ML18082A336

Ets,App B,Part 1 - Radiological,For License DPR-75

ML18082A336
Person / Time
Site:	Salem
Issue date:	04/18/1980
From:	NRC COMMISSION (OCM)
To:
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ML18082A334	List: ML18082A333 ML18082A336 ML19323A980 ML19323A982
References
NUDOCS 8005090069
Download: ML18082A336 (67)

Text

APPENDIX B TO OPERATING LICENSE NO. DPR-75 SALEM NUCLEAR GENERATING STATION

.UNIT 2 PUBLIC SERVICE ELECTRIC AND GAS COMPANY DOCKET NO. 50-311 ENVIRONMENTAL TECHNICAL SPECIFICATIONS PART I - RADIOLOGICAL

Sec ti on 1.0

1. l 1.2 2.0

2. l 2.2 2.3 2.3.l

2. 3.2 92.3.3 2.3.4

2. 3. 5 3.0

3. l

3. l

• l 3.1.l.l

3. 1.2 3.2 4.0 5.0

5. l 5.2 5.3 e.3.1

5. 3. 2 ENVIRONMENTAL TECHNICAL SPECIFICATIONS PART I - RADIOLOGICAL TABLE OF CONTENTS Title DEFINITIONS, ABBREVIATIONS AND NOTES **

DEFINITIONS NOTES...

LIMITING CONDITIONS FOR OPERATION THERMAL EFFLUENTS

• CHEMICAL EFFLUENTS RADIOACTIVE EFFLUENTS

• SPECIFICATIONS FOR LIQUID WASTE EFFLUENTS.*******

SPECIFICATIONS FOR LIQUID WASTE SAMPLING AND MONITORING **

SPECIFICATIONS FOR GASEOUS WASTE EFFLUENTS *.**..**

SPECIFICATIONS FOR GASEOUS WA~TE SAMPLING AND MONITORING SPECIFICATIONS FOR SOLID WASTE HANDLING AND DISPOSAL * * *. *

• ENVIRONMENTAL SURVEILLANCE ****

NON-RADIOLOGICAL SURVEILLANCE

• ABIOTIC.. * * * * * * * *

• Meteorological Monitoring **

BIOTIC *****.*

RADIOLOGICAL SURVEILLANCE

• SPECIAL SURVEILLANCE AND STUDY ACTIVITIES

• ADMINISTRATIVE CONTROLS

• RESPONSIBILITY **

ORGANIZATION ***

REVIEW AND AUDIT *.

NUCLEAR REVIEW BOARD ( NRB) * * * * * * *.

STATION OPERATIONS REVIEW COMMITTEE (SORC)

• i Page

1. 1-1 l

• 1-1

1. 2-1

2. 1-1

2. 1-l 2.2-1

2. 3-1

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 5.1-1 5.2-1

5. 3-1

5. 3-1

5. 3-1

ENVIRONMENTAL TECHNICAL SPECIFICATIONS PART I - RADIOLOGICAL TABLE OF CONTENTS (Cont'd)

Section Title Page 5.4 ACTION TO BE TAKEN IF A LIMITING CONDITIONS FOR OPERATION IS 5.5 5.6 5.6.1.

5.6.1.T 5.6.1.2 5.6.2 5.6.2. 1 5.6.2.2

• • 6.2. 3 5.6.3 5.7 EXCEEDED * * *. * *.. * *.

5. 4-l PROCEDURES.

PLANT REPORTING REQUIREMENTS ROUTINE REPORTS.. *

• Annual Environmental Operating Report..

Radioactive Effluents Release Report...**

NONROUTINE REPORTS.*************

Nonroutine Environmental Operating Reports *******

Nonroutine Radiological Environmental Operating Report.................

Nonroutine Radioactive Effluent Reports..***.

CHANGES IN ENVIRONMENTAL TECHNICAL SP EC !FI CA TIO NS.

RECORDS RETENTION **.******.*******

ii 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

-\\ *;

..J Table No.

2. 3-1 2 *.3-2

2. 3-3

2. 3-4

2. 3-5 3.2-1 3.2-2 5.6-1 LIST OF TABLES Title Radioactive Liquid Sampling and Analysis.

Radioactive Gaseous Waste Sampling and Analysis

• Liquid Waste System Specifications.*

Gaseous Waste System Specifications * *

• Gamma and Beta Dose Factors * * * *.

Page

2. 3-20 2.3-21

2. 3-22

2. 3-23

2. 3-24 Operational Environmental Radiological Monitoring Program 3.2-6 Sensitivity Levels for Environmental Sample Analyses.

3.2-9 Environmental Radiological Monit.oring Program Summary.*

5.6-8 iii

LIST OF FIGURES N

Figure o.

Title 5.2-1 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 from the station that it will not be affected by radiological emissions or other station releases.

3.

EMERGENCY NEED FOR POWER An emergency need for power shall be considered to exist if the system is unlikely to 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 collected for the purposes of analysis.

1. 1-1

5.

ENVIRONMENTAL SIGNIFICANCE Exceeding a report level, or when, in the opinion of the Station Superintendent, an event which causes an adverse impact on the environment has occurred *

. 6.

FUNCTIONAL TEST Us~ of a simulated signal or check source to determine instrument operability.

7.

GAMMA SCAN (GAMMA SPECTROSCOPY)

Identification of gamma emitting isotopes, using a multi-channel analyzer.

8.

INDICATOR STATION Sample location where any adverse environmental effects resulting from station operation could be perceived.

9.

INSTRUMENT CHECK Visual inspection of a monitor readout.

1. 1-2

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 based on available information.

12.

SPECIAL STUDY PROGRAMS En vi ronmenta 1 study programs designed to evaluate the impact of station operation on an environmental parameter.

1.1-3

~'i.2 NOTES

1.

The Environmental Technical Specifications are limitations, conditions and requirements which are considered necessary to addre?S environ~ental concerns.

2.

Each Monitoring.Requirement sha 11 be performed within the specified 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, calibration and functional test frequencies.

These pro.vis ions pro vi de a llowab 1 e tolerances for perfonni ng monitoring activities beyond those specified in the nominal monitoring interval. These tolerances are necessary to provide operational flexibility because of scheduling, per-fonnance considerations and environmental influences.

1. 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 in liquid and gaseous effluents to the environs to ensure that these releases a-re 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 W*ithin 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:

• • • • • • • -* e

/

For 1iquid wastes:

a.

The. annua 1 dose a.bove background to the total body or an organ of an individual from a.11 rea*ctors at a site should not exceed 5 mrem in an unrestricted area.

b.

The annual total quantity of radioactive mate.rials in liquid waste, exclud'ing tritium and dissolved gases, d.ischarged from each reactor shou.l d not exceed 5 Ci.

For gaseous wastes:

c.

The a*nm.1a l to ta 1 quantity of noble gases above ba.ckground discharged from the site should result in an air dose due to gamma radiation of less than 2.* 3-1

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

d.

The annual total quantity of all radioiodines and radioactive materfal in particulate forms with half-lives greater than eight days, above background, from a 11 reactors at a site should not result in an annua 1 dose to any organ of an individual in an unrestricted area from all pathways of exposure in excess* of 15 mrem.

e.

The annual total quantity of iodine-13.l discharged from each reactor-.

at a site should not exceed l Ci.

2.3. l SPECIFICATIONS FOR LIQUID WASTE EFFLUENTS a

• The concentration of radioactive materials released in liquid waste. effluents from a 11 reactors at the site sha 11 not exceed the values. specified in TO CFR Part 20, Appendix B, Table II, Column 2, fo.r unrestricted areas.

b.

The cumulative release of radioacttve materials tn liquid waste effluents, excluding tritium and dissolved gases, shall not exceed 10 Ci/reactor/ca-lendar quarter.

c.

The cumulative release ef radioa.ctive mate.rials i'n liq_uid waste effluents, excluding tritium and dissolved gases, shall not exceed 20 Ci/reactor in any 12 consecutive months.

d.

During release of radioactive wastes,. the effluent control monitor shall be set to alann and to initiate the automatic closure of 2.3-2

{ --

e.

each waste isolation valve prior to ~xceeding the limits specified in 2.3.1.a above.

The operability of each automatic isolation valve in the liquid radwaste discha.rge 1 ines shal 1 be demonstrated quarterly.

f.

The equipment installed in the liquid radioactive waste system S'hall be ma.intained and shall be ope.rated to process radioactive liquid wastes prior to their discharge when the projected cumula-tive rel~ase could exceed 1.25 Ci/reactor/calendar quarter, exclud4ng tritium and dissolved gases.

g.

The maximum radioactivity to be ccmtained in any liquid radwaste tank that can be discharged di re.ctly to the en vi ron*s shall not exceed-10 Ci, excluding tritium and dissolved gases..

h.

If the cumulative release of radioactive materials in l"iquid effluents, excluding tritium and dissolved g.ases, exceeds 2.5 Ci/reactor/calendar qua*rter,. the licensee shall make an investiga-tion to id_entify the ca*uses for such releases, defi.ne and initiate a program of action to re.duce such releases to the design objective levels listed in Section 2.3., and report these actions to the NRC i'n accordance with Specifi-cation 5.6.2.3.1.

i.

An unplanned or uncontrolled offstte release of radioactive mate-rials in liquid effluents in excess of 0.5 curies requires notifica-tion. This notification shall be in a.ccordance with Spe.cification 5.. 6.2.3.3.

2.3-3

- /

SPECIFICATIONS FOR LIQUID WASTE SAMPLING AND MONITORING

a.

Plant records shall be maintained of the radioactive concentration and volume before dilution of liquid waste 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 5.6.1 of these Specifications. Estimates of the sampling and analytical errors_ assocJated 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 concentration of each principal gamma emitter in accordance with Table 2.3-1 to demonstrate compliance with Specification 2.3.l using the flow rate into which the waste is discharged during the period of discharge.

c.

Sampling and analysis of liquid radtoactive waste shall be performed in accordance with Table 2.3-l. 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 a*nd recorded during releases..

Whenever these monitors are tnoper-abl e 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 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 waste tank shall be made and any release in progress shall be terminated.

2.3-4

. ~

Bases

e.

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

f.

All liquid.effluent radiation monitors shall be calibrated at 1 east quarterly by means of a radi cacti ve source which has been calibrated to a National Bureau of Standards source.

Each monitor shall also have a functional test monthly and an i-nstru-ment check prior to making a release.

g.

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

Whenever these monitors are inoperable, the b.l owdown fl ow shall be di ve.rted to the waste management sys-tern and the d*irect release to the environment te.nninated..

_-.-...-:"*: -9rhe_ release_ of rad.ioactive materi'als i-n liquid waste-effluents to unrestrictect--*-'-------

areas sha.11 not exceed the* concentration limits specified in 10 CFR Part: 20 and should be as low as pra.cticable in accordance with the*requirements of 10 CFR Pa*rt 50.36a.

These specifications provide reasonable assurance that the resulting annua.l dose to the total body or any organ of an individual in an unresricted area will nat exce.ed fr mrem.

At the same time., these specifications permit the flexibi'Hty of ape:rati on, compati b Te with* con*si de*rations of hea 1th and safety, to _

assu.re that the p.ublic is provided a dependable source of power under unusual G>pera Ung CQnd i ti ans which may temporarily resu 1t in rel eases higher than the design 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 operatingconditions, and exerting every effort to keep levels of radio-9*ctive material in liquid. wastes as lew as practicable, the annual releases will not exce.ed a small fraction of the concentration limits specified in 10 CFR Part 20.

2.3-5

• . The design objectives have been deve 1 oped based on operating experience taking into account a combination of 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 50.36a.

Specification 2.l.l.a requires the licensee to limit the concentration of radio-a.ctive materials in liquid waste effluents released from the site to levels specified in 10 CFR Part 20, Appendix B, T~ble II, Column 2, for unrestricted areas. This specification provides 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.

-*specifications 2.3.l.b-and 2.3.l.c establish the uppe*r limits for the release-of*'""*-----

radi oactive materials in l i qui"d effl uerits.

The intent of these Speci_fi ca ti ans is _

to permit the licensee the flexibility o.f operation to assure that the public. is p.rovided a dependable source of power under unusual operating conditions which may temporarily result in releas.es higher than the levels normally achievable whe.n the plant and the liquid waste treatment systems are functioning as designed.

Release.s of up to these levels wtll result in concentrations of radioactive material in liquid waste effluents at small percenta.ges of the limits specified in 10 CFR Part 20.

Consistent with the requirements o.f 10 GFR Part 50, Appendix A, Design Criterion 64, Specifications 2.3~1.d and 2.3.1.e require operation of euitable equipment to control and monitor the releases of radioactive materials in liquid wastes during any period that these releases are taking place.

2.3-6

.Specific~tion 2.3.1.f requires that the licens-ee maintain and operate the equipment installed in the liquid waste systems to reduce the release of radioacttve 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 pro_vides reasonable assurance that the quantity released will not exceed the design objective.

In order to keep releases of rad-ioact.ive materials as low as practicable, the specification requires operati?n 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.

Spe~ification 2.3.l.g restri~ts the amount of radioactive material that cou.ld. be inadvertentl:__released to the environment to an amount that will not exceed the. Technica.l Spec.ification limft.

In a-ddition to li'mi tihg condi'tions for o.pe.ratfon Tis ted unde.r Sp.ecffi ca ti ans 2.3. l.b an~ 2.3. l.c, the repo.rting requirements of Specification 2.3. l.h delineate thatthe licensees.hall i'dentify the cause whenever the cumulative re.lease of radioactive materials in liquid waste effluents e-xceeds one-half the des fgn objective annua-1 quantity du.ring any ca.l enda:r quarter and describe the p.roposed prog.ram of actfon to reduce such releases to design objective Te.ve.ls on -a ti me l y basis. This report must be filed within 30 days following the calendar quarter-in which the release occurred as re.quired by Specifica-tion 5.6.2 of these Technical Specifications

• 2.3-7

~Specification 2.3.l.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 in conformarice with the requirements of Design Criteria 60 and 64.

These requirements provide the data for the licensee and the Commission to evaluate the plant's performance relative to radioactive liquid wastes released to the environment.. Re.ports on the quantities of radioact.ive materials released in liquid waste effluents are furnished to the Commission according to Section 5.6.l of these Technical Specifications.

On the basis of such reports and any additional 9information the Commis~ion may obtain from the licensee or others, the Corrmiss_~-~n ____....

may from time to time require the licensee to take such* action as the Commission deems appropriate.

The points of releas.e to the environment to be monitored in Section 2 *. 3.. 2 fnclude*

all the monitored release points as provided for in Table 2.3-3.

2.3.3 SPECIFICATIONS FOR GASEOUS WASTE EFFLUENTS The. terms used in these Specifications are as follows:

subscripts v, refers to vent releases i, refers to individual noble gas nuclide (Refer to Table 2.4-5 for the noble gas nuclides considered) 2.3-8

.. ::.... e QT = the total noble gas release rate (Ci/sec)

= lQ sum of the. individual noble gas radionuclides determined

i to be present by isotopic analysts K = the average total body dose facto.r due to gamma emission (rem/yr per Ci/sec)

[ = the average skfo dose factor due to beta emi ss i ans (rem/yr per Ci/sec)

M = the av~rage air dose factor due to beta emissions (rad/yr per* Ci /sec)

N = the avera.ge air dose factor due to gamma emissi ans (rad/yr pe-r Ci /sec)

The va.1 ues of K, L, M' and N are to be de:tenni ned each ti*me isotopic analysis is required as deli'neated i'n Speciffcation 2.3.4.

Determi:ne the following using the results of the noble gas radionuclide analysis:

K -* (l/QT) 1:-Q.K.

l 1 1

[ = (l/QT) J..Q.L.

., 1 1 M = (l/QT) I-Q.M.

1 1 1 N -* (1/QT) I.Q.N.

1 1 1 Wh*ere the val ue.s of Ki, Li, Mi and N.i are provided in Table 2. 3-5, and are site dependent gamma and beta dos.e factors:

2.3-9

"\\

Q = the measured release rate of the radioiodines and radioactive.

materials in particulate forms with half-lives greater than eight days.

a.

(1) The release rate limit of noble gases from the site shall ba such that

b.

< 1 and

< l *.

(2)

• The release rate limit of all radioiodines and radioactive materials (1) in particulate form with half-lives greater than *eight days, rele?sed:_.*.*

tp the* envi rans as part. of the gaseous. w_astes from the.site shall*

• be* such that:;

. 5

1. s x 1 a Qv

< 1

~

-.... ~~. -*.,..

~... *.. '

The average relea*se rate of noble gases ~from the site-. duri~g ariy\\: * *,

• .::_.,r*:*,

t*

ca*lendar. quarter.shall_ be such that:

• , f...

and (2)

The average release rate of noble gases from the site during any 12 consecutive months shall be:

2.3-10

. 'I

...... -.A (3)

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

25 [ 1

• 5 x 1 o5Qv J

< 1 (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/reactor.

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 of 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

(1)

If the average release rate of noble gases from the site during any calendar quarter is such that:

> l or

> l (2)

If 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 calendar quarter is such that:

> l (3)

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

d.

During the release of gaseous wastes from the primary system waste gas holdup system the effluent monitors listed in T-able 2.3-4 shall be operating and set to alarm and to initiate the automatic closure of the waste gas discharge valve prior to exceeding the limits specified in 2.3.3.a above.

The operability of each automatic isolation valve shall be demonstrated quarterly.

e..

The maximum activity to be contained in one waste gas storage tank shall not exceed 41,000 curies (considered as Xe-133).

2.3-12

~*

f.

An unplanned or uncontrolled offsite release of* radioactive materials in gaseous effluents in excess of 5 curies of noble gas or 0.02 curie of radioiodine in gaseous fonn requires notification. This notification 2.3.4 shall be in accordance with Section 5.6.2.3.3.

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 samplihg and analytical error associated with each reported value should be included.

b.

Gaseous releases to the envfronment (Table 2.3-4), except from the

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

turo1 ne ouiTcfing vent-;-ra-fi on exh-aust-an-d-a-s-no~ed-;n-Speci-fi-cati~on---.--*

• ~.

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

. - da.i ly for gross radioactivity. If these monitors are i rioperab le for more "than -seve_rt gays, these release-s shall be tenninated.

c.

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

2.3-13

/

Bases

d.

All waste gas effluent monitors shall be calibrated at least 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 2.3-2.*

The. release of radioactive materials in gaseous waste effluents to unrestricted areas shall not exceed 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 50.36a. These specifications provide reasonable assurance that the resulting annual air dose from the site due to gamma ra,diation will not e~ceed 10 mrad, and an annual air dose from the site due to beta radiation will not exceed 20 mrad from noble gases, that no individual in an unrestricted area wi 11 rekeive 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, compatible with considerations of health and safety, to assure that the

~ubic is *provided with a dependable source of power under unusual operating 2.3-14

9':

- conditions 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 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 combinatfon 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 annua.1 gamma and beta dose rate above background to an individual in an unrestricted area will not exceed 500 mr~~ to the total body or 3000 mrem to the skin in compliance with the limits of 10 CFR Part 20 *.

• 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-1968 and model techniques provided in Regulatory Guide 1.109, Calculation of Annual Doses to Man from Routine Releases 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 using onsite meteorological data and the dose expressions provided in Regulatory Gui Ge 1. 109.

The dose expression considers the release point location, building wake effects, and the physical characteristics of the radionuclide~.

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

The release rate Specifications for a radioiodine and radioactive material in particulate form with half-lives greater than eight days are dependent on existing

.y:~~-.---radionuc-1--ide-pa-thways-~to -man. --T.he _pathwaj's _wh.i.ch were __ ex_ami_neq_ fo_r 4hes_~---.. -- -----.,..-~:-_-_ ~.~--

Specifications are:

1) individual inhalation of airborne radionuclides,

.2) deposition of radionucl ides 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 for estimating doses to the thyroid via these pathways are described in Regulatory Guide 1.109. Tile 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 detennined using onsite meteorological data and the expressions described in Regulatory Guide 1. 109.

Specification 2.3.3.a(2) limits the release rate of 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 rad.ioiodines and radioactive material in particulate form with half-lives greater than eight days, the most restrictive location is a dariy farm located 6600 r:eters in the NW direction (vent X/Q = 1.1 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 Spe.cifications 2.3.3.a and 2.3.3.b, the reporting requirements of 2.3.3.c provide that the cause shall be identified whenever the release of gaseous effluents exceeds one-half the design objective annual quantity during

• *c:. _ 9 any ca 1 endar quarter. a~d that the proposed program o~-ac:*t1*on-to-reduce~-s-u.eh-. ----.. -- ______ _

release rates to the design objeciives shall be described.

Specification 2.3.3.d. requires that suitable equipment to monitor and control the radioactive gaseous releases is operating during any period these releases a*re 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 based 5 percent meteorology, the average gross energy is 0.19 Mev per disintegration (considering Xe-133 2.3-17

1

,.)to be the principal emitter) and exposure occurring at the minimum site boundary

.. J' 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.

. Specification 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 assura:nce.. *that radioactive materials released in gaseous waste effluents are prop~rly controlled and monitored in conformance with ~he requirements of Design

~*:::::.: ~.*

~ ~i-ter~fa.--60-and-64.-. ~~ese-r-equ.:i.~ements~p~o.vJde-the_da.ta __ forc._~he_l_tcen see_and __. ----. __

the Commission. to evaluate the plant's performance re.lative to radioactive waste effl ue.nts released t,o the environment.

Reports on the quantities of radioactive materia:rsc'released*fn gaseous effluents are furnished to the Commission on the basis* of-Sectio'n 5.. 6.1 of these: Techni~al Specifications.

On the basis of suc.h

.report$*: arid any a*cidttional information the Commission may obtain from the* 1 icensee or a the-rs~ *:the Cammi ssion may from time to time require the 1 icensee to take such action ~s 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.

1.:... :.

• 2.3-18

~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 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 sol id waste shipments, volumes, principal

~: -*

radionu.clide.s, and total c.urie quantity,.shall-be submitted in accordance with Section 5.6.. l.

Bases The requirements for solid radioactive waste handling_ and disposal g*iven 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, lo CFR Part 71, and 49 CFR Parts 170-178-.

2.3-19

TABLE 2. 3-1 RADIOACTIVE LIQUID SAMPLING ANO ANALYSIS

/

/

Sampling Frequency Detectable Liquid Type of Concentr;itions So*JrCd and Analysis Activity Analysis

(µCi/mil~

b A. Monitor Tank Releases Each Batch Principal Gamma Emitters 5 x 10-1 One Batch/Month Dissolved Gases f 10-5 Weekly Compositec Ba-La-140, I* 13-1 10-6 Monthly Compositec H-3 10-5 Grosso:

10-7 Quarterly Compositec Sr-89,.Sr-90 5 x 10-s

8. Primary Cool;:int.

Weeklyd 1-131, 1-133 10-6 C. Steam Generator 61owdo.wn Princip31 Gamma Emitters 5 x 10-:*

Weck lye Ba-L6-140: 1-131 10-6 One Sample/r.1onth Di:;solvcd G.:ises f 10-s... - -. -....

Monthly Compositee H-3 10-5 10-1 Grosso:

Quarterly Compo-sitee Sr-89, Sr-90 5 x 10-&

• The detectability limits for activity analysis arc b'1sed on the technical feasibility and on the potential. significance in the environment of the Qu;.ntitics released. For some nuclitfes, lower detection limits may be readily achievable, and when nuclides are measured below the stated limits, they should also be reported.

bFor certain mixtures of gamma emitters, it may not be possible to measure radionucfides in concentrations-near thei~

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 r<Jdionuclides using measured ratios with those radionuclides which are routinely identified and measured.

c A *eomposite sample is one in which the c. Jantity of liquid s.:impled is proportional to the quantity of liquid waste ciischarged.

dThe power level and cleanup or purification flow rate at the sample time shall also be reported.

eTo be representative of the average quantities and concentrations of radiooctive materials in liquid effluents. samples 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 composite sample to be representative of the average effluent*

/* release.

or dissolved noble gases in water, assume a MPC of 4 x 1 o*5 µCi/ml of water.

2. 3-20

/

TABLE 2.3-2 RADIOACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS

• Sampling Frequency Dc1ec1able Gaseous Tvpe or

. Concentra11on1 Source and Analysis Activity Analysis b1C1/m11*

b A. Waste Gas Decay Tank Releases Each Tank to Principal Gamma Emitters 10-4 be Released H-3 io-6 B. Containment Purge Releases Each Purge Principal G.ammJ Emitters 10-*c 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 io-*b. c (Ga~ Samples)

H-3 10-6 Weekly (Ch.:rcoal Sample) 1-131 10-*l Monthly (Charcoal Sampl.:-) I 1-133, 1-135 10-10 Weekly (Particulates)d Principal Gamma Emitters (Ba-La-140, I-131 and others) 10-11 Monthly Composited-(Particulates)

Gross.a

• 10-t I Ouar:terly Composited Sr-89, Sr-90 10-***

(Particula tcs) 1 The above detectability limits for activity analysis are based on technical feasibility and on the potential significance in the environment of the quantities released. For some nuclides. lower detection limits may be. readity achievable, and when nuclides are measured ~low the stated limits, they should also be reported.

bFor certain mixtures of gamma emitters, it may not be possible to measure radionuclides at levels near their sensitiv*

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 radionuclidcs using observed ratios with those radionuclides which are*

measurable.

c Analyses shall also be pcrforrr.~d !allowing each refueling, startup, or similar operational occurrence which could alter the rr.ixture of radionuclides.

dTo be representative of the avcra;c 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.

w I

N N

TABLE 2.3-3 SALEH STATION LIQUID WASTE SYSTEM LOCAJ!ON OF PROCESS ANP EFFLUENT MONITORS AND SAMrLERS REQUIRED BY TECHNICAL SPECIFICATIONS Grab rJ.!?asurement High Radiation A!!tO Control 10 Gross Actlv1 ty Sillnple Gross D1Hohicd lsolop1c Liquid Process Stre11m or Release Point Alarm..

!solution Villve

!:ontlnuous S1a11011 Ac1ivi1v I

Gast:s Alpha H*l Analysis Level

. Hon Hor Al;inn Hiscell~neous Monitor Ta"ksb x

x x

x x

x x

Chemical Drain Tank x

x x

x x

x x

Laundry and Hot Shower Tanks 1 x

x x

x x

x x

Primary Coolant System x

x Liquid Radwaste Discharge Pipe x

x x

x Steam Generator Blowdown System x

x x

x x

x x

x x

Outdoor Storage Tanks (potentla11¥ radioactive)

Xe Primary Water Storage Tank

• 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 H9t Shower Tanks are sample~. analyied, and then ffltered prfor to release through the 11qufd radwaste dfscharge pipe.

b Includes Waste Monitor Tanks, Waste Hon1tor Holdup Tank, eves Moritt9r Tanks.

c Grab sample to be taken and ~nalyzed each 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> whenever ~ank leakag~ 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 gros~ activity fn the secondary coolant system exceeds 10-5 ue1/ml (Except H-3).

N.

w I

N w I a **',

TABLE 2.3-4 SA~EH STATION GASEOUS WASTE SYSTEM l.OCATION 0F PROCESS ANO EFFLUENT MOl\\!ITORS /\\ND SAMPLERS REQUIRED BY TECHNICAL SPECIFICATIONS Contfnuous

.Grab Mea,urernent Radtatfon Auto Control 10 S.1m11h:

Proce~s Streom or Release Point Alann Isolation. Valve Mopttor Si.111011 NoLlc Gas I

Particulate Waste Gas Decay Tanks x

x x

x Condenser Atr Removal Syste"!

• X x

x

-x x

x Plant Vent

~

xh x

x x

x Building Ventilation Systems Reactor Contain1T1ent Building (whenever x~

th~re is fiow) x x

x x

x x

Auxiliary Building and Radwaste Area1 Xe x

x x

Fuel J.f andling & Storage Building*

Xe x

x x

\\

Turbine Gland Seal Condenser a Xe x

x x

Waste Gas Discharge Line x

x x

H-3 Alpha x

x x.

x x

x x

x x

x x

x x

x Sinca'the** procaa~ atralllll8 or buil4ina vantil~t~n *Y*t!lll* *~*routed to the plant vent 1 th* ~eed for a continuoua 11011itor at the individual dta-charge point to the main exhaust duct is eliminated *. *Ona contlnuoua monitor at the final raleaae point ta aulficient.

b Continuoualy monitored.

Also includea continuous **iodine.* noble &!IS and porticula.te monttora which are in service during waste gas decay Unk releaaaa and contai~ment purg!ng operations.

c Crab aample station* frOll ~hich 11ontfll1 1** 11uipha (T9ble 2. 3-2) are tc> ll°e ~'ken. Also, 1rab sal!lplea should be taken and measured to determine the

• proceas ~tream or building ventil~tion !Y*te111 11~urce when~ver an ~n~~plalned lncreaae la indicated. by th* pl~t vent "aaplar-moniton *.

d Include11 continuous noble gas monitor which monitors this location at *all t.lJDes other than waste decay tank releases and contai0111ent purging operation*,

Noble Gas Radionuclide N.

w I

N Kr-83m

.i::.

Kr-85m Kr-85 Kr-87 Kr-88 Kr-89 Xe-l3lm Xe-133m Xe-133 Xe-l35m Xe-135 Xe-137 Xe-138 I e TAOLf: 2.3-5 GAMMA AND BETA DOSE FACTORS FOR SALEM, UNITS l AND 2

-6 3

X/Q = 1.2 x JO sec/m @ 1270 Meter~,

Dose Factors for Vent Liv Skin rem/ r 8.6 x 10-5 0

0.043 0.97 1.8 1.0 0.012 1.6 0.012 3.0 12 3.1 7.4 2.8 7.8 1.3 12 1.4 0.34 0.57 0.43 0.26

l. 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. l9 2.9 5.0 3.0 North 0.35 2.4 2.3 12 3.5 13 1.3 1.8 1.3 0.89 2.9 15 5.7

ENVIRONMENTAL SURVEILLANCE The objective of the Environmental Surveillance Program is to detennine 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 pre.operational 11base-line 11 levels will reveal

• changes and trends* that could be attributed to plant operation.

As operating experience and surveillance data are obtaihed, the Environment~l Surveillance Program will be modified. to.reduce or eliminate surveillance of those parameters

....... _. that have not been significantly affected by plant operation

• 3.0-1

3.1 NONRADIOLOGICAL SURVEILLANCE 3.1.1 ABIOTIC 3.1.1.1 Meteorological Monitoring Objective The objective of meteorological monitoring is to adequately measure and document meteorological conditions at the site.

Specification The meteorological monitoring system shall conform to the reconunendations in Regulatory Guide 1.23,_0nsite Meteorological Programs, dated Februar,y: 17,_ 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 suITDTiarized and reported in a fonnat consistent with the recommendations of Regulatory Guide 1.21, Measuring, Evaluating, and Reporting

3. 1-1

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

Sunnnaries 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, Office of Nuclear Reactor Regulation.

Any modifica-tions to the meteorological monitoring program as described above shall have the written approval of the Director, Office of Nuclear Reactor Regulation, prior to initiation of the modification.

Base.s 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 resulttng from actual routine or accidental releases of radioactive materials to the atmosphere. A meteorological data collection program as described above is necessary to meet the requirements of sub-paragraph 50.36a (a) (2) of 10 CFR Part 50, Appendix E to 10 CFR Part 50, and l 0 CFR Pa rt 51.

3. 1-2

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

3. 1-3

RADIOLOGICAL SURVEILLANCE Objective 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 collected and analyzed in accordance with Table 3.2-1.

The sample locations are described in Table 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.

4.

During the seasons that animals producing milk for human consumption are on pasture, samples of fresh milk shall be obtained from these animals at the locations and frequencies shown in Table 3.2-1, and analyzed for their radfoiodine content (calculated as I-131). Analyses shall be performed within eight days of sampling.

Suitable analytical prcicedures shall be used to determine the radioiodine concentration to a sensitivity of 0.5 3.2-1

picocuries per liter of milk at the time of sampling.

For activity levels at or above 0.5 picocuries per liter, the detenninate error of the analysis shall be within + 25%.

Results shall be reported, with associated calculated error, as picocuries of I-13f per liter of milk at the time of sampling.

5.

A census of milk animals within a 1-mile radius from the plant site or within the* 15 mrem/yr isodose line, whicheve.r is larger, shall be conqucted at the beginning and a-t the middle* o.f each grazing season by using a door to door or equi vaJ e.nt counting te.chn*i que to determine their 1 ocati on and number with respect to the site. A census shall be conducted within a 5-inile radius for cows and goats, with enumeration by using referenced infonna.tion from county agricultural agents or other reliable sources.

If it is learned from this census that milk animals are p.resent at a location which yields a calculated* infant thyroid. dose gre.a.ter than any other sampled locations, the new location shall be. added to the surveillance program.

The infant thyroid dose shall be calculated using the equations and a:ssumptions presented in Re.gula.tory Guide 1.109, Calculation of Annual D.os.e,s to Man from Routine Re leas.es of Re;a.ctor E.ffl uents for the. Pu.rpose of Evaluati'ng Compliance W-ith 10 CFR Pa*rt 50, Appendix I dated March 1976.

Following the addition of any new location, a sampling location yielding a lowe*r calculated dose may then be dropped from the surveillance program at the. end of the grazing season du.ring which the census was conducted.

3.2-*2

Any locations from which milk can no longer be obtained may be dropped from the s urvei 11 ance program.

The Cammi s s ion sha 11 be no ti fi ed in writing that milk animals are not longer 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, milk sampling shall be done.weekly with I-131 analysis being performed on each s*ample.

6.

A. census* of gardens producing fresh lea*fy vegetables for human consumpti'on

( e ~ g., 1 ettuce, s.pi nach, etc: *. ) sha.11 be conducted ne.ar the end o.f the growing season to determine thei.r locati'on with respect to the site. This census is 1 imited to gardens having an area of 500 square feet or more and shall be conducted. under the fa 11 owfo*g conditi ans:

1.

Within al-mile radi'us of the p.lant site, enumeration by a door-to-door or equtvalent 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 s ha 11 be extended to a distance of 5 mil es 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 pe.nnitted from the required sampling schedule if s*pecimens are unobtainable due to hazardou.s conditions, seasona 1 unavail-ability, or malfunctions of a.utomatic sampling equipment.

In the case of the latter, corrective action shall be completed prior to the end of the next sampling period, tf possible.

Any location from which environmental monitoring program samples can no longer be reasonably obtained may be dropped from the su.rvei 11 ance program.

The NRC sha 11 be no ti fi ed in writing of the reasons for this action.

Any location which is dropped s ha 11 be replaced by a su ttab le a 1 terna te 1 oca ti on.

3.2-4

Reporting Requirement

• ~n annual report shall be submitted in accordance with the requirements of I

Specification 5.6.l.

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

Bases The magnitude and flu<:tuati~n of radioactivity levels in the environment surrounding the plant have been determined during implementation of the pre-operationa.l environmental radiation monitoring program.

This information serves as a solid baseline for evaluating any changes in environmental radio-activity levels during plant operation.

The operational environmental radiation

__ onitoring program was derived using the preoperational environmental radiation monitoring pro.gram as a basis.

The monitorfog program utilizes a series of sampling locations which were determined by cohsideration of the spatial distribution. of ~tation effluents, including areas where concentrations of effluents in the environment are expected to be greatest, site meteorology, population distribution and ease of a*ccess to the. sampling stations. The selection of sampling media was based on an evaluation of potential critical pathways of radiation exposure to man.

Concurrent sampling at control and indicator stations permits plant-produced radionuclides to be distinguished from other sources of radionuclides.

3.2-5

EXPOSURE' PATllWA'r

• • AIRJORM!

,1 (a) P A

ll T

I c

u L

A r

! s (b) I 0

D I

N

£

-*~

STATION COD!

+

lODl 251 lFl 2P2 383 16£1 lODl 16£1 2P2 251 3H3 lODl 16£1 3Gl 3HJ lPl 2F2 501 211 2!l 251" T.Ul.I. J.2-1 OPERATlOKAL EllYIRONKE!!TAL llADIOLllCICAL HOHITOlllllG PllOC1WI LOCATION 3.9 a1 SSll of vent Oil aite 5.8 a1 H of vent

8. 7 *1* NH! of vent 110 *1 n: of atation 4.1 a1 111111 of v..,t 3.9 ai SI!:, of Yll!lt 4.1 mi lillll of vent NJ; 8*7 111 !Ill! Of YODt on Sita 110 ai H! Of Yllnt 3.9 111 ss;: oC '"ent 4.1 mi Nllll-of vent

16. 6 m11ee* !IE of* vent 110 mi !IE of atation 5.8. mi H of vent*

K;J; 8.7 *1 lillE of vent

3. S Ill !' of vent.

S mi RR!. of vent 4*. 4 Iii llKE of vent on alt*

COLl.!CTION M!'TllCO

&~CT Continuou1 low voluaa air*

aami>ler.

Sample collact..t nery voelr. along with Ultmr change A. TEil.A. illipregnated chnrcoal fl.,....chrough* cartridge 1*-

connected to air particulate

&ir *ami>lcr and ia.collected.

-*klp.

10 aoil plu1a*, to a depth2of.

6" over an are.a of 25 ft ara

_compoaited and Haled 111 a* plastic bag at each. location* A aa.ple will be. collected fr011 ucb locat1o1l once every l year1 TTP! ' P'lll!:QO!!lcT or AIL\\LTSlS compodta Sr 89 c-dta Sr 90 parfo~ quarterly C:rou Mta analysim oa..ca -UJ.r

...,i.,. __ -1t1r*

Ca.poaition Gaaa acan quarterly Iodine 131 analyaea-are* performed veelr.ly G-*-apectra.etry perfanaed on each

-le on callectian*.

Sr-90 analyaea on one &maple from-each locac1oa on collect.ioa.

• Sail *aaplea are takan in accordance with procedure* 1111tlined in HASL~JOO (R..,. 5/73). If a auttable 11Ample cannot be* obtained at a location, a *ample ah.all be obtained fr-a nev location, The NaC *hall be aot1f1ed 1.a vritin1 of the new aa.pia lacatioo.

Control Station

• • ea.... 1pectrcxoatrp 1hall ba perfo..._. if aroaa beta amc111da four ti..

• the control atacioo valua.

e 3.2~

STATION CODE

/

DIRECT 1001 16El ZFZ l3Fl lFl 3Gl 3Rl 2Hl 6Sl 7Sl l4Dl 1051 IV.

11A7ER.

11.Al.

(a) s 12Cl R

F A

c E

7!1 (b) G a

451 0

u N

3!1 D

(c) D R

2F*3 (rav)

I N

K I

!I c;

+ Co11trol Station TAIU 3.2-1 (Cone.)

OP!llATIOllAL l!ll'VllONKDTAL IADIOLOCICAL llOllITORI!IQ nDCllAll LOCATION 3.9 iai SSW <>£ vent l.. l mt NNW of vent

8. 7 iai NNE of ve11t

!!iddletovn, Del; 9. 8 mile* W of vent S.8 1111 N of vo11t

16. 6 111lea HE of vat 32 mi NE of vmt JS.5 ml ~E of vent

• 2 milea ESE of v...,c COLLECTION HEl'llOll

& f'R!:

ENCY 2 doe1-ten vlll be collected frClll each loc:at1on quarterly St.atian persoonel gate 3.9 mi WNll of vent Cooling vacer* inlet;} At lea*t one *do*imeter collected 150 ft SSW-of vent fro.. chia location quarurly Approx:Lmaul7 650 ft SW of ve11t 2-l/2 Iii WSV of vat Tvo gallon e&11ple to be collected mucthly providia1 viater icing cotiditioaa allav aampb collection 1 1111 W of Had Bona Creelr.; 4.5 Iii S! of Yei>t:

on site.

4.5 mi NE 0£ vent S*'im: W&cer Co. i NH! of Vltllt l. -.. UH ~** 0-h >o ~U~O

_t- -thly 50 al aliquot la takan daily aad c09p0a1ted to a llOllthly uapla of cva 1alloaa 3.2-7 TTP! ' FRJ!QUDICT OF A!IALYSIS Camu do*e-quarter ly G..... acaa llODthly H-3, Sr-89 and Sr-90 a.a.alyaee of quarterly compoaitaa c;,,_. *can -

QC B-3 analyaea are d011e monthly Gro** bet*.aa.thly Gi&IZllA *can -

QC B-3.,athly Sr 89 and Sr 90 analyau oa quarterly coa.po*ites

V..

+."'{!A.-XC I

r.,

r i

0 s

VI.

DIC?STIOll (a) II I

L

r.

(b),

I s B

(c) C R

A 1-(d) J'CITS or

'l!C!:UTIO!I

(*) G A

II STATION COil!

7!1

+ l2Cl 15'1 2n sn 14Fl 3Cl lW

+ l2Cl 12Cl

+

lGl ZFl

a::r.-

DX

• LDcat1mr. _gi*.,. ac t1-of coU.CUmr.

TAIL! 3.2-1 (Cont.)

OPDATIDIW. !llVIllJlllEKrAL IWlIOLOCICAL l<<!KlT!l&IllC PIOGIAll LDCATIOH 1 mi V of Kii4 BorH Cr.U.;

4.5 111 S! of v... c 2-1/2 mi llSV of Yilllt Outfall area; 650' SV of HDt S.2 111 NV of vent S mi !ilm of v.,.t 6.5 111 ! of Vmlt 5.5 111 I/NV of H1lt

16. 6 1111H II! of vei:

Outfall area; 650' SV of V-t 2-112. Iii VSV of v.,.t Outfall area1 650' SV of V""t llut. ~

oppo*n*-

ktilicial Iai.ad, 2,.1/z ai vsv. of 10.2 a11H* R-of vet 4.45111 llR!*of Vmlt l *1 NNE-of vent COLLEctIOH-l!!T!IOD

' F!EQU!l!C!

A. beuchoe._1e coadati"I of ben chic oraaut-and aaaoci&ced aal1-t 1** tali.ell oelliaunually.

Pour gallon srab &allJl.la of frHh *illr. 18 callecud troa each fani a*i-thly.

Collected -1r.17 if calculated do** ac*..S* U *r-to child'*

thyroi.d-.

}-

Tvo key._1.. of-ft.h ar* aealc ia plucic bag or jar and fro1.,.

1"'"1-amwally or vb.,.

ia a.aeon Tllo key *-pl.. of crab ar*- naled 1D

• plaatic bag. or jar and frozen

• "'"1-aunually *or vh*u lD. *-*=-

s..p1.. are collec:t.i during. the non.al bar-

-.._.._..... -'--'.,.,_~

v.. t auaon, Haled 111 plaatic, and-froHu if per.iababla. Suff1c1eat

... pl* 1a collaccad _to yield soil arm.. of dry

.,.1&ht and dooa* aaaua-lly St.attmr. vicinity uat aid*-of ucuary v.. c aide of-atuary,_

S-5 Iii. fr...,..,.,

VlthiA-.-10 u-of Statloa J

}

lluakrau ara* akiaa..t and fro1m1* ae111-amually leaf-portioa of c-- 18..

• uapled and frozen mnually

... * ~

._1 *. 1e -..bject to nail.ability of alauabtared c-

• Control Station 3.2-8 TTP! 6 F'Rl!!QUERCf OF A!IALTS'!S

..._ s11<<\\rooetr7 of HC~ umpl*

'""t-*n.,.*11;,; Sr-89 1nd Sr-90

-t-*mw.117 on O...,.lllUIS.

Sr-90... 1-annu*llr 011 seeteen\\

~

1c:.an 11<>ntbly; Sr-89 aad Sr-90 110ntbly; I-131 aonthly l-lll ~y if calcuatal doH acaeda. 15 *-*

ta cb11.cl'1 thyr_oid C:- 1eaa of edible ponioa on collectioa G._ acaa of e.dibla-portimr. on collection bdioiodiile deterainati;,., -

of grff.o. leafy vegat*blu*

Oil' collection.

Gema *can on colleccioa.

c:-. acaa-. an edibl*

portiaa ouly oa col-lectimr..

/

TABLE 3.2~2 SENSITIVITY LEVELS FOR ENVIRONMENTAL SAMPLE ANALYSES SA."IPLE TYPE Air Particulates Air Iodine Soil Ther.:io 1 u~i nescent Dosimeters Surf ace water Ground water

!:)rinking water B.enthes-Fish TYPE OF ANALYSIS Gross beta Garrma scan Sr 89 Sr 90 I 13:1 Gamma scan S.r 90 Gamma Gamma scan*

Trtt.ium s:r 89 Sr 90 G'amma scan Tritium Gross b.eta Gamma scan Tritium Sr 89*

s*r 90 Gamma s.can Sr 89 Sr 9.0 Garrma scan 3.2-9 SENSITIVITY*

-14 4.4 x 10

µCi/ml 1X10--14 II II 5 X io-15 II*

II

. 1 X 10-15 II II 4 X 1 o.;,*14*

II II 1 *x i-o-7 c*

d

µ i/g-ry 5 X 10-8

. II

. II approx. 5mrem/yr l x

-9*

10

-- µCi /ml--*-'"" --*.*..... :_ -

2 x 10-7 II II 5 x To-*9 II II

l. x 10-*9 II

.II 1 x io-*9 II II 2 x l o-7 II*

II 1

-9 II II X* 10 1 x io-9:

II II 2 x io-1 II II 5 x io-9 II II 1 x 10-*9 II II 1 x 10-7

µCl/g.-dry 5 x 10-7 II II 1 x 10-7 II II 8 x 10-8

µCi/g-wet

./

j

.... -/

TABLE 3.2-2 (Cont'd)

SENSITIVITY LEVELS FOR ENVIRONMENTAL SAMPLE ANALYSES SAMPLE TYPE Milk Fruits and Vegetables Meat Game TYPE OF ANALYSIS GalTllla scan Sr 89 Sr 90 I 131 Gamma scan I 131 Gamma scan Ganma scan SENSITIVITY*

1 x 10-8 µCi/ml 5 X 1 o-9 II II 1 X 1 o-9 II II 5 X 10-1011 II s x lo-8 iiCi/g-wet 5 X 1 o-8 II II 8 X 10-8 II II 8 X 10-8 II II

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

3.2-10

i I

4.0 SPECIAL SURVEILLANCE AND STUDY ACTIVITIES None.

4.1-1

r"** e 5.0 ADMINISTRATIVE CONTROLS Administrative Controls below apply to Appendix B Part I only.

5. 1 RESPONSIBILITY 5*. 1

• 2 The imp 1 ementation of the survei 11 ance programs extern a 1 to the plant~ including sampling, sample analysis, evaluation of results and the preparation of required rep.arts is the res*ponsibility of the Licensing and Environment Department in the Enginee.ring and C-onstruction Department.

This Department is responsible for the assignment of personriel to the above fun~tions, for assurance that appropriate written procedures, as describ_ed in Section 5.5 *. 1, are utilized in the.su.rveillance prog:ram activities and for assur'-

fng the qualHy oJ su.rveillance prog.ram results, as described

• in Section 5.5.3.

The Statton Manager or his delegated alternate is responsible for 0p*e.rati:ng. the plant in compliance with the limiting condi'tions fo*r operati0n as specified in the Environmental Technical Specifications and for the in-plant monitoring ne.cessary to ens:ure s.uch operation.

His responsibility includes ass*urance that plant activfties a:re conducted in such a manner as to provide continuing protection to the en~ironment and that p.ers.onnel performing such.activities use appropriate written procedures as des~rtbed in Section 5.5.

5.1-1

5.2 Organization 5.2.1 Figure 5.2Tl identifies the corporate relationship between the Licensing and Environmental Department and the station Manager and also shows the organization of the Licensing and Environunent Department.

Figure

6. 2. 2 of the Radiological Safety Te.chnical Specifications identifies the Production Department Station Organization.

5.2.2 The Nuclear Review Board (NRB)" and Station Operations Review Comrilittee (SORC) are shown in Figure 5. 2-1.

They are advisory groups to the Vice President -

Productj,on and the station Manager respectively.

5.2-1

IJ)

N I

N I

o(NU~Al MANAOfR -

'ENGINEERING

! e.

.../

'~

r*

SENIOR YIU PRESIDENT -

lNEHOY SUPPLY.

fNOINEEJllNG Vlq 'RU!DU~T -

v1q PRESIDENT -

VICI PRl$10lNI -

lNOl~E"R!NO,

PROOUCJION ftlH SUf'f'L Y ANO CONSIRUCl!otf NUCUAR I

REVIEW BOA HO

~lNl~AL MANAGER -

MANAGER-QENERAL MANAGER -

GENERA~ "'AHAGER -

LUllNSING Iii lNVIRONMlNT I

Q.A.

ENGINEER STAT JOH O. A.

. ENGIHEER (SALEH)

OUALITY ASSURANCE EUCIRIC PRODUCTION*

fUH. SUPPLY NUCUAR PLANT lNOINHR MANAGER -

MAf4AGf R -

NUCLEAR.

SAUM GENER" llNG QPlRAllONS llAHON I

NUCLEAR FUEL HEALTH PllYSJClST CYCLE lNOiNEER I'

FIGURE 5.2-1 OFFSITE ORGANIZATION FOR FACILITY MANAGEMENT AND TECIJNICAL SUPPORT LL RAM

I 5.3 REVIEW AND AUDIT 5.* 3.1 NUCLEAR RE.VIEW BOARD (NRB)

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

l

• NRB sha 11 review:

a; Proposed Environrrental Technical Spec.ifica:tion changes or license amendments.

b.

Violations of Environmental Technical Specifications.

c..

En vi ronmenta*l M'onitori ng Pro.gram and Eva 1 uati ans.

d*.

Routine and non-routine repo.rts required. by the Environmental Technical*

S:ped Hcati ans:.

2.

The NRB. s.hal l, at least once. each ye:ar, conduct (or cause ta have conduc.tect) and eva.luate: audits of:.

a.

Plant operation to assure Environmenta.l Technical Specification compliance *.

b.

Mo.nitoring program sampling practices to assure they adhere to p.rog.ram s.chedule and appropriate procedures *.

5. 3.2 STATION OPERATIONS REVIEW COMMITTEE (SORC')

The SORC shall' have the fa.Hawing responsibilities concerning the environmental i rr.pact of the pl a*nt:

1.

Revi'ew plant procedures which have* a potential i*mpact on the environment

• 5:. 3-1

~1 2.

Review proposed changes to the Environmental Technical Specifications.

3.

Review environrrental monitoring program results and evaluations.

4.

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

5.

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

5.3-2

}.

( --

5. 4 ACTlON TO BE TAKEN IF A LIMITING CONDITION FOR OPERATION IS EXCEEDED 5.4. l Remedial action as permitted by the Environmental Technical Specifica-tion shall be taken until the condition can be met.

5.4.2 Exceeding a limiting conditi"on for operation shall be i'nvestigated by the Station Ope.ration Review Co11111ittee.

5.4.3 A report for each occurrence shall be prepared and.submitted as specified i.n Section 5.6.2.

5.4-l

e; 5.5 PROCEDURES

5. 5.1 5.5.2 5.5.3 Detailed written procedures, including applicable check lists and instructions, shall be prepared and followed for all activities involved in carrying out the Environmental Technical Specifications.

Procedures for the environmental surveillance and special study programs described in Sections 3 and 4 shall be prepared 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 shall be determined from experience with similar instruments in simi la*r environments and from manufacturers' technical manuals.

In addition to the procedures specified in *section 5.5. l, the plant operating_procedures shall include provisions to ensure the plant and all its systems and components are operated. in compliance with the limiting conditions for ope.ration established as part of the Environ-menta*l Te.chnical Specifications.

Procedures will be established to assure quality results.

Procedures*

W*i 11 ind ude:

a.

Audits to assure organizations performing program activities are fo llawing pol icy directives and are using the appropriate written instructions.

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.l.l Annual Enviro.nmental Operating Report

l.

A report an the radiological environmental surveillance programs for the previous 12 months of ope.ration sha 11 be submitted to the Di rector of the Regional Inspection and Enforcement Office (with copy to the Director~

o*ffice. of Nuclear Reactor Regu]ation) as a s*eparate document within 90 day.s after Ja*nuary l of* each year.

The period of the first report shall be.gfo with the date of ini't.iaJ criticality. The reports shall include.

summaries, inte.rpreta:tions, and sta*tistical evaluation of the results of the radiological environmenta-1 s.urvefllance activities for the report p.e:ri od, incl ud-fng* a. com[,i)ari'sen with i;>reope.rat.i anal studies, ope*rati onaJ controls (as approprtate), and previous environmental surveillance rep.arts and an a.ssessment of the observe:d. i:mpa*c.ts of the pl ant operation o.n the en.vi ronme.nt.

If hannful effects or evidence of irreversible dama.ge-a*re detected by the monitoring., the licensee shall provide an*

a:nalysi-s of the. problem and a proposed cou.rse of action to alleviate the

2.

Res:ul ts of al 1 radi ologkal envi ronmenta 1 samples taken sha 11 be surrmari zed o:n an annual basis follow*ing the format of Table 5.6-1.

In the* event thait s:ome results a*re not ava*flable* w*ithi-n the 90 day period, tne report S*ha.11 be submitted noting and e~pla*inin*g tne* reas.ons for the missing res.1:Jlts.

The missing data shall be subm-itted as soon as possible in a s:1:1pplementary report.

5 *. 6-1

5.6.1.2 Radioactive Effluents Release Report

.\\ 1.

A report on the radioactive discharges released from the site during the previous 6 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) within 60 days after January l and July 1 of each year.

The report shall include a surrrnary of the quantities of radio-active liquid and gaseous effluents and solid waste released from the plant as outlined in Reference 1, with data surrmarized on a quarterly ba.sis fo11owing the format of Appendix B thereof.

2.

The report shall include a su1T1Tiary of the meteorological conditions concurrent with the re-1 ease of gaseous effluents during each quarter as outlined in Reference 1, with data surrmarized on a quarterly basis following the format

~

of Appendix B thereof.

Calculated offsite dose to humans resulting from the release of effluents and the-1-r subsequent dispe.rsion in the atmosphere shall be reported as recorrrnended in Refe.rence l.

5. 6*. 2 NONROUTINE REPORTS

5. 6. 2. 1 Nonrouti ne EnvfronmentaJ Operating Reports A report shall be submitted in the event that (a) a limiting condition for operation is exceeded (as specified in Section 2.0, "Limiting Conditions for Operation"},

(b) a report level is reached as specified in S.ection 3.0, "Environmental Surveillance")

or (c) a*n unusual or important. event occurs that causes a significant environmental impact, that affects potential environmental impact from pla*nt operation, that ha.s high public or potential public interest concern,ing environmental impact from pla-nt o~eration 5.6-2

-~eports shall be submitted unde*r one of the report schedules described below.

l

• Prompt Rep.ort.

• Th-ose events requ.i ring p.rompt reports withi*n 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> by telephone-, tele.g.raph, or facsimile transmissfon to the Director of the Regional Inspection and Enforcement Office (with copy to the Director, Office of Nuclear Reactor Regulation).

2.

30-Day Repo.rt~

• Thos.e events not requiring a prompt report sha 11 be reported

• within 30 days by a. written repo.rt to the. Di rec.tor of the _Region-al Inspection and Enforcement Office (with capy to the Director*, Office of Nuclea*r Rea:ctor Reg'u:l ati on).

5.. 6.2.2.

Nonrout.i-ne Radiological En.vi-ronmental Operat1ng Report Anomalous Measurement Report If a-con finned measure.d level of radiaa.ctivi ty* in any environmental medium exceeds TO times* th*e control station va;l ue., a written report sha.1 l be.

• Written TO-day and 30.-day. reports and, to the-extent possible,.the prelimina*.ry telephone, tele.~raph, or facs:jmi*le rep.arts shall (a) describe, analyze,. and ev.a:l uate* the occurrer:n:e,.* inclue.i:ng extent and ma.gnitude of the impact, (b) describe* the ca-us.e o-f the occu.rren*ce; and (t) indicate the corrective action (including any s i gni*ficant changes made in p*rocedu.res) taken to preclude. repe*-

titi on of the occurrence and to. prevent similar occurrences involving simi la,r comp:onents er systems.

N'ote:

The si gni flcan*ce of. an unusual *or apparently i-mportant event with rega.rd to envi ronmenta 1 impact. may not be obvi'.ous or folly appreciated at the time ef occurrence.

In su.ch cases, theNRC' shall b.e informed promptly of chan:g,es in the a.s.sessment of the significance of the event and a corrected re:1D0rt shall be. s.ubniitted as expeditiously as possible.

5.6-3

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

This report shall include an evaluation e:

of any release 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 concentrations of 7.0 picocuries per liter 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 menter of the general public.

3.

Fresh Leafy Vegetable and Inhalation Pathway Measurements*

a.

Lf green lea!y vegetable samples collected.over a calendar:-

_quar~e:!" s_bQw,_ _____ _

average I-131 concentrations of 220 picacu.ries per kilogram or greate.r, a written repert and a p 1 an shal 1 be submitted within 30 days advising the Commission of the proposed action to ensure the plant-related annual d*oses wi 11 be within the design objective of 15 mrem/yr to the thyroid of any member of the general public.

b..

If a.ir s:amples collected over a cale.ndar qua*rter show average concen-trati ens of I-131 of 2 pico.curies per cubic meter or greater, a w*ri tten Milk pathway measurements apply when this pathway is controlling with respect to atmospheric radioiodine releases.

If the milk pathway is not controlling then the reporting 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 advising the Conmission of the proposed action to ensure the plant related annual doses will be w,ithin 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 rel eases sha 11 be provided i'n the* Annual Opera ti'ng Report.

5.6.2.. 3 Nonroutine Radioactive* Effluent Reports

1.

Liqu.id Radioactive Wa*stes Report If' the cumulative releases of rad.toactive rr.a,teri a 1 s in l iqu.i d effluents, exc 1 udi ng tritium and d.i sso 1 ved ga.ses, should exceed one-ha'lf the design objec.ti ve. annua 1 quantity during any ca 1 endar quarter, the lice"!see shall make an i'nves:tigation to identify_ the_ cause.s _Qf __ ~-------

such releases a'nd. define. and* ini:t.iate a p.rogram of action to reduce such.

r~Jeases to the. design obj:ectiv.e 1 ev.el s. A written report of these acti'ons s.hall be. submitted to the. N*RC within 30 days from* the end of the quarter d:.iri-ng. which the reJ ease occurred.

2.

Gaseous Radioa*ctive Wastes Report.

Should 'the conditi'ons (a)., (b), and (c) r.tsted below exist, the licensee shaJ 1 make an investi g*ation to identify the causes of the release rates and define and initiate a program of action to red1Jce the release rate*s to des.ign objective levels. A wri'tten report of thes.e a:ctions shall be submitted to* the NRC within 30 days from* the end of the quarter during which the releases occurred.

\\........*

5.6-5

\\

~

a.

If the average release rate of noble gases for the site during any

---

,,--* e

• /

\\_

\\.. .

3.

calenda*r quarter exceeds one-half the design objective annual quantity,

b.

If the average release rate per site of all radioiodines and radioactive mate.rials in particulate, form with half-lives greater than e*ight days during any calendar quarte:r exceeds one-ha.lf the design objective annual quant;-ty.

c.

rt* the amount of iodine-131 releas:ed during any calendar quarter is greater than 0.5 Ci/reactor*.

Unplanned or Uncontrolled Release Repo.rt.

Any unplanned or uncontrolled offsite release of rad.ioactive materials in exces.s of 0.5 curie in liquid o.r in excess of s curies of' noble gases or- 0.02_ c.ur;-e of radioiodines in ___ gise-0-us ____ *-

form* requires. nc;)ti fication.

This no:ttfi cation must be made by a written*-

report within 30 d:ays-tC:> the-NRC~ The rep.art shall des*cribe th~ event, -

i C:ienti fy the causes of the unp 1 anned or uncentro.11 ed release and report acti.ons taken to-prevent recurrence.*

5.6.3 Clt!ANGES 1N E:NVIRONM_ENTAL TECHN,ICAL SPECIFICATIONS s*.6.3'.1 A rep.e:rt shall be made to the Commission prior to implementation of a change, in pl a*nt design, in p 1 a,nt ei:iera-tion, or i.n pr0cedures described in-Sec ti on 5. 5 if the change would* have a si.gni ficant effect an the--

envtronment or i*n*volves an env-ironmental matter or questi©n not i:ire-viously reviewed and evaluated by the Commission.

The report shall fnclucle a: des-cript;-on and ev.aluation of the changes ana a supporting benefit-cost ana.lysis.

5.6-6

.5.6.3 Request for changes in environmental technical specifications shall be submitted to the Director, Office of Nuclear Reactor Regulation, for review and authorization.

The request shall include an evaluation of the environmental impact of the proposed change and a supporting benefit-cost analysis.

5.6.3.3 Changes or a.dditions to pennits and certificates required by Federal, State *. local, and ~~l authorities for the protection of the environ-Refe.rence.s ment wi 11 be reported.

When the* re.qui red changes are submitted to the concerned agency for approval, they will also be submitted.to the Director, Office of Nuclear Reactor Regu.lation, for information.

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

1.

R:eg.ulatory Guide 1.21, M~asuring, Evalua*ting and Reporting Radioactivity in Solid Wastes and Releases of Ra*dfoactive Materials in Liquid and Gase.ous Effluents from Light-Water-Cooled Nuclear Power Plants, Revision 1, June 19-74.

5.6-7

U1.

. a..

I CX>

. ~ ~ : :

TA~LE 5.~-1

• ENVIRONMENTAL RADIO~QGlCAL MONITORING PROGRAM

SUMMARY

Name *of Faci l Hy D. ocket No.

~~-~~~~~~--

---

~-~

Locatien of Facility Reporting Period

(:Count,y, State) *

--=-------

Med,i,ym or Pa,t~wa.y Sampled Hln*i t of Measurement)

ATr Part tu, ates

. (pCi/ml).

Fish pi/kg (dry weight) y Analysis arid Lower Lfm1t total Number

• o.f A 11 9.(1\\naly.ses 0et;ec.d,m a./ *

• lnclJc~t.or Locat)ons Location w:Hh Highest Annual Mean Meiiri b/

Name Mean fiJ Number of Control LQc~tions Nonroutine Mean b/

Reported Pef.fo.rmed (LLD*)

416

• o.ooa 32 U7Cs 0.()03 R~n9.e-!ij Distance and Direction* Range.!11 Range-RI Measurements fl o~ oa. < 2001312)

(O.Q5-2.Q:)

o. 05 (4/24)

(0.03-0. l~)

Middletown s'm1les 340° Smithville 2.5 m1les 160° 0.10 (5/52) o.os (8/lP4)

(o:oa - 2.0)

(0.05-1.40) 0.08 (214)

(0.03 - 0. 13)

MDL 4

14-0 Ba

. 0.003 0.03 (2/24:)

((>.Ol-Q.08)

Podunk 0.05 (214) 0.02 (l/8) 89sr 40 0.002 90sr 40 0.0003 y

8 137Cs 80 134cs 80 60co 80 MQL MDL MOL MDL 120 (3/4)

(90-,200) 4; o miles 270° River Mile 35 Podu~k River c.0.01 - 0.08)

MDL MDL See Column 4 MDL 0

MDL 0

90 (1/4) 0 MDL 0

MDL 0

!/Mi*n*imum Detectab,le Level ('M[i)L) is cteHried as lob where fra is d~f1ned a~ the standard deviation of the background count..

WMean and range based upon detec;:tab;le measuremerits on~y. Fracdon of detect~ble measurements at specified locations is indicated in parentheses YNonrouUne reported me!ls4rements are deHned 1'n ~*section 5.6~~b~

g,/Note: l'he example data are pravtded for iHu$trative purpose~ _only.

5. 7 RECORDS RETENTION

5. 7. 1 Records* and logs* re*l ati ve to the following areas sha 11 be made and retained for the 1 i fe of the p1 ant:

5. 7.2

a.

Records and drawings detailing plant design changes and modifications made to_systen:i and equipment as described in Section 5.6.3.

b.

Re.cords of all data from environmental monitoring, surveillance, and spec.ial surveillance and study activities required by these e.nvi ronmenta 1 technical specifications

• All other records and 1 og_s rel a ting to the en vi ronmenta 1 te.chni cal s*peci f'tcations shall be retafned for five yea-rs fol 1 owi'ng lo.ggi ng or

• recordtng.

5.7-1