5; mrem-.

e 0

T:he,* annua~' tota:i( quanti:ty of: fodfne-T3l discharged' from each reactor*

at a, s-.fte* should not exceed 1 Ci'.

2.3~.1 SRECtFLCATilONS: FOR uqum* WASTE EFFLUENTS

• a*..

The* concentratfon*: of' ra*dfoactiVe-materials released in liquid was,te effluents from* all reactors at the site shall not exceed

\\

the-values' s:pe:ciffed~ ih: 10 CFR Rart:.20.,- Appendix s*, Table II, CoTumn: 2',. for unres:trfcted. areas* *.

b.*..

The' cumulative, release: of radi-oacttve. materials. in* liquid waste effTuents,, *excluding: tri.tlum and* dfs*solved gases, shall not exceed ro~ Ci /reactor/calendar* quarter *.

c*.

The" cumulative~ re Tease of ra'di oactfve: mate.rials: in liquid waste-eff:l uents, excluding tritium and dis*solved gases*, shall not e-xceed 2'0* Cf/reactor i"n any T2 consecutive months.

d. _ Duri.ng* release. of radioactive wastes*, the effluent control monitor S'hall be-set to aTa:nn and. to init.iate the automatic closure of 2.J-2'

e.

each waste i sol ati on valve prior to exceeding the 11mi ts specified in 2.3.1.a above.

The operability of each automatic. isolation valve in the liquid

5. 6.,2. 3. 3.

.2. 3-3

2.3.2 SPECIFICATIONS FOR LIQUID WASTE SAMPLING AND MONITORING

a.

Plant records shall be maintained of the*radioactive concentration I

and volume before dilution of liquid wa.ste intended for dis-charge and the average dilution flow and length of time over which each discharge occurred. Sample analysis results and other reports shall be submitted by Section 5.6.l of these Specifications. Estimates of the sampling and analytic~l errors_ assoc1ated with each reported value shall be included.

b.

Prior to release of each batch of liquid waste, a sample shall be taken from that batch and analyzed for the concentratio~

of each principal gamma emitter in accordance with Table 2.~-1 to demonstrate compliance with Specification 2.3.l using the flow rate into which the waste. is discharged during the period of di scha'rge.

c.

Sampling and analysis of liquid radioactive waste shall be performed in accordance with Table 2.3-1. Prior to taking samples from a monitoring tank, at least two tank volumes shall be recirculated.

d.

The radioactivity in liquid wastes shall be continuously monitored and recorded during releases.

Whenever these monitors are inoper-able 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 samples of each tank to be discharged shall be analyzed and two plant personnel shall;independently check valving prior to the dis-charge. If these monito.rs 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 rele~se from a liquid waste tank shall be made and any release in progress shall be terminated.

f.3-;4

Bases

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.c~eck prior to making a release.

g.

The radioactivity in steam generator blowdown shall* be continuously monitored and recorded.

Whenever these monitors are inoperable, the bl owdown fl ow sha 11 be diverted to the. waste management sys-tem and the direct release to the environment tenninated.

The release of radioactive materials in liquid waste effluents to unrestricted**-

areas shall not exceed the concentration limits spe~ified in 10 CFR Part 20 and should be as low as practicable 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 unresricted area will not exceed 5* mrem.

At the same time, these specifications permit the flexibility of operation, cempatible with considerations of health and safety, to assur~ that the public is provided a dependable source of power under unusual operating conditions which may temporarily result in releases higher than the design objective levels bu~ 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 radio-active material in liquid wastes. as low as practicable, the annual releases will not exceed a small fractipn of the concentration limits specified in 10 CFR Part 20.

2.3-5

The design objectives have been developed based on operating experience taking into account a combination bf variables including defective fuel' primary system leakage, primary to secondary system leakage, steam generator blowdown and the perfonnance of the various waste treatment systems, and are consistent with 10 CFR

• Part SO. 36a.

Specification 2.3.1.a,requires the licensee to limit the concentration of radio-attiv~ m~terials 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. Ttiis specification prov.ides assurance that no member of the general public will be exposed to liquid containing radioactive materials in excess of limits con.sidered permissible under the Commission's Regulations.*

Spec ff i cations 2. 3.1. b **and 2. 3. 1

• c establish the upper 1 i mits for the re 1 ease *of "* * * **

radfoactive materials 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 t~e plant and the liquid waste treatment systems are functioning as designed.

Releases of up to these levels will result in concentrations of radioactive material in liquid waste effluents at small percentages of the limits specified in 10 CFR

• Part 20.

Consistent with the req ui remen~s of 10 CFR Pa rt 50, Appendix A, Design Criterion 64, Specifications 2.3. l.d and 2.3.l.e require qperatiqn of suitable *equipment to control and monitor the releases of radioactive materials in.*

liquid wastes during any peri8d that these releases are taking place.

2.3-6

Specification 2.3.1.f requires that the licensee maintain and operate the equipment installed in 'the* liquid waste systems to reduce the release of radioactive materials in liquid effluents to as low as practicable consistent with the requirements of 10.CFR Part 50.36a. Normal use and maintenance of.

installed equipment-in;the liquid waste system provides reasonable 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 equipment whenever it appears that the projected cumulative discharge rate will exceed one-fourth of this d~si~n objective annual quantity during any calendar quarter.

Spe~ificition 2.3.l.g restricts the amount of radioactive material th~t could be inadvertently released to the environment to an amount that will*

not exGeed the Technical Specification limit.

In addition to limiting conditions for operation listed under Specifications 2.3. l.b an~ 2.3.1.c, the reporting requirements of Specification 2.3.1.h qelineate that the licensee shall identify the cause whenever the cumulative release of radioactive materials in liquid waste effluents exceeds one-half the design objective annual quantity.during anycalendar quarter and 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 calenc:lar quarter in which the release occurred as required by Specifica-tion 5.6.2 of these Technical Specifications

• 2.3-7

Specification 2 3.1. i 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 monitoring requirements given under Specification 2.3.2 provide assurance that radioactive materials in liquid wastes are properly controlled and monitored tn conformance with the requirements of Design Criteria 60 and 64.

These recjuire.ments provide the data for the licensee and the Commission to evaluate the plant's performance relative to radioactive liquid wastes released to the environment.. Reports o.n the quantities of radioactive materials released in liquid waste effluents are furnished to the Commission according to Section 5.6.l of these Technical Spec.i-fications.

On the basis of such. reports and any additional informati.on the Commission may obtain from the licensee or others, the Commission may from tJme: to time require the licensee to take such action as the Commission cleems &ppropri ate.

The points, of release to the env*ironment to be monitored i.n Section 2.3.2 foclude

~,l l t.he mon.ttored, r.el 1ease poJnts. as~ provided for in. Tab Te 2. 3-3.

2.*,3. 3 SPECff:JCATlONS. FOR GASEOUS, WASTE EFFtUENTS The terms: us:ed in these. Specificati ans are as follows:

s.Libscrtpts v ;. refers to vent re Teases

, ~e,fe

• rs: to. fndi:vidual noble gas nuclide (ReJer to Table* 2 *. 4-5: for the noble gas. nuclides consJde:red}

2.3-8

. --~::..

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

= lQ sum of the individual noble gas radionuclides determined i i to be present by isotopic analysis K = the average total body dose factor due to ga1T111a emission (rem/yr per ~i/sec)

[ = the average skin dose factor due to beta emissions (rem/yr per Ci /sec)

M = the average air dose factor due to beta emissions (rad/yr per Ci /sec)

• N = the average air dose factor due to gamma emissions (rad/yr per Ci/sec)

The values of K, [, Mand N are to be determined each time isotopic analysis is required as delineated in Specification 2.3.4. Determine the following using the results of the noble gas radionuclide analysis:

K = (l/QT) I.Q.K.

l l l

[

= {l/QT) /.;Q;L; M = ( 1 /QT) Ii Qi Mi N = (1 /QT) l

• Q

• N.

l l 1

Where the values of K1, Li, M; and N1 are provided in Table 2.3-5, and a re site de'pendent garrma and be ta dose factors:

2.3-9

Q ~ the measured release rate of the r~di?iodines and radioactive materials in particulate forms wi~h half.;.lives greater than

• eight days.

a.

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

Q. 33 [QTv (Lv + l. Hfv U

< l (2')

The release rate limit of all radioiodines and radioactive materials i.n p.art:iculate.fonn with half-lives greater than eight days, released to the e_nvirons as part of the gaseous wastes from the site sha 11 be S;U,Ch t.ba.t:

l 5-105' Q

., 'x. '

v

< l q..

(l); The* average rele.ase rate of noble gases from the* site during any

~:alem.d.aJ' qua-rter s.ha.H be s.uch that:

l3 [Qt/~~]

< l and 6.. 3 [ QTv-MJ*

< l

('~)

The, avera~ge.* relea,se: rate of noble gases from the site during any 12 conse.cuttve months: s.ha n be:

2:5.~ [~tvJi~ J and l3 [ QTvMv. ]

< 1 2.3-10

(3)

The average release rate per site of all radioiodines and radio-I active materials in particulate form with half-lives greater than eight days during any calendar quarter shall be such that (4) The average release rate per site of all radioiodines and radio-active materials in particulate form with half-lives greater than eight days during any period of 12 consecutive months shall be such that:

< l (5) The amount of iodine-131 released during any calendar quarter shall not exceed 2 Ci/reactor.

(6)

The amount of iodine-131 released during any period of 12 consecutive months shall 'not exceed 4 Ci/react6r.

c.

Should any of the conditions of 2.3.3.c(l), (2) or (3) listed below exist, the licensee shall make an investigation to identify the causes o~ the release rates, define and initiate a program of action to reduce the release rates to design objective levels listed in Section 2.3 and report these actions to the NRC within 30 days from the end of the quarter during which' the releases occurred.

2.3-11

((ll )}

Iif:. tne: a:vera.§1~* re'1ei.S*e rite* of nob le gases from the site during any c::artenda'r q~a*rte.rc* fit-; sttch' that:

> l

({Z'.)}

i:.n: the~ a\\v.e:ra.ge'. re:ltease: rate per site of a 11 radi oi odi nes and radio-a=utiv.e; matertals: fn, pa*rtt:cul'ate* form* with ha 1 f-1 i ves greater than e:iigh;t: days, d*urfog1 any calendar* quarter is such that:

> l f3:l!

I'.f the: amount: of' todfne-1'3l released duri'ng any calendar quarter is g,reater than; o:=~.5:, C:t/re1*c.tor..

cf..

Du.r.fng; the: r:eJ.eas'e; om* g_a.seous. wastes from the primary system waste gas tt0Jrdup1 sy,s.tem~* the: e:ff,luent monfto.rs listed in Table 2.3-4 shall be operating and~ set to,, a*la=nn> and: to:. in.ttfa.te the. automatic closure of the waste gas d:.ijs:cha:r.g~~ va-J:v,e: p.rior-to exceeding:, the 1.imits specified in 2.3.3.a above.

• l:he~ CJ?.er:ab:i:.Ii*:ty' o.f each: automati'c isolation valve sha.ll be demonstrated q.ua'.r:tenr:Y:'""

. i e:..

T'.he~ maximum~a.ctt'v1i'ty,* to be* conta.fned in one waste gas storage tank shal 1 n-a;t~ e:xceed:; 4'T,.oo:m c u.r.i:es0 ('cons:.; de red as Xe-1 33) *

'I

2.3.4

f.

An unplanned or uncontrolled offsite release of radioactive materials in gaseous effluents in excess of 5 curie~ of noble gas or 0.02 curie of radioiodine in gaseous form requires notification. This notification shall be in accordance with Section 5.6.2.J.3.

SPECIFICATIONS FOR GASEOUS WASTE SAMPLING AND MONITORING

a.

Plant records shall be maintained and reports of the sampling and analys-es results shall be submitted in accordance with Section 5.6 of these Specifications. Est1mates of the sampling and analytical error associated with each reported value should be included.

• . b.

Gaseous releases to the environment (Table 2.3-4), except from the turbine building ventilation exhaust and as no_~ed in Specification 2.3~4.c, shall be continuously monitored for gross radioactivity and the flow continuously measured.and recorded.

Whenever these monitors are inoperable, grab samples shall be taken and analyzed daily for gross radioactivity. If these monitors are inoperable for more than seven days, these releases shall be terminated *

c.

During the release of gaseous wastes from the primary system waste 9as holdup system, the gross activity monitor, the iodine collec-tion device, and the particulate collection device shall be operating

• 2.3-13

d.

All waste gas effluent monitors shall be calibrated at least Bases quarterly by means of a known radioactive source which has been calibrated to a National Bureau of Standards source.

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

e.

Sampling and analysis of radioactive material in gaseous waste, including particulate fonns and radioiodines shall be performed in accordance with Table 2.3-?.

The. rele~se of r.adioacti ve materials in gaseous waste effluents to unrestricted areas shall not ~xceed the concentration limits specified in 10 CFR Part 20 and should be as low as practicable in accordance with the requirements of 10 CFR Part 50w36a.

These 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 ai~ dose from the site due to beta radiation will not exceed 20 mrad from noble gases, that no individual in an unrestricted area will receive an annual dose greater than 15 mrem from fission product noble. gases, and that the annual dose to any organ of an indivdual from radio-iodines and radioactive material in particulate form with half-lives greater than eight days will not exceed 15 mrem per site.

At the.same time these specifications permit the flexibility of operation, compa.tible with considerations of health and safety, to assure that the I

pubic is.provided with a dependable source of power under unusual operating 2.3-14

cqndi~ions which may temporarily result in releases higher than the design objective levels but still within the concentration limits specified in 10 CFR Part 20.

Even with this operational flexibility under unusual operating conditions, if the licensee exerts every effort to keep levels of radioactive material in gaseous waste effluents as low a~ 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 variables including defective fuel, primary system leakage, primary to secondary system leakage, steam generator blowdown and the performance of the various waste treatment systems.

Specification 2.3.3.a(l) limits the release rate of noble gases from the *site so that the corresponding annual gamma and beta dose rate above background to an individual in an unrestricted area will not exceed 500.mrem to the total body or 3000 mrem to the skin in compliance with the limits of 10 CFR Part20.

For Specification 2.3.3.a(l), 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 2.3-5. The expressions used to calculate.

these dose factors are based on dose models derived in Section 7 of Meteorology and Atomic' Energy-196.8 and model techniques provided in Regurafori Gl.dde Lio9,'

Calculation of Annual Doses to Man from 'Routine Reil eases of Reactor Effluent_? *for the Purpose of Evaluating Compliance With 10 CFR: Part 50, Appendix I dated ;

March 1976.

2.3-15

Dose calculations have been made to determine the site boundary location with the highest anticipated dose rate from noble gases usfog onsite meteorological data and the dose expressions provided in Regulatory Guide 1.109.-- The dose expression considers the release point location, building wake effects, and the physical characteristics of the radionuclides.

The.offsite location with the hi~hest. anticipated annual dose from released noble gases is 1270 meters in the North direction.

The release ~ate Specifications for a radi~iodine and radioactive 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.

~.. -*

Specifications are: 1) individual inhalation of airborne radionuclides,

_2) deposition of radionuclides onto green leafy vegetation with subsequent con-sumption by man, and 3) deposition onto grassy areas where milch animals graze with consumption of the milk by man.

Methods fo*r estimating doses to.the thyroid via these pathways are described in Regulatory Guide 1.109. The offsite location with the highest anticipated thyroid dose rate from radioiodines and radioactive material in particulate form with half-lives greater than eight days.

was determined using onsite meteorological data and the expressions described.

in Regulatory Guiqe 1.109.

Specification 2.3.3.a(2) limits the release rate bf radioiodines 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 than 1500 mrem.

2.3-16

For radioiodines and radioactive material in p~rticulate form with half-lives greater than eight days, the most restrictive location is a dariy farm located 6600 ffieters in the NW direction (v~nt X/Q = ~.l x 10-7 sec/m3).

Specification 2.3.3.b establishes upper offsite levels for the releases of noble gases and radioiodines and radioactive material in particulate form with half-lives greater than eight* days at twice the design objective annual quantity during any calendar quarter, or four times the design objective annual quantity during any period of 12 consecutive months.

In addition to the limiting conditions for operation of Specifications 2.3.3.a and 2.3.3.b, the repo.rting requirements of 2.3.3.c provide that the cause shall be identified whenever the release of gaseous effluents exceeds one-ha 1 f the design objective annual quantity during any calendar quarter and that the proposed program o! action to reduce such rel'ease rates to the design objectives shall be described.

Specification 2.3.3~d requires that suitable equipment to monitor :and control' the ~adio~ctive gaseous releases is operating during any period these releases are taking place.

Specification 2.3.3.e limits the maximum quantity of radioactive gas that.can be contained in a waste gas storage tank.

The calculation of this quantity should assume instantaneous ground release, a X/Q b~sed 5 percent meteorolo~y~

the average gross energy is 0.19 Mev per-disintegration (con~iderin~ Xe-133 2.3-17

to be the principal emitter} and exposure occurring at the minimum site boundary radius using a semi-infinite cloud model.

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

Specif1cation 2.3.3.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 Specification 2.3.4 provide assurance that radioactive materials released in gaseous waste effluents are properly controlled and monitored in conformance with the req~irements of Design Criteria 60 and 64.. These requirements provide the data for the licensee and the Commission to evai"uate the plant's performance relative to radioactive waste effluents released to the environment. Reports on the quantities of radioactive materials released in gaseous effluents are furnished to the Commission on the basis of Section 5.6.l of these Technical Specifications.

On the basis of such reports and.any additional information the Commission may obtain from the l,icensee

• or others, the Commission may from time 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 2.3.4 include all the monitored release points as provided for in Table 2.3-4.

2.3-18 I*

I

'~

Specification 2.3.4.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 requirement for all PWR reactors, the monitoring of gaseous releases from turbine buildings is not required.

2.3.5 Bases SPECIFICATIONS FOR SOLID WASTE HANDLING AND DISPOSAL

a.

Measurements.shall be made to determine or estimate the total curie quantity and principal radionuclide composition of all radioactive solid waste shipped offsite.

b.

Reports of the radioactive solid waste shipments, volumes, principal radionu.clides, and total curie quantity, shall _be submitted in accordance with Section 5.6.l.

The requirements for solid radioactive waste handling and disposal given under Specification 2.3.5 provide assurance that solid radioactive materials stored at the plant and shipped offsite are packaged in conformance with 10 CFR Part 20, 10 CFR Part 71, and 49 CFR Parts 170-178.

2.3-19

(

TABLE 2.3-.l RADIOACTIVE LIQUID SAMPLING AND ANALYSIS Sampling Frequency Detectable Liquid Type or Concentr;itions So*"Cd and Analysis Activity Analysis CµCi/ml)a b

A. Monitor Tank Releases Each Batch Principal Gamma Emitters 5x10-7 One Batch/Month Dissolved Gases f 10-9 Weekly Compositec Ba*La~140, I* 131 10...

Monthly Conipositec H-3 10-s Grosso:

10-7 Quarterly Compositec Sr-89, Sr-90 5 X 10-g B. Primary Coolant.

Weeklyd 1-131, 1-133 10-6 I',.

C. Steam Generator Slowdown Princip31 Gamma Emitters 5 x 10-'

Weeki ye Ba-Li-140: 1-131 10-6 One Sample/r.1onth Dissolved Gases f 10-s -** *-

Monthly Compositee H-3 10-s Grosso:

10-i

~

Quarterly Compositee Sr-89, Sr-90 5 X 10-B 11The detectability limits for activity analysis arc b<tsed on the technical feasibility and on the potential significance in the environment of the ou.:.ntities released. For some nucli<.les, lower detection limits may be readily achievable, *and when nuclides are measured below the stated limits, they should also be reported.

a> For ~rtain mixtures of gamma emitters, it may not be possible to measure radionuclides in concentrations near th~i~

sensitivity limits when other nuclides are present in the sample in much greater concentrations. Under these circum*

stances, it will be more appropriate to calculate the concentrations of such radionuclides using measured ratios with those radionuclides which are routinely identified and measured.

c A *composite sample is one in which the c_:Jantity of liquid sampled is.proportional to the quantity of liquid waste ciischargcd.

dThe power level and* cleanup. or purificat:on flow rntc at the sample time shall also be reported.

eTo be representative of the average quantities and concentrations of r;,dioilctive materials in liquid effluents. sJmplcs should be collected in proportion 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 con1posite sample to be representative of the average effluent release.

f For dissolved noble gases in water, assumc.,a MPC of 4 x. 10*5 µCi/ml of water.

2.3-20

TABLE 2.3-2 RADIOACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS

• Sampling Frequency Dc1ecu!bht Gaseous Type of Concentrallons Source and Analysis Activity_ Analysis

(µC1/mll~

A. Waste Gas Decay Tank Releases Each Tank to be Released Principal Gamma Emitters 10-4 b

H-3 10-6

a. Containment Purge Releases Each Purge Principal G:wimJ Emitters 10-4C H-3 10-6

c. Condenser Air Ejector

• Monthly Principal Gamma Emitters 10_,.b. c H-3 10-6 D. Environmental Release Points

.Monthly Principal Gamma Emitters 10-"'b, c (Gas Samples)

• H*3 10-~

• Weekly (C:h;:rcoal Sample) 1-131 10-12 Monthly (Charcoal Sampl.:-)

1-133, 1-135 10-10 Weekly (Particulates)d Principal Gamma Emitters (Ba-La-140, 1-131 and others) 10-11 Monthly Composited (Particulates)

Gross a

• 10-11 Quarterly Composited Sr-89, Sr-90 10-11 (Particula tcs) 1 The above detectability limits for activity analysis arc based on 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 tr.!low the stated limits, they should also be reported.

I> for certain mixtures of gamma emitters, it may not be possible to measure radionuclidcs at levels near their sen§itiv*

ity limits when other nuclides arc present in the sample at much higher levels. Under these circumstances, it will be more appropriate to calculate the levels of such radionuclides using observed ratios with those radionuclides which are mcaJurable.

c Ana,lyses shall also be pcrform~d following t!ach refueling, startup, or similar operational occu~rence which could alter the rr.ixture of radionuclides.

dTo be representative of the average quantities and concentrations of radioactive materials in particulate form released in gaseous effluents, samples should be collected in proportion to the rate of flow of the effluent.stream.

2. 3-21

N.

N N

TABLE 2.3-3 SALEH STATION - LIQUID WASTE SYSTEM LOCATION OF PROCESS AND EFFLUENT MONITORS AND SAMPLERS REQUIRED ElY TECHNICAL SPECIFICATIONS Gr;ib

V. '-!asu rement High Radiation Auto Control 10 - Gross Act1v1 ty Sample Gross 01ssolvcd Isotopic Liquid Proc1m Stream or Release Point Alarm Isolation Vi!lve Continuous St;i11on Activity I

G<1ses Alpha H*3 Analysis Lrvel

. Hanf tor At.>""

Miscellaneous Monitor Tanksb x

x x

x x

x x

-chemical ~rain Tank x

x x

x x

x

)(

Laundry 1nd Hot Shower Tanks 1 x

• x x

x x

x x

Primary Coolant System x

x Liquid Ra<.lwaste Discharge Pipe x

x x

x Steam Generator Slowdown System x

x x

x x

x x

x x

Outdoor Storage Tanks (potentially radioactive)

Xe Prf111ary Water Storage Tank x

x x

Refueling Water Storage Tank

--Component Cooling Systems*

x x

x xd Turbine Building Sumps (Floor Drains) x x

x a The contents of the -Laundry and Hot Shower Tanks are sampled, analyzed, and then filtered prior to release through the liqufd radwaste discharge pfpe.

b Includes Waste Monftor Tanks, Waste Monitor Holdup Tank, eves Monitor Tanks.

c Grab sample to be taken and analyzed each 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> whenever tank leakage exists.

1 Grab sample,to be taken and analyzed each 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> whenever the gross actfv1ty fn the secondary coolant system exceeds 10-5 uCf/ml (Except H-3)~

.. !~ml

TABLE 2.3-4 SALEM STATION GASEOUS WASTE SYSTEM LOCATION OF PROCESS ANO EFFLUENT MONITORS ANO SAMPLERS REQUIRED SY TECHNICAL SPECIFICATIONS Rad1at1on Cont1nuous Grab MeaforeFT'!!nt Auto Control 10 S.:imp!e Process Stream or Release Point Alam Isolation Valve Monitor S1a11on Not.le Gas I

Particulate H*3 Alpha N

w I

N w waste.Gas Decay Tanks Condenser Air Removal System Plant Vent Building Ventilation Systems Reactor Containment Building (whenever th~re is fio\\'1.')

• A!Jxiliary Building and Raawaste Areaa Fuel Handling & Storage Buildinga Turbine Gland Seal Condenser I

Waste Gas Discharge Line x

x x

xh x

x xd x

x x

x x

x x

x x

-X x

x x

x x

x x

x x

x x

x x

Xe x

x x

x xc*

x x

x x

. Xe x

x x

x Sine* *the.. proceH *trUlll8 or buildiq ventilation aysU.. are routed to the plant nnt, the need for a contilluoua *ldtor at the indirldaal dia-charge point to the -in exhaust duct is el:lainated.

One continuous monitor at th* final relu.e point u aafficient.

x x

x x

x x

x b

Continuously ll!01litored.

Also includes continuous iod1.ne, noble gas and *particulate monitors whi~h are in service during waste gas decay tauk releaae*

and containment purging operations.

I.

c Crab.-ple atatioa.9 from which llOllthlJ pe aaples (Table 2.3-2) ~re to 'be takan. Also, grab samples ahould be: taken au aeaaured to decemina the*

procees *tram 'or IMailcliq ventilation *111te11 eourca ubenaver so uoexplai!led iocreu* ia indicated by the plmlt Tent NBPler-monitora *.

d Include11 continuous _noble gas monitor Which monitors this location at all tiaea other than waste decay tank releaau mid.ccmtai.-eat.tNrliDI operatt...~

Noble Gas Radionuclide N.

w I

N Kr-83m

~

Kr-85m Kr-85 Kr-87 Kr-88 Kr-89 Xe-131m Xe-133m Xe-133 Xe-135m Xe-135 Xe-137 Xe-138 I.

~

~ j

~ )

TABLE 2.3-5 GAMMA AND BETA DOSE FACTORS FOR SALEM, UNITS 1 AND 2 Dose Factors for Vent 8.6 x 10-5 0

0.043 0.97 1.8 1.0 0.012 1.6 0.012 3.0 12

3. l 7.4 2.8 7.8 1.3 12 1.4 0.34 0.57 0.43 0.26

1. 2 0.36

o. 31 0.37 0.38 1.2 0.85 1.3 1.4 2.2

1. 5

0. 18 15 0.19 2.9 5.0 3.0 0.35 2.4 2.3 12 3.5 13

1. 3 1.8 1.3 0.89 2.9 15 5.7

• J

3.0 ENVIRONMENTAL SURVEILLANCE The objective of the Environmental Surveillance Program 'is to determine the effects of plant operation on the ecosystem.

The program is designed to accomplish this objective through periodic sampling and analyses of key parameters in the vicinity of the Salem Nuclear Generating Station. The key parameters selected for monitoring are those that could reasonably be expected to be affected by plant operation.

Comparison of surveillance data with preoperational "base-line levels will reveal changes and trends that could be attributed to plant operation.

As operatin~

experience and surveillance data are obtained, the Environmental Surveillance Progra*m will be modified to reduce or eliminate surveillance of those parameters that have not been significantly affected by plant operati_on

• 3.0-1 I

3.1 NONRADIOLOGICAL SURVEILLANCE 3.1.l ABIOTIC 3.1.1.1 Meteorological Monitoring Objective The *objective of meteorological monitoring is to adequately measure and document meteorological conditions at the site.

Spec ifi cation

-The meteorological monitoring system shall confonn to the reconvnendations in Regulatory Guide 1.23,. Onsite Meteorological Programs, dated February l7, 197~!._

and. consist of instruments to measure wind speed and direction, air. temperature and vertical air temperature differences at heights above ground that are representative of atmospheric conditions that exist at all gaseous effluent release points, as described in Section 3.3.3.4 of the Safety Technical Specifications.

Reporting Requirements Meteorological data shall be surrnnarized and reported in a fonnat consistent with the recommendations of Regulatory Guide 1.21, Measuring, Evaluating, and Reporting

. 3.1-1

Radioactivity in So*lid Wastes and Releases of Radioactive Materials in Liquid and Gaseous Effluents from Light-Water-Cooled Nuclear Power Plants, Revision 1, dated June, 1974 arid Regulatory Guide 1.23, Onsite Meteorological Programs, dated February 17, 1972, and observations in a fonn consistent with National Weather Service procedures.

Summaries of data.and observations shall be available to the U. S. Nuclear Regulatory Commission upon request. If the outage time of any of.the required meteorological instruments exceeds seven consecutive days, the total outage time and dates of outage, the cause of the outage, and the instrument(s) involved shall be reported within 30 days of the initial time of the outage to the Director, Offke of Nuclear Reactor Regulation.

Any modifica-tions to the meteorological monitoring program as described above shall have th~ written approval of the Director, Office of Nuclear Reactor Regulation, prior to i niti at ion_ of the modifi.cation.

Bases The collection of meteorological data at the plant _site will provide information which may be used to develop atmospheric diffusion parameters to estimate potential radiation doses to the public resulting from actual routine or accidental releases of radioactive materials to the atmosphere. A meteorol.ogical data collection program as described aboye is necessary to meet the requirements of sub-paragraph 50.36a (a) (2) of 1-0 CFR Part 50, Appendix E to 10 CFR Part 50, and 1 O C FR Pa rt 51.

3. 1-2

3. 1. 2 BIOTIC See Appendix B Part II, Non-Radiological

• 3.1-3

3.2 RADIOLOGICAL SURVEILLANCE Objective.

• i; An environmental radiological monitoring program shall be conducted to assist in verifying that radioactive effluent releases are within allowable limits.and

. that plant operations have no detrimental effects on the environment.

Specification 1..

Environmental samples shall be tollected and analyzed in ac~ordance with Table 3.2-1.

The sample locations are described in Tabl~ 3.2-1.

2.

The analytical techniques used shall be such.that the detection capabilities in Table 3.2-2 are achieved.

3.

Reports shall be submitted in accordance with the requirements of Specific~

ation 5.6.

• z

4.

During the seasons that animals producing milk for human consumption are on pasture, samples of freshmilk shall be obtained from these animals at the locations and frequencies shown in Table 3.2-1, and analyzed for their

. radioiodine content (calculated as 1-131). Analyses shall be performed within eight days of sa~pling.. Suitable analytical prricedures shall be used to determine the radioiodine concentration toa sensitivity of o.s*

I.

3.2-1

p;.cocuries 'per liter of milk at the time of sampling.

For activity levels

'at :or above O *. 5 *pi cocuri es per 1 i ter, the detenni nate error of the analysis shall :be within+ *25%.

Results shall be reported, with associated calculated error, as picocuries of 1-131 per liter of milk at the time of sampling.

5.

~ census Df milk animals within a 1-mile radius from the plant site or wi:thin.:the 15 -mrem/yr isodose line, whichever is larger, shall be conducted at the beginning ~nd at the middle of each grazing season by using a door

to door.or equivalent counting technique to determine their location and

,numb~r.with respect to the site. A census shall be conducted within a 5-mile radius :for cows and goats, with enumeration by using referenced infonnati on from county c:lgri cultural agents or other reliable sources.

If lt.is learned from this census that milk animals are present at a location whlch yields a calculated infant thyroid dose greater than any other sampled l a*cations, the new location shall be added to the survei 11 ance

.program. The infant thyroid dose shall be calculated. using the equations and assumptions presented in Regulatory Guide 1.109, Calculation of Annual Doses -to Man from Routine Releases of Reactor Effluents for the Purpose of Eva'luati~g Compliance With 10 CFR Part 50, Appendix I dated March 1976.

Following the addition of any new location, a sampling location yielding a 1 ewer calcul a,ted dose may then be dropped from the survei 11 ance program at

the *end *of the grazing season during which th,a census was GOnducted.

3.2-2

Any locations from which milk can no longer be obtained may be dropped from the surveillance program.

The Conunission shall be notified in writing that milk animals are not l~nger present at the location or suffi-cient quantity of milk cannot be obtained or there exists a lack of coop-eration in obtaining samples. A new sampling location shall be specified to replace the dropped location. The new location shall be one which represents the next greatest calculated infant thyroid dose.

If the calculated dose to a child's thyroid at any location where there is an animal producing milk for human consumption exceeds 15 mrem/yr,. mi.lk sampling shall be done weekly with I-131 analysis being performed on each sample.

6.

A census of gardens producing fresh leafy vegetables for human consumption (e.g., 1 ettuce, spinach, etc.) sha 11 be conducted near the end of the growing season to determine their location with respect to the site. This census is limited to gardens having an area of 500 square feet or more and shall be conducted under the following conditions:

1.

Within a 1-mile radius of the plant site, enumeration by a door-to-door or equivalent counting technique.

3.2-3

2.

If no milk-producing animals are located. in.the vicinity of the site, as detennined by Specification 4 of Section 3.2, the census described in item 1. above shall be extended to a distance of 5 miles from the site.

If this census indicates the existence of a garden at a location yielding a calculated thyroid dose greater than that from the previously sampled garden, the new*location shall replace the garden previously having the maximum iodine concentration. Also, any location from which fresh leafy vegetables can no longer be obtained may be dropped from the surveillance program.

The NRC shall be notified in writing that such vegetables are no longer grown at that location.

7.

Deviations shall be pennitted from the required sampling schedule if specimens are unobtainable due to hazardous conditions, seasonal unavail-ability, or malfunctions of automatic sampling equipment.

In the case of the latter, corrective action shall be completed prior to the end of the next sampling period, if possible. Any location from which environmental monitoring program samples can no longer be reasonably obtained may be dropped from the surveillance program.

The NRC shall be notified in writing of the reasons for this action; Any location which is dropped shall be replaced by a suitable alternate location.

3.2-4

~..

' I.

Reporting Requirement An annual report shall be submitted in accordance with the requirements of Specification 5.6.l.

Non-routine reports shall be submitted, as required, in accordance with Specification 5.6.2.

Bases The magnitude and fl u~tuati~n. of radi oacti vi ty levels in the environment surrounding the plant have been determined during implementation of the pre-operational environmental radiation monitoring program.

This information serves as a solid baseline for evaluating any changes in environmental radio-acti.vity levels during plant operation. The operational environmental radiation monitoring program was derived using the preoperational environmental radiation monitoring program as a basis.

The monitori.ng program utilizes a series of sampling locations which were determined by consideratic;m of the spatial distribution of station effluents, including areas where concentrations of effluents in the environment are expected to be greatest, site meteorology, population distribution* and eas*e l)f ac~ess to the sampling stations. The selection of sampling media was based on an evaluation of potential critical pathways of radiation exposure to man.

Coneurrent s4mpling at control.and indicator stations permits plant-produced radionuclides to be_ distinguished from other sources of rapionuclides.

3.2-5

EXPOSVU PATHWAY

1. ~

11.

(a) P A

R T

1 c

u L

A T

E s (b) I 0

D I

N E

~

STATION CODE 1001 251 lFl 2F2 3H3 16El 1001 16El 2F2 251 3H3 10!)1 16El jGl 3H3 lFl 2F2 5Dl 2Fl 2El 251..

TAIL! 3.2-1 OPERATIOllAL tl!VlllONllEllTAL IWllOLOGICAL HOHITOIIllG Plt.OOIAll LOCATION 3.9 ll1 5511 or vent on aite 5.8 ai N of vent

8. 7 11i: li'llE of vent 110 at !IE of mt* ti.on 4.l*ai llNW of* vent 3.9 Iii SE of vent 4.1 mi llNW of vent NJ; 8. 7 ml NN1! of vant on ntte:

UO 11i NE of vent 3.9 Iii SSW of \\'Cnt 4.1 mi NH\\l.of vent 16.6 11ilee NE of vent 110 mi NE of station S.8 mi N of v~nt.

NJ; 8. 7 mi NllE of vent 3,S Iii E of vent 5 111 llNE of vent

4. 4 111 RllE of vent on aite COLLECTION METHOD

& Fl!!Q!IP!CT Continuou* l;;,, voluaa air sampler.

Sample collected every week along with filter change A TEDA inipregnated charcoal flow-through cartridge ia connected to air particulate air aaiapler and i* collected

-.u,.

10 soil plugs to a depth2of 6

11 over an area of 25 ft are coopol!lited and sealed in.a pln.*tic bag at each" location* A aaaple will be collected from each location once every 3 yeara TTPI!. ' FllEQUl:liCT 01 AIW.!SlS co.poaite Sr 89 co.poaita Sr 90 perfor.ed quartarlJ C:roaa Mta anal191e oa eacll -*kl7

...,1.,._. -1t1r*

COllpOaition Gmma acan quart*rlJ Iodine 131 1nalyoH ere performed veeklJ Ganaa apectrometry perforaed on each sample on collection Sr-90 analyaea on one all!lple frDll each location on collection

• Soil... ples are taken in accordance with procedure* outlined in HASL-300 (Rev. 5/73),

If a auitable...,le cannot be obtainad at

• location,

• aampla *hall be obtained fra11 a new location.

Tha 111!.C aball be notified in writing of the new aampla location.

Control Stadon

• • C...... apectr011&try ahall ba perfonled if arona beta eJOCaade four ti11aa the control atatioa value.

3.2-6 i

EXPOSURE PATHWAY Ill.

DIRECT IV

• l!!!:!]!

(*) s u

ii F

A c

E (b) G R

0 u

N D

(c) D R

I N

K I

N G

STATION CODE 1001 16El 2F2 lJFl lFl JGl JHl

+

2Hl 651 751 14Dl 1051 lW

+

12Cl 7El 451 3El 2F3 (uv)

~ ConLrol Station

. t.Ui.! ). 2-1 (Coni:. )-

OP!RATIOIW. l!lfl'llONll!Jn'AL IADIOLOGICAL MONlTI>!l1!9.Pl!09!A,!!

LOCATION 3.9 ml SSW l'f vent 4.1 *mt NNW of vent

8. 1. mi NNE of vent Hlddletovn, Del; 9.8 mi le* W of vent S.8 mi H of nat

16. 6 mile* NE of vut 32 mi NE of vent 38.5 ml NNE nf vent

• 2 miles ESE of vent Statton personnel gate J. 9 mi llNll of vent COLLECTION METH00

' FREQ!!!NCY 2 doe1.8ete*ra vlll be collected frOG each location quarterly CooUni vater inl~t; }. At _leit*t one*dodmeter collected 150 ft SSW of vent from tble location quarterly Approximately 650 ft SW of vent 2-1/2 mi WSW of vent 1 mi. W of Had BorH Creek; 4.5 ai SE of vent on site 4.S mi NE of vent Salem. Water NNE of.vent Tvo gallon ample to be collected monthly providing winter icing condition* ellov eample collection Two gallon grab sample 1* collected flDllthly 50 al *liquot 1* taken daily and compoaited to a aollthly aaapl* of tv0 a*llona 3.2-7 TYPll ' rREQUEllct OF ANALYSIS Gaaaa do*e-quart11rly G..,... ecan llDnthly H-3, Sr-89 and Sr-90 analyHe of quarterly coaposl taa Gmaa scan -

QC B-3 aoalJ*** ere done llDnthly Groaa beta oonthly Gamma acan. -

QC H-3 monthly Sr 89 and Sr 90 analyaeo oa quart.er 17 compo1l te*

!':D':!SUll n.T51AY STATlOll CODE v **

AQYA:""IC 711 I

!I r

.. 12Cl lil 0

s llil VI.

DIG!STICM (a) M I

L

)[

. (b) p 1

s R

(c) C R

A II (d) "J"l!nTS or VEGET.lTIOll (e) G A

11*

I!

l5f l 2'1 5'1 1411 3Gl llAl

+ l2Cl lLU

.. 12Cl

+

lGl 2!1 "2Pl QC

• Quarterl7 coapoeit*

J;EX

• location ginn at t:!me of collecCion.

Till.! 3.2-1 (Cont.)

OP!UTIDllAL l!llVllOIM!lrfAL IWIIOLOGICAL llOlllTOl.IllC PIOGIAK LOCATIOll l ai V of M&d Horse Creek; 4.5 ill SE of Vent 2-1/ 2 d VSV of v,,..t Outfall ar~; 650' SV of Yeat 5.2 "'1 NW of vent 5 ai 11111! of vant 6.5 d E of vent 5.5 ai 'WHll of vent 16.6 dlH NE of nnt Outfall area; 650' SV of v~t 2-1/2 *1 VSV of vant Outfall**area; 650' SV of Vl!Dt lfaat. ~

11rpo1t.ta Artif1c1&1 Ialand, 2.:.i12 *1 VSV of Yl!Dt

10. 2 *ilea II. of vent 4.45 a1 1111! of vent 3 111 NNE of vent

}

....-a-s-~.. ~

~

-.,_....... a... --.

Station v1cin1t7 uot

• id* o~ **tuary W**t aide of **tuary, 3-5 m'fr.. vant Vithln 10 *1 of Station J

}

COLLECTION ll!'nlOD

• PllQYDC!

A benthoo -le coneiatina of benthic organiama and aoaociated aedt.ent ia taken ooaiannuall7.

Four gallon 1rllh aa11plll of fre1h nilk 18 eollected fr.. uch fana **i--thly.

Collected -kly if calculatad doH exceed* ll *r-to child'*

thyroid.

Tvo key oamplH of fi*h ara aaalad in plaetic ba11 or jar and froaen

... 1-annually or vllan in 1ea1oa Tvo key aaapl** of crab ara

• aealed in

• plHtlc bag or jar and frozen.

aeai-annualiy or vllen in 1eaaon Sompleo are collected during the normal har-vaet sueo11, *aaled in pU.etic, and frozen if periahable. Sufficient aaapla io collected to yield 500...... of dey weight and done annually ltoekrate are eldmiad and frozen 1-1-amwally llaaf portion of eov i****

&a11pled and f roaen H*i-annually

"**

• Thia -le ia aubjec.t -to *availability of alaughtered cov Control Station 3.2-8 TYPE

• nEQU!llCY OP ANALYSIS Ga.... 1pectronoetry of Heh """'1*

1en1-*imo.el1y; Sr-89.net Sr-90 a-111 on 01'98nl.. 1, Sf'-90 **I-annually on tedll!!ent C-ocan -nthly; Sr-89 llDd *r-90 90Dthl,.; I-131 D<>nthly 1-lll -Uy 1f cdculatlld dose micaede 15 **

to child' a thyroid a-ocan of edible portion on collact1011 c..... acan of edible portion OD collect1011 lladioiodine dete.. ination of gr HD leafy vegatablea on collection Gmma 1can on collection eca11 OD adibl*

portion only on col-lection

~

~

TABLE 3.2-2 SENSITIVITY LEVELS FOR ENVIRONMENTAL SAMPLE ANALYSES SAMPLE TYPE Air Particulates Air Iodine Soil Thermo luminescent Dosimeters..

Surface water Ground water Drinking water Benthos Fish

• .TYPE OF ANALYSIS Gross beta Ganma scan Sr 89 Sr 90 I 131 Gamma scan Sr 90 Ganma

• Ganvna scan*

Tritium Sr 89 Sr 90 Gamma scan Tritium Gross beta Ganvna scan Tritium Sr 89 Sr 90 Ganma scan Sr 89 Sr 90 Ganma scan 3.2-9

~-

SENSITIVITY*

4.4 x 10-14 µCi/ml.

1 X l o-14 II II 5 X 1 o-15 II II 1 X l o-15 II II 4 X 10-14 11 11 1 x 10-i

µCi /g~dry 5 X 10-8 II II approx. 5mrem/yr

-9 1 x l 0. -. µCi/ml---**'""---*-*

2 x 10-1 5 x io-9 1 x i o-9 1 x l o-9 2 x 10-1 l x 1 o-9 l x 10-9 2 x 10-1 5 x 10-9 1 x 1 o-9 II II II II II II II II II II II II II II II II II II II II 1 x 10-7

µCi/g-dry 5 X 10-1 II H

.,. 1 o-7..

11 11 x

8 x 10-8

µCi/g-wet

TABLE 3.2-2 (Cont'd)

SENSITIVITY LEVELS FOR ENVIRONMENTAL SAMPLE ANALYSES SAMPLE TYPE TYPE OF ANALYSIS SENSITIVITY*

Milk Gan1tla scan l x 10-8 µCi/ml Sr 89 5 X 10-9 II II Sr 90 l X l o-9 II II I 131 5 x 10-1011 II Fruits and Vegetables Gamma scan 5 x 10-8 µCi/g-wet I 131 5 X 10-8 II II Gamma scan 8 X 10-8 II II Gamma scan 8 x 10-8 II II

• The sensitivity of the garruna scan analysis are for Cs 134 and Cs 137 and are at a 95% confidence level.

3.2-10

~

4.0 SPECIAL SURVEILLANCE AND STUDY ACTIVITIES None

• 4.1-1

5.0 ADMINISTRATIVE CONTROLS Administrative Controls below apply to Appendix B Part I only.

5. 1 RESPONSIBILITY 5.1.2 The implementation of the surveillance programs external to the plant, including sampling, sample analysis, evaluation of results and the preparation of required reports is the responsibility of the* Licensing and Environment Department in the Engineering and Construction Department.

This Department is responsible for t~e assignment of personnel to the above functions, for assurance that appropriate written procedures, as described in Section 5.5.1, are utilized in the surveillance program activities and for assur-ing the quality of surveillance program results, as described in Section 5.5~3.

The Station Manager or his delegated alternate is responsible for operating the plant in compliance with the limiting conditions for operation as specified in the Environmental Technical Specifications and for the in-plant monitoring necessary to ensure such operation.

His responsibility includes assurance that plant actjvities are conducted in such a manner as to provide continuing protection to the *environment and that personnel performing such activities use appropriate written procedures as.described in Section 5.5.

5. 1-1

5.2 Organization 5.2. 1 Figure 6.2-1 of the Radiological Safety Technical Specifications (Appendix A) identifies the corporate relationship between the Licensing and Environment Department and the station Manager and also shows the organization of the Licensing and Environment Department.

Figure 6.2-2 of the Radiological Safety Technical Specifications (Appendix A) identifies the Production Department Station Organization.

5.2.2 The Nuclear Review Board (NRB) and Station Operations Review Committee (SORC) are shown in Figures 6.2-1 and 6.2-2 of the Radiological Safety Technical Specifications (Appendix A).

They are advisory groups to the Vice President - Production and the station Manager respectively.

5.2-1

UT N

I l\\J I

OENERAl MANAGER -

ENGINEERING r - -- -

I ON-SITE I

SENIOR VICE PRESIDENT -

lNEROY SUPPLY*

ENGINEERING VICE PRESIDENT -

VICE PRESIDENT -

VICE PRl SIDE NJ -

lNOINEERINO PRODUCTION f\\lf L SUPfl Y ANO CONSTRUCTION NUCLEAR REVIEW I

BOARD GENERAL MANAGER -

MANAGER-GENERAL MANAGER -

GENERAL MANAGER -

LICENSING*

ENVIROflMlNT I

Q.A.

ENGINEER STATION Q.A.

.ENGINEER (SALEH)

DUALITY ASSURANCE EUCIRIC PRODUCTION FUEL. SUPPLY NUCLEAR Pl ANT ENGINEER I

I I

MANAGEft -

MANAGER-NUCltAR IAl EM GE NE RA TINO OPERATIONS ITAHON 1

HEALTH HUCUAR FUEL CYCLE ENGINEER PHYSICIST FIGURE 5.2-1 RESPONSIBLE FOR OVERA LL RAM FIRE PROTECTION PROG OFFSITE ORGANIZATION FOR FACILITY MANAGEMENT-AND TECHNICAL SUPPORT

\\

5.3

5. 3.1 REVIEW AND AUDIT NUCLEAR REVIEW BOARD (NRB).

The NRB shall have the following responsibilities concerning the environmental i~pact of the plant:

1.

NRB shall review:

a; Proposed Environrrental Technical Specification changes or license amendments.

• b.

Violations of Environmental Technical Specifications.

c.

Environmental Monitoring P~ogram and Evaluations.

d.

Routine and non~routine reports required by the Environmental Technical Speci fi c,ati ons.

2.

The NRB shall, at least once each year, conduct (or cause to have conducted) and evaluate audits of:

a.

Plant bperation to assure Environmental Technical Specification compliance.

b.

Monitoring program sampling practices to assure they adhere to program schedule and appropriate procedures.

5.3.2 STATION OPERATIONS REVIEW COMMITTEE (SORC)

The SORC shall have the following responsibilities concerning the environnental impact of the plant:

l.

Review plant procedures which have a potential impact on the environment.

5. 3-1

r

2.

Review proposed changes to the Environmental Technical Specifications.

3.

Revi~w environmental monitoring program results and evaluations.

4.

Review routine and non-routine reports required by Section 5.6 prior to their submittal to the Contnission.

• 5.

Investigate all violations of Environmental Technical Specifications and recoJTilllend corrective action to prevent recurrence.

,.,.... ;._*a)-.

5.3-2

• I.

r

• I I..

~.4 ACTION TO BE TAKEN IF A LIMITING CONDITION FOR OPERATION IS EXCEEDED

5. 4. l 5.4.2*

Remedial action as pennitted by the Environmental Technical Specifica-tion shall be taken until the condition can be met.

Exceeding.a limiting condit.ion for operation shall be investigated by the Station Operation Review Comnittee.

5.4.3 A report for each occurrence shall be prepared and submitted as specifie' in Section 5.6.2 *

. 5. 4-1

5.5

5. 5. 1

*** 5.5.2 1***

I 5.5.3

... 1 **

PROCEDURES

~-. **--~..

Detailed written procedures, including* apJ>11c;~b:le i c~~ck J 1sts and instructions, shall be prepared and fo.llowed for all-activities involved in carrying out the Environmental Techriic*1_ Sp~cifications. Procedures for the environmental surveillance and special st~dy programs described in Sections 3 and 4 shall be pr'epared by personnel responsible for the particular monitoring program.

Procedures shall include sampling.

-- data recording and storage, instrument' calibration, measurements and analyses, and actions to be taken when limits are approached or exceeded.

Testing frequency of any.alarms shall be included.

These frequencies sha 11 be determined from experience with similar instruments in similar environments and from manufacturers* technical manuals.

In addition to the* procedures specified in Section 5. 5. 1, the plant operattng_procedures shall include provisions to ensure the plant and all its systems and components are operated in compliance with the limiting conditions for-operation. established as part of the Environ-mental* Technical Specifications.

Procedures will be es tab 1 i shed to assure qua 11 ty results.

Procedures will include:

a.

Aud.its to assure organizations-perfonning program activities are following policy directives and are using the appropriate written instru~tions.

. 5 ~ 5-1

b.

A corrective action plan that identifies. controls and corrects deficiencies.

c.

A plan to investigate anomalous or suspect results.

5.5-2

5.6 PLANT REPORTING REQUIREMENTS 5.6.l ROUTINE REPORTS 5.6.1.1 Annual Environmental Operating Report 1.

A report on the radio 1 ogi cal en vi ronmenta 1 survei 11 ance programs for the previous 12 months of operation shall be submitted to the Director of the Regional Inspection and Enforcement Office (with copy to the Director, Office of Nuclear Reactor Regulation) as a separate document within 90 days after January 1 of each year. The period of the first report shall begin with the date of initial criticality. The reports.shall include sununaries, interpretations, and statistical evaluation of the results of the radiological environmental surveillance activities for the report period, including a comparison with preoperational studies, operational controls (as appropriate), and previous environmental surveillance reports and an assessment of the observed impacts of the plant operation on the environment.

If harmful effects or evidence of irreversible damage are detected by the monitoring, the licensee shall provide an analysis of the problem and a proposed course of action to alleviate the

• problem.

2.

Results of all radiological environmental samples taken shall be sunmarized on an annual basis following the fonnat of Table 5.6-1.

In the event that some results are not available within the 90.day period, the report shall be submitted noting and explaining the reasons for the missing results. The mi ~sing data sha 11 be s.ubmi tted as soon as possible in a supplementary.,;eport.

5.6-l

l

r..

~-

.. sr~ 66 l *! 2£'.:

RadJ oactif vec: Effluents Re 1 ease Report

11.

A~repprt~om1th~Jradj6acti~e~discharges released from the site during-the p,r;-ev*ious*;6~:mon*th-s~~of-*operation shall* be. submitted to the D.irector of the Regjona:l Inspection :and*:: Enforcement Office -(with copy to the Di rector, Office of'?Nticlear. Reacto~*Regulation-) within 60. days.after. January l and.July 1 of each"~year;.. Tneurepprt:.:.shaJ 1 include a surrmary of the quantities of radio-ac::tive~! l:i qui d-:jand:-:g!'.!seouseffl uents and __ so.l id *waste released from the plant a.sso.utrit1ed,-::.irr*Reference'~ 1,, with data.' summarized on a-quarterly basis f6*l 1 owi ngg th'e:: f onnattof:' Appendix

• s* thereof.

2~l..

The~: repprt.-. sha:J r it1cH1de::: a: su1TTI1ary, of the meteorol ogj cal conditions concurrent wof*thr;the': reTease-~ofi-gaseous~ effluents during each quarter as outlined in Re.fe.renc:e:~ h.. w,i th" data: summar.i zed*~ on a: quarterly basis fol lowing the format o-f-?Append:ix*'. e~:: ther-eof~ Cakulated. offsi~e dose to humans result~ng fr~m ~~~ "'......

• release2of*:eff1uents:c,and;the.ir *subsequent dispersion in the atmosphere shall b'.e,::repor,ted:'.asc~ recorrmended-; i n**

Reference:

' 1.

S!i6\\S2;~13 Nonroutine-.E'i'i-v*ironmenta:l *operating 'Reports.

Mrep_orttshallibe2subirritted.'fo :the-event that (a) a limiting condition for operation issexceeded::{as~*specified'irl:Section 2~0-, "Limiting Conditions for Operation"),

(o~))ai1repprt*~le-ve:l'iS:reacb;ed.:as*specified* in* section 3.0, "Environmental Surveillance"}

• or,r(c*)}anr-,unusuaror:important event occurs that ~auses a.:signif1cant environmental imp~ct*~., that~: affects--. potential envi ronmenta:l *impact: from plant operation, -that ha:s:s h!igb'*, pub*ri c.~or.:*-potentia-1: public interest* concerning -environmental impact from p;lanttoperati om-5 ~ 5.,.2.

• ---i---*

Rep9rts shall be submitted under one of the report schedules described below.

i

• \\

l.

Prompt.Report.* Those events requiring prompt ".'ePOrts 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 transmission to the Director* of the*

Regional Inspection and Enforcement Office {with copy to the Director, Office of Nuclear Reactor Regulation).

2.

30-Day Report.* Those events not requiring a prompt report shall be reported within 30 days by a written report to the Director of the Regional Inspection and Enforcement Office (with copy to the Director, Office of Nuclear Reactor Regulation).

5.6.2.2 Nonroutine Radiological Environmental Qpe.rat1ng Report

1.

Anomalous Measurement Report If a confirmed measured level of radioactivity in any environmenta.1 medium exceeds 10 times the control station value, a written r_eport shall0 be Written 10-day and 30-day reports and, to the extent possible, the preliminary telephone, telegraph, or facs1mile reports shall (a) describe, analyze, and

~valuate the occurrence,*including extent and magnitude of the impact, {b) describe the cause of the occurrence, and (c) indicate the *corrective action (including any significant changes made in procedures) *taken to preclude repe-tition of the occurrence and to prevent similar occurrences involvi.ng similar c;omponents or systems.

Note:

The significance of an unusual or apparently important event with regard to environmental impact may not be obvious or fully appreciated at the ti me of occurrence., In such cases, the NRC sha 11 be i nfonned promptly of changes in the assessment of the significance of the event and a corrected report shall be submitted as expeditiously as possible *

'5.6-3

submitted to the Director of the NRC Regional Inspection and Enforcement Offi~e (with copy to the Director, Office of Nuclear Reactor Regulation) within 10 days after confinnation.

This report shall include an evaluation of ~my rel ease conditions, environmental factors, or other aspects necessary

.to explain the anomalous result.

2.

Milk Pathway Measurements*

a.

If milk samples collected over a calendar quarter show average I-131 concetitrati ens of 7. 0 pi cocuri es per 1 i ter or greater, a written report and a plan shall be submitted within 30 days advising the Commission of the proposed action to ensure the plant-related annual doses will be within the design objective of 15 mrem/yr to the thyroid of any meni>er of the general public.

3.

Fresh Leafy Vegetable and Inhalation Pathway Measurements*

If green lea!.y vegetable samples collected.. over a calendar. qua_r~~t.s_~Qw,._.....

average I-131 concentrations of 220 picocuries per kilogram or greater, a written report and a plan shall be submitted within 30 days advising the Commission *of the proposed action to ensure the plant-related annual doses will be within the design objective of 15 mrem/yr to the thyroid of any member of the general public.

• ~*

• If air samples collected over a calendar quarter show average concen-trations of I-131 of 2 pi cocuri es per l:ub1 c meter or greater, a wri tteri

• • :Mil:kpathway measurements apply when this pathway is controlling with respect to atmospheric radioiodine releases *. If the milk pathway is not controlling then th~ :r-eporting requirements for the fresh leafy vegetable and inhalation pathway are in effect.

5.6-4

report and a plan shall be submitted within 30 days advis.ing the ColTITlission of the proposed action to ensure the plant rel_ated annual doses will be within the design objective of 15 mrem/yr to the thyroid of any member of the general public.

c.

If statistically.significant variations of offsite _environmental radionuclide concentrations with time are observed, a comparison of these results with effluent releases shall be provided in the Annual Operating Report.

5.6.2.3 Nonroutine Radioactive Effluent Reports

1.

Liquid Radioactive Wastes Report.

If the cumulative releases of radioactive rr.aterials in liquid effluents, excluding tritium and_d_issolved ga~~.s.* should exceed one-half the design objective annual quantity during any c~_lendar quarter, the 1 i censee shall make an investigation to identify_ the caus~s _Qf

• .~- -:,

J

~,'

such releases and define and initiate a program of action to reduce such releases to the design objective levels. A written report of these actions

~

~.

~.-

~hall be submitted to the NRC within 30 days from the end of the quarter during which the release occurred.

2.

Gaseous Radioactive Wastes Report.

Should *the conditions (a), (b), and (c) listed below exist, the licensee shall make an. investigation to identi;fy the I

causes of the release rates and define and initiate a program. of action to reduce the release rates to design objective levels. A written r~port of these actions shall be submitted to the NRC within 30 days from the end of the quarter during whic;h the releases occurred

• 5.6-5

I: *:.:.

1:::::::.

a.

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

b.

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

c.

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

3.

• Unplanned or Uncontrolled Release Report.

Any unplanned or uncontrolled offSite release of radioactive materhls fo excess of 0.5 curie_ in ~~~d _ _:- ~--*

in excess of 5 curies of noble gases or 0.02 curie of radioiodines in gaseous for~ requires notification.* This notification must be made by a written report within 30 days to the NRC.

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

5.6.3 CHANGES IN ENVIRONMENTAL TECHNICAL SPECIFICATIONS 5.6.3.l A report shall be made to the Commission prior to implementation of a change in plant design, in plant operation, or in procedures described I

in Section 5.5 if the change would have a significant effect on the environment or involves an environmental matter or question not previously reviewed and evaluated by the Commission.

The report shall incl4de a description and evaluation of the changes and a supporting benefit~cost analysis.

5.6-6

5.6.3 Request for changes in environmental technical specifications shall be submitted to the Director, Office of Nucle*a*r,~eactor Regulation, for

. review and authorization.. The request' shall. inC"lude ati evaluation of the environmental impact.of the proposed change and a supporting ben~fit~cost analysis

• 5.6.3.3 Changes or a,dd_itions to permits and certificates required. by Federal,

. State,. local, and ~io~~l _authorities for the protection. of the environ-References ment will be reported.

When the r~quired changes are sub~itted to the concerned agency for approva 1, they wi 11 a 1 so be s ubm1 tted to the Director, Office of Nuclear Reactor Regulation, for informatfon.

• The submittal will include an evaluation of the environmental; impact of the change.

1.

. ReQulatory Guide 1. 21, Measuring, Evaluating and Reporting Radioactivity in i.,

Solid Wastes and Releases of Raditiactive M~terials in Liquid ahd Ga~eous Effluents. from Light-Water.:.cooled Nuclear Power Plants, Revision 1, June 1974.

5.6-7

(J1

O'I I co TABLE 5.6,.l ENVIRONMENTAL RADIOLOflICAL MONITORING PROGRAM

SUMMARY

Name of Facility _

Docket No.

Location of Facility

(~aunty, State~

Reporting Period Analysis and Lower Limit Number of Medium or Pathway Total Number of All Indicator Locat!ons Location with Highest Annual Mean Control Locations Nonroutine Sampled of Analyses Detection !f Mean b/

Name Mean §]

Mean b/

Reported (Unit _of Measurement)

Perfonned (LLD)

Range-£./

Distance and Direction Range 'pj Range-QI Measurements fl r Part1cu ates

( pCi /m3)

B 416 0.003 0.08 (200/312)

Middletown 0.10 (5/52) 0.08 (8/104)

(0.05-2.0) 5 miles 340° (0.08 - 2.0)

(0.05-1.40) y 32 137 Cs 0.003 0.05 (4/24}

Smithville 0.08 (2/4)

MDL 4

(0.03-0. 13) 2.5 miles 160° co.03 - o. 13) 140Ba 0.003 0.03 (2/24)

Podunk 0.05 (2/4) 0.02 {1/8)

(0.01-0.08) 4.0 miles 270° (0.01 - 0.08) 89sr 40 0.002 MDL MDL 0

90sr 40 0.0003 MDL MDL 0

Fish y

8 pCi/kg (dry weight) 137Cs 80 MDL MDL 90 (1/4) 0 134cs 80 MDL MDL MDL 0

60co 80 120 (3/4)

River Mile 35 See Column 4 MDL 0

(90-200)

Podunk River

~Minimum Detectable Level (MDL) is defined as 3crb where 6cr is defined as the standard deviation of the background count.

.!Y'Mean and range based upon detectable measurements only.

Fraction of detectable measurements at specified locations is indicated in parentheses

£/Nonroutine reported measurements are defined in Section 5.6.2b.

~Note: The example data are provided for illustrative purposes _only.

'(

5.7 5.7.1

..* 5.7.2 RECORDS RETENTION Records and logs relative to the following areas shall be made and retained for the life of the plant:

a.

Records and drawings detailing plant design changes and modifications made.to_syste~ and equipment as described in Section 5.6.3.

b.

Records of all data from environmental monitoring, surveillance, and special surveillance and study activities required by these environmental technical specifications

• All other records and logs relating to the environmental technical specifications shall be retained for five years following logging or recording.

5.7-1

APPENDIU TO FACILITY Q.PERAJ.llill_LICENSE NO, _ _.DP.R::l.5

. SALEM_ NUCLEAR GEfil.RAIING STATION UNIT 2 PUBLIC SERVICE ~LECTRIC AND ~AS COMPANY DOCKET NO. 50:311.

ENVIRONMENTAL TECHNICAL SPECIFICATIONS PART II - NON-RADIOLOGICAL MAY 1981

I,,

I SALEM NUCLEAR GENERATING STATION UNIT 2 ENVIRONMENTAL TECHNICAL SPECIFICATIONS (NON-RADIOLOGICAL)

TABLE OF CONTENTS Section

1.

Definitions................................................

1-1

2.

Limiting Conditions for Operation..........................

2-1

3.

Environmental Monitoring...................................

3-1 4.

Special Studies and Requirements...........................

4-1 4.1 Exceptional Occurrences...............................

4-1 4.2 Special Studies.......................................

4-1

5.

Admi ni strati ve Contra ls....................................

5-1 5.1 Re~ponsibility........................................

5-1

5. 2 Review and Audit......................................

5-1 5.3 Changes in Station Design or Operation................

5-2 5.4 Station Reporting Requirements........................

5-3 5.5 Changes in Environmental Technical Specifications and Permits.........................................

5-4 5.6 Records Retention.....................................

5-5

1.

DEFINITIONS Annually:

Annually is once per calendar. year at intervals of twelve calendar months ! 30 days.

Clean Water Act:

Federal Water Pollution Control Act (FWPCA) as amended.

NPDES Permit:

NPDES permit is the National Pollutant Discharge Elimination System Permit No~ NJ0005622 issued by the U.S. Environmental Protection Agency to Public Service Electric and Gas Company (PSE&G).

This permit authorizes PSE&G to discharge controlled waste water from the Salem Nuclear Generating Station into the* Del aware River.

Site:

The site includes 'the 700 acre exclusion area.

Offsite includes all other areas.

Station:

Station r~fers to Salem Nuclear Generating Station Units l and 2.

1-1

2.

LIMITING CONDITIONS ~OR OPERATION None required.*

• In. consideration of the provisions of the Clean Water Act (33 USC § 1251, et seq.) and in the interest of avoiding duplication of effort, the conditions and.monitoring requirements related to water quality and aquatic biota are specified in the National Pollution Discharge Elimination System (NPDES) Permit No. NJ0005622 issued by the U.S. Environmental Protection Ag~ncy to th~ Public Service Electric and Gas Company (PSE&G).

This permit authorizes PSE&G to discharge controlled waste water from the Salem Nuclear Generating Station into the Delaware River.

The Nuclear Regulatory Commission will be relying on the N~DES permit limita-tions for protection of t~e aquatic environment from non-radiological effluents.

2-1

3.

ENVIRONMENTAL MONITORING 3.1 Aquatic Studies None required.*

3.2 Terrestrial Studies None required.

• In consideration of the provisions of the Clean Water Act (33 USC§ 1251, et seq.) and in the interest of avoiding duplication of effort, the conditions and monitoring requirements related to water quality and aquatic biota are specified in the National Pollution Discharge Elimination System (NPDES) Permit No. NJ0005622 issued by the U.S. Environmental Protection Agency to the Public Service Electric and Gas Company (PSE&G).

This permit authorizes PSE&G to discharge controlled waste water from the Salem Nuclear Generating Station into the Delaware River.

The Nuclear Regulatory Commission will be relying on the NPDES permit limita-tioris f6r protectio11 of ~he aquatic en~ir~nment from non-radiological eff)uents.

3-1

4.

SPECIAL STUDIES AND REQUIREMENTS

4. 1 Exceptional Occurrences 4,1.1 Unusual 6r Important Environmental Event~

Specification The licensee shall record unusual or important events that potentially could cause or indicate environmental impact related to &tation operation.

The

. following are ~xamples of ev~nts that should be recorded:

large numbers of birds colliding with station structures; onsite plant or animal disease outbreaks; unusual occurrence or mortality of any species protected by the Endangered Species Act of 1973; fish kills near the plant site; unanticipated or emergency discharges of waste water or chemical substances.

Reporting Requirement Should an unusual or important event occur, the licensee shall make a prompt report to the NRC in accordance with the provisions of Subsections 5.4.2.a and 5.4.2.c or Subsection 5.4.2.d.

4.1.2 Exceeding Limits of Other Relevant Permits Specification The licensee shall.notify the NRC of occurrences in which the limits specified in relevant permits and certificates issued by other Federal, State, and local

~gencies are exceeded and which are reportable to those agencies.

I Reporting Requirement The licensee shall make a report to the NRC in accordance with the provisions of Subsections ~i4.2.~ and 5.4.2.c or Subsection 5.4.2.d in the everit that a

.limit specified in a relevant permit or certificate issued by another Federal, State, or local agency is exceeded.

/

4.2 Special Studies None; 4-1

5.

AOMrnlSTRATIVE CONTROLS

~dministrative controls below apply to ~ppendix B - ?art II only.

5.1 Resoonsibilitv 5.1.l The implementation of the surveillance programs external to th.e ;;ilant.

including samoJing, sample analysis, evaluation of results and the pr~odrition o~ required reorirts is.tne resoonsibilitv of the Licensing and Envi~onment Department.

This Department is responsible for the assignment of personnel to the above. functi ans, for assurance that apprapri ate written procedures a re :Jti.1 i zed. in the s urveil 1 a nee program acti vi tie$ and for assuring the quality of surveillance program results.

5.1. 2 The Station Manager or his delegated alternate is 'responsible for operatinq the plant in compliance with the limiting conditions for operation as so~cified in the Environmental Technical Specifications and for tne in-ulant moni:oring necessary to en~ure such operation; His responsibility incluaes assurance that plant activities are conducted in such a manner as t.:> proviue continuing protection to~the environment and that personnel performing such activities use appropriate written proc~dures as described in Sect~an 5.5.

5.Z Review and Audit 5.Z. l Nuclear Review Board (NRB)

. The NRB shall have the fallowing responsibilities concerning the environment~!.

impact of the plant:

l.

NRB shall review:

a.

Propo$ed Environmental Technical Specifications changes or l1c~nsa amendments.

b.

Violations of'Envirom11ental Technical Specifications.

c.

Environmental*Monitoring Program and Evaluations.

• d.

Routirie and non-routine reports req~ired by th~ En~ironmenla; Technical Specifications.

2.

The NRB shall, ~t least once each year, conduct (or cause to nave :on~uctt~)

and evaluate audits of:

a.

Plant operation to assure Environmental Technical Specificat.iui1 comp 1 i am:e.

5-l

I I

I L__

b.

Monitoring program sampling practices to assure they adhere to program schedule and appropriate procedures.

5.2.2 Station Operations Review Committee (SORC)

The SORC shall have the following responsibilities concerning the environmental impact of the plant;

1.

Review plant procedures which have a potential impact on the environment.

2.

Review proposed changes to the Environmental Technical Specifications.

3.

Review environmental monitoring program results and evaluations.

4:

Review routine and non-routine reports required by Section 5.6 prior to their submittal to the Commission.

5.

Investigate all violations of Environmental Technical Specifications and recommend corrective action to prevent recurrence.

5.3 Changes in Station Deiign or Operation Changes in station design o'r operation affecting the environment shall be subject to the following conditions:

A.

The licensee may (1) niake changes in the station design and operation, and (2) conduct tests and experiments not described in this document without prior Commissi~n approval, unless the proposed change, test, or experiment involves a change in the objectives of the ETS, and/or an unreviewed environmental question of significant impact.

B.

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 in the final environmental statement (FES) as mociified by staff's testimony to the Atomic Safety and Licensing Board, supplements to the FES, environmental impact appraisals, or in any initial or final decisions of an Atomic Safety and Licensing Board; or (2) a significant change in effluents or power level as specified in Section 51.5(b)(2) of 10 CFR 51; or (3) a matter not previously reviewed and.evaluated in the documents specified in (1) of this section which may have a significant adverse environmental impact.

c.

The licensee sha'll maintain records of changes in facility design or operation made pursuant to this subsection.

The licensee shall also maintain r~cords of tests and experiments carried out pursuant to paragraph*

11A1' of this subsection.

These records shall include a written eval~ation ~hich provides the bases for the determination that the change, test, or expe~iment does not involve an unreviewed envi~onmental question of significaAt impact or constitute a change in the objectives of these ETS.

The licensee shall furnish to the Commission, annually or at such shorter intervals as may be specified in the lic~nse, a report containing 5-2

5.4

5. 4. 1 descriptions, analyses, interpretations, and evaluations of such changesi tests, and experiments.

Station Reporting Requirements Routine Reports Annual *Erivironmental Operating Report A report on the environmental surveillance programs for the previous 12 months of operation* shall be subm1tted to the Director of the Regional Inspection and Enforcement Offi"ce (with copy to the Director, Office of Nuclear Reactor Regulation) as a separate document within 165 days after January 1 of each year.

The period of the first report shall begin with the date of initial criticality.

The report shall include summaries, interpretations, and statistical eval~ation of the results of the non-radiological environmental surveillance activities (Section 3.0) and the environmental monitoring programs required by limiting conditions for operation (Section 2.0) for the report period, i~cluding a tomparison with preoperational studies, operational controls (a~ appropriate), and previous environmental surveillance reports and an assessment.of the observed impacts of the plant operation on tile environment.

If harmful effects or evidence of irreversible damage are detect~d; the licensee shall provide an analysis of the problem and a p-roposed course of action to alleviate the problem;

. For those programs concerned with water qua 1 i ty or protection of aquatic

• biota, which are regulated under the Clean Water Act, the requirements of this section shall be satisfied by submitting to the NRC copies of the reports as..

required by the NPDES permit (or otherwise required pursuant to the Clean Water Act), and in accordance with the frequency; content, and schedules set forth by the agencies responsible for implementing the Clean Water Act~

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 s9on as possible in a supplementary report.

The Annual Report shall also include a summary of':

1.

A 11 ETS 'noncomp 1 i ances and the corrective actions taken to remedy them:

2~

Changes made to applicable State and Federal permits and certifications,

3.

Chang~s in station design which could involve an environmental impact or ch~nge the findings of the FES.

4.

All nonroutine reports submitted per ETS Section 4.1.

5.

Changes* in approved ETS.

5.4.2 Nonroutine Reports A report shall be submitted i~ the event that an 11Unusual or Important Environ-mental Event, 11 as specified in Section 4. 1. 1 occurs, or if another relevant 5-3

permit is violated as specified in Section 4.1.2.

The schedule and content for these nonroutine reports are described below:

5.4.2.a Prompt Report Those events specified as re~uiring prompt reporting shall be reported 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 transmission to the NRC followed by a written report to the NRC within 30 days.

5.4.2.b Thirty~Day Report Those event~ not *requiring a prompt report as described in Subsection 5.4.2.a shall be reported to the NRC within 30 days of their occurrence.

5.4.2.c Content of Nonroutine Reports Written 30-day reports and, to the extent possible, the preliminary telephone, telegraph, or facsimile reports shall (a) describe, analyze, and evaluate the occurrence, includin~ extent and magnitude of the impact, (b) describe the cause of the occurrence, (c) indicate the action taken to correct the reported occurrence, and (d) indicate the corrective action taken (including any signifi-cant changes made in procedures) to preclude repetition of the occurrence and to prevent similar occurrences involving similar components or systems.

5.4.2.d Exc~pti6ns fo~ Matters Regulated Under the Clean Water Act For matter~ regulated**unde~ the Clean Wate~ ActJ the report schedules and content requirem~nts described in Subsections 5.4.2.a, 5.4.2.b, and.5.4.2.c shall be satisfied by submitting, to the NRC, copies of reports as required by.

the NPDES permit (or other regulations pursuant to the Clean Water Act) and in accordance with the s.chedul es and content requirements imposed thereby.

• 5.5 Ch~nges in Environmental Technical Specifications and Permits 5.5. l Changes in Environmental Technical Specifications.

Requests for changes in environmental technical specifications shall be submitted to the NRC for review and authorization per 10 CFR 50.90.

The request shall include ~n ev~luation of the environmental impact of the proposed change and a supporting justification; Implementation of such requested changes in ETS shall not commence prior to incorporation by the1 NRC 6f the new specifications in the license.

5.5.2 Changes in Permits and Certifications Changes and additions to required Federal (other than NRC), State, local, and

'regional authority permits and certificates for the protection of the environment shall be reported to the NRC within 30 days.

In the event that the licensee initiates or becomes aware of a request for changes to any of the water quality requirements, limits, or values stipulated in any certification or permit' issued pursuant to the Clean Water Act, the NRC*shall be notified withi~

30 days.

5-4

r.*

• If a permit or certification, in part or in its entirety, is appealed and stayed, the NRC shall be notified within 30 days.

If, as a result of the appeal process, the permit or certification requirements are changed, the change shall.be dealt wit~ as described in the previous paragraph of this section.

5.6 Records Retention Records and. logs relative to the environmental aspects of station operation _

sha 11 be niade and retained in a manner convenient for review and irlspect ion.

These reco~ds and logs shal) be made available to NRC on request.

5.6.l The following records shall be retained for the life of the station:

(a) Record of changes to these Ehvironmental Technical Specifications including, wheri applic~ble, records of NRC approval of such changes.

(b) Record of modifi~ations to station structures, systems, and components determiMed to potentially affect the continued protection of the environment.

(c)

Record of changes to pe~mits and certification required by Federal (other tha~ NRC), State, local, and regional authorities fo~ the protection of the environment.

(d) Routine reports submitted to the NRC.

5.. 6.2 Records of the f6llowing shall be retained for a minimum of five years:

(a) Review and audit acti~ities~

(b) Events, and the r~ports thereon, which are the subjects of non~outine reports to th~ NRC..

5.6.3 Records associated with requirements of Federal (other than NRC),

State, local al")d regional authorities' permits and certificates for the.protection of the environment s*hall be retained for the period established by the respective permit or certificate.

i 5-5