Text

Appendix B to Operating License DPR - Environmental Technical Specifications for Salem Nuclear Generating Station Units 1 and 2
	ML19031A149
Person / Time
Site:	Salem
Issue date:	01/12/1976
From:	; Public Service Electric & Gas Co
To:	; Office of Nuclear Reactor Regulation
References
	Download: ML19031A149 (118)
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APPENDIX B TO OPERATING LICENSE DPR-ENVIRONMENTAL TECHNICAL SPECIFICATIONS FOR SALEM NUCLEAR GENERATING STATION UNITS 1 AND 2 PUBLIC SERVICE ELECTRIC AND GAS COMPANY DOCKET NOS. 50-272, 50-311

ENVLRONMENTAL TECHN!_CAL SPECJ:FICATIONS TABLE OF CONTENTS Section T;i.tle

Page 1.0 . DEF;I:NITLONS, .*ABBREVIATIONS *AND NOTES 1.1 DEFINITIONS 1.1-1

1. 2 ABBREVIATIONS 1. 2-1 1.3 NOTES 1.3-1 2.0 . LIMITING CONDITIONS FOR.OPERATION 2.1 THERMAL 2.1-1 2.1.la Maximum ~T Across Condenser 2.1-1 2 .l.lb Maximum ~T Across Condenser During Pump Outage 2.1-3 2.1.2 Maximum Discharge Temperature 2.1-5 2.1.3 Rate of Change of Discharge Temperature 2.1-7 2.2 CHEMICAL 2.2-1 2.2.1 Biocides 2.2-1 2.2.2 Suspended Solids 2.2-3 2.2.3 pH 2.2-5 2.3 RADIOACTIVE EFFLUENTS 2. 3.-1 2.3.l Specifications for Liquid Waste Effluents 2. 3-2*

e 2.3.2 Specifications for Liquid Waste Sampling and Monitoring 2. 3-3 2.3.3 Specifications for Gaseous Waste Effluents 2.3-8 2.3.4 Specifications for Gaseous Waste Sampling and Monitoring 2. 3-12 2.3.5 *Specifications for Solid Waste Handling and Disposal 2.3-:18 3.0 ENVIRONMENTAL SURVEILLANCE 3.0-1 3.1 NON-RADIOLOGICAL SURVEILLANCE 3.1-1 3.1.1 Abiotic 3.1-1 3.1.1.1 Chlorine 3.1-1.

3.1.1.2~ Dissolved Gases 3.1-2 3.1.1.3 Suspended Solids 3.1-3 3.1.1.4 Other Chemicals 3.1-4 3.1.1.5 Chemical Releases 3.1-6 3.1.1.6 Meteorolog;i.cal Monitoring 3.1-7 3.1.2* Biotic 3.1-8 3.1.2:1 General Ecological Survey 3.1-8 3.1.2.2 Impingement of Organisms 3.1""."15 e i

Section Title 3.1.2.3 Entrainment of -Planktonic Organisms 3.1-17 3.1.2.4 References 3.1-21 3.2 RADIOLOGICAL SURVEILLANCE 3.2-1 4.0 . SPECIAL SURVEILLANCE AND STUDY ACTIVITIES 4.1 EXPERIMENTAL ENTRAINMENT STUDIES 4.1-1 4.2. THERMAL AND CHEMICAL RESPONSES OF ESTUARINE ORGANISMS 4. 2-1 4.2.1 General 4.2-1 4.2.2 Temperature Preference Studies 4.2-2 4.2.3 Temperature and Chemical Avoidance Studies 4. 2-2 4.2.4 Cold Shock Studies 4.2-4 4.3 Thermal Plume Mapping 4.3-1 4.l1 Intake Velocity Study 4.4-1 5.0 ADMINISTRATIVE CONTROLS 5.1 RESPONSIBILITY 5.1-1 5.2 ORGANIZATION 5.2-1 5.3 REVIEW AND AUDIT 5.3-1 5.3.1 Nuclear Review Board (NRB) 5.3-1 5.3.2 Station Operations Review Committee (SORC) 5.3-1 5.4 ACTION TO BE TAKEN IF A LIMITING CONDITION FOR OPERATION IS EXCEEDED 5.4-1 5.5

PROCEDURES 5.5-1 5.6 PLANT REPORTING REQUIREMENTS 5. 6-1.

5.6.1 Routine Reports 5.6-1 5.6.1.1 Annual Environmental Operating Report 5. 6-1 5.6.1.2 Radioactive Effluents Release Report 5.6-3 5.6.2 Nonroutine Reports

5.6-3

5. 6.* 2 .1 Nonroutine Environmental Operating Reports 5.6-3 5.6.2.2 Nonroutine Radiological Environmental

! Operating Reports I 5.6-5 5.6,.2.3 Nonroutine Radioactive Effluent Reports 5.6-6 5.6~3 Changes in Environmental Technical Specifications 5.6-7 5.7 RECORDS RETENTION 5.7-1 ii

Section Title 3.1.2.3 Entrainment of Planktonic Organisms 3.1-17

.3.1.2.4 References 3.1-21 3.2 RADIOLOGICAL SURVEILLANCE 3.2-1 4.0 *sPECIAL SURVEILLANCE AND STUDY ACTIVITIES 4.1 EXPERIMENTAL ENTRAINMENT STUDIES 4.1-1 4.2 THERMAL AND CHEMICAL RESPONSES OF ESTUARINE ORGANISMS 4. 2-1 4.2.1 General 4.2-1 4.2.2 Temperature Pref ererice Studies 4.2-2 4.2.3 Temperature and Chemical Avoidance Studies 4.2-2 4.2.4 Cold Shock Studies 4.2-4 4.3 Thermal Plmne Mapping 4.3-1 4.4 Intake Velocity Study 4.4-1 5.0 ADMINISTRATIVE CONTROLS 5.1 RESPONSIBILITY 5.1-1 5.2 ORGANIZATION 5.2-1 5.3 REVIEW AND AUDIT 5.3-1 5.3.1 Nuclear Review Board (}lRB) 5.3-1 5.3.2 Station Operations Review Connnittee (SORC) 5.3-1 5.4 ACTION TO BE TAKEN IF A LIMITING CONDITIO~

FOR OPERATION IS EXCEEDED 5.4-1 5.5

PROCEDURES 5.5-1 5.6 PLANT REPORTING REQUIREMENTS 5. 6-1.

5.6.1 Routine Reports 5.6-1 5.6.1.1 Annual Environmental Operating Report 5.6.,-1 5.6.1.2 . Radioactive Effluents Release Report 5.6-3 5.6.2 Nonroutine Reports 5.6-3 5.6.2.1 Nonroutine Environmental Operating Reports 5.6-3 5.6.2.2 Nonroutine Radiological Environmental Operating Reports 5.6-5 5.6.2.3 Nonroutine Radioactive Effluent Reports 5.6-6 5.6.3 Changes in Environmental Technical Specifications 5.6-7 5.7 RECORDS RETENTION 5. 7-1 ii

e LIST OF TABLES Table No. Page No. Title 2.3-1 2.3-19 Radioactive Liquid Sampling and Analysis 2.3-2 2.3-20 Radioactive Gaseous Waste Sampling and Analysis 2.3-3 2.3-21 PWR Liquid Waste System Specifications 2.3.:.4 2.3-22 PWR Gaseous Waste System Specifications 2.3-5 2.3-23 Gamma and Beta D*ose Factors 3.1-1 3.1-23 Water Quality Analysis Parameters 3.1-2 3.1-24 Summary of Aquatic, Terrestrial and Aerial Sampling Programs 3.1-3 3.l-24a Anticipated Chemical Waste Discharge 3.2-1 3.2-5 Operational Environmental Radiological Monitoring Program 3.2-2 3.2-8 Preoperational x.J_ _and a Values

2-3 3.2-10 Sensitivity Levels for Environmental Sample Analyses 5.6-1 5.6-9 Environmental Radiological Monitoring Program Summary e* iii

LIST OF FIGURES Figure No. Page No. Title 3.1-1 3.1-25 Biological Sampling Stations in the Vicinity of Artificial Island 3.2-1 3.2-12 Locations of Radiological Sampling Stations within a 10 Mile Radius of the Site 5.2-1 5.2-2 Organization Chart Showing Corporate Interrelationships

5;2-2 5.2-3 Mechanical Division Organization Chart 5.2-3 5.2-4 Station Organization Chart iv

1.0 - DEFINITIONS, ABBREVIATIONS AND NOTES 1.1 DEFINITIONS

1. AMBIENT TEMPERATURE Temperature of the river unaffected by localized waste heat discharge; temperature of the river outside the designated mixing zone.

2. AMPEROMETRIC TITRATION Sp~cific adaptation of polarographic principles which are used to measure the total re~idual chlorine or to differentiate between the free and combined available chlorine.

3. CALIBRATION Use of a known quantity of a measured parareeter to determine the accuracy of the measuring instrument.

4. CHLORINE DEMAND The amount of chlorine required to oxidize substances in the water which reduce free chlorine.

5. COMBINED AVAILABLE CHLORINE RESIDUAL i

Residual consisting of mono-, di-, and trichlorornines.

1.1-1

6, CONDENSER Shall include the three condenser shells utilized in the Circulating Water System for each unit.

7. CONDENSER OUTLET TEMPERATURE The average condenser outlet circulating water temperature of those condenser sections in service measured as per DISCHARGE TEMPERATURE.

8. CONDENSER SHELL A single heat exchanger in the Circulating Water System which includes two inlet and outlet water boxes and two tube bundles.

9. CONTROL STATION Sample location that is far enough away from the station that it will not be affected by radiOlogical emissions or oth~r station releases.

10. DISCHARGE TEMPERATURE The average temperature of the six 84 inch ID discharge lines for each unit. The temperatures are measured at a point approximately 20 feet downstream from the condenser outlet water boxes.

1.1-2

11. DISCHARGE VELOCI'l;\

//)-inch The average of tlw , . ..,.. ~,',' \ U\::1;, :~am the tlrtt*I* 1 1

I :,;,nit.

ID circulating wat,*\ ,\\~'h<irl_'..t.:: ?ipes frofll t*!f

. I I* (l)SS-This number is cal1.'\tL . \.tt,,!, U2.£.-;~i on disch[fl'I'."

sectional area and ~~it~' t' 101-1.

12. EMERGENCY NEED FOR ~\' 1~}~:'{

I I r1;*.4 to

An emergency need .t\.':* power >frall be conq '. ;i* *mand 4

exist if the syst ~m '.::;. unU.k'=::::*r to meet f 11" * , .-:

after the licensee ':'.c,~~ ctttc::*:;}:2.d to sat Jc~ I! ~-

requirements by op~.r~ning all other ava1J:tli In base load units.

13. ENVIRONMENTAL SAffPLES Samples of soil, air,,. -.:ater, i.::::..:ta, or biul11jt;l!*iil-material collected fc-:- the pur;1:ses of anol y1 1 I Ht

14. ENVIRONMENTAL SIGNIFI*:_.:...:iCE Excee d ing a report

1 2*~.J.., ' or

w11~n, i"n the tJ/11 11 /tiii of the Station Super1nt2::.c:2nr:, an ~vent whicli

,,,u~;~ an adverse impact on ti-.e ;:-:wirorn:1<.~1t has occtlf* ,.,,,/ 1

15. FREE AVAILABLE CHJ,OJL~.~-z .?. ES IDL'i,",

* ,,. **~.7,..,r,i:.i

- .; ;".1.*~ i** te ions

( I JI'* I I ,. j1ypo-Residual c_ons1st1ng r",,

chlorous acid ( HOCJ.;, * ',r ;r;r, ...' -:r.v,1r chlorirH' / I ;j **1 ) '

16. FUNCTIONAL TEST Use of a simulated .1 i *//.:d r,v , .*,.k source !:II II1'.

1 µrmine instrument operafJ.i .1 i ,. I""

I . I* *?

17. GAMMA SCAN (GAHNA SPECTROSCOPY)

Identification of gamma emitting isotopes, using a multi-channel analyz~r.

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

19. INSTRUMENT CHECK Visual inspection of a monitor readout.

20. INTAKE TEMPERATURE The temperature of the circulating wate.r as measured at the inlet to the condenser shells; the temperature in the service water headers to the nuclear area and turbine area.

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

22. RADIOLOGICAL REVIEW POINT The activity level of an environmental radiological parameter that exceeds a preoperational value by a calculated amount, based on the standard deviation of that parameter during the pre.operational monitoring program.

1.1..:4

23. REPORT LEVEL The numerical level of an environmental parameter below which the enviro~mental impact is considered reasonable based on available information.

24. SPECIAL STUDY PROGRAMS Environmental study programs designed to evaluate the impact of station operation on an environmental para-meter.

25. TOTAL AVAILABLE CHLORINE RESIDUAL Sum of free and combined available chlorine residuals.

1.1-5

1.2 ABBREVIATIONS

1. EPA United States Environmental Protection Agency

2. JTU Jackson Turbidity Units

3. MDA Minimum Detectable Activity

4. MHT Mean High Tide

5. MLT Mean Low Tide

6. MT Mean Tide

7. NPDES National Pollutant Discharge Elimination System

8. NRC United States Nuclear Regulatory Commission 1.2-1

1.3 NOTES

1. The Environmental Technical Specifications are limita-tions, condit.ions. and requirements which are considered necessary for the protection of the environment. Safety Technical Specifications are imposed upon plant opera-tion in the interest of the health and safety of the public.

Compliance with the Saf~ty Technical Specifications shall have precedence over the Environmental Technical Specifications at all times.

2. Each Monitoring Requirement shall 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 provisions provide allowable tolerances for performing monitoring activities beyond those specified in the nominal monitoring interval. These tolerances are necessary to provide operational flexibility because of scheduling, performance considerations and environmental influences *

.e 1.3-1

20 0 LIMITING CONDITIONS FOR OPERATION 2.1 THERMAL 2 .1. la MAXIMUM £..T ACROSS CONDENSER DURING NORMAL OPERATION Objective*

To limit thermal stress to the aquatic ecosystem by limiting the maximum

~T across the condenser during normal operation.

Specification The maximum ~T across-the condenser shall not exceed 16.5°F during normal operation with all six circulating water pumps operating. In the event that the specification is exceeded corrective action shall be taken to reduce the ~T to within specification. Such corrective action could

(

include cleaning condenser water boxes or reduction of unit power level, unless an emergency need for power exists.

Monitoring Requirement The temperature differential across the condenser shall be monitored every hour utilizing the computer printout of the intake and discharge temperature measurements. The intake temperature is measured at each of the two inlets to each condenser shell. The discharge temperature is measured at a point downstream of the condenser in each of the two 84-inch ID discharge lines from each condenser shell. The range of this instrumentation is 0 - 150°F and the system accuracy is +/- 0.5°F.

If the plant computer is oµt of service, the intake and discharge temperatures shall be monitored every two hours utilizing local reading instrumentation tmtil the plant c~mputer is returned to service.

2.1-1

_,I - - L _____ _i Bases The condenser cooling water system was designed to minimize thermal stress to organisms which may be entrained in the cooling water discharge *

.The overall impact on all species is not expected to be significant for the following reasons:

1. Comparatively small amounts of water are utilized for cooling purposes compared to tidal flow (on the order *of 1%) *

2. No thermal blockages for .the Delaware estuary are predicted by the thermal plume model.

I

3. Studies show almost total survival among most potentially entrainable important species found in the vicinity of the plant exposed for 10 minutes to a ~T of 16.5°F. During normal plant operation the period of entrainment will be less than 4 minutes

2.1-2 n

2.1.lb MAXIHlJ}l ~T ACROSS CONDENSER DURING PUMP OUTAGE Objective To limit thermal stress to the aquatic ecosystem by limiting the maximum

~T across the condenser during pump outage.

Specification

1. The maximum ~T across the condenser shall not exceed 16o5°F for more th.2.n 24 consecutive hours oecause of scheduled maintenance and inspection ..

2. The maximum AT across the. condense~ shall not exceed 16.5°F for more than 72 consecutive hours for reasons of pump failure.

3. At no tilile. Will the Kr. across the condenser exceed 27 .5°F .. *

In the event that either specification is exceeded, corrective action shall be taken to reduce the ~T to within specification. Such

'corrective action could include cleaning condenser water boxes or r.eduction of limit power level, unless an emergency need for power exists~

Monitoring Requirement The temperature differential across the condenser shall be monitored every hour utilizing the computer printout of the intake and discharge temperature measurements. The intake temperature is measured at each of the two inlets to each conaenser shell. The discharge temperature is measured at a point downstream of the condenser in each of the two 84-inch 2.1-3

ID discharge lines from each condenser shell. The range of this instrumentation is 0 - 150°F and the system accuracy-is+/- 0.5°F.

If the plant computer is out of service, the intake and discharge temperatures shall be monitored every two hours utilizing local reading instrumentation until the plant computer is returned to service.

Bases The condenser cooling water system was designed to .. operate with a llT that would minimize thermal stress to organisms. The U. S. Environmental Protection Agency has set. a limit of 27.5°F as a maximum liT permitted under the NPDESP permit number NJ 0005622. The,overall impact of occasional operating delta temperatures in excess of 16.5°F is.not expected to be significant for the following .reasons:

1. Less cooling water would be required during operation at the higher.

A_T.than during normal operation.

2. No thermal blockages for the Delaware estuary are predicted by the thermal plume model.

3. Studies show a relatively high survival among potentially entrainaole important species found in the vicinity of the plant exposed for 10 minutes to a 11.T of 27.5°F.

.. During a pump outage the period of entrainment will* be less than 8 minutes.

2.1-4

.. /"' ...... .

2.L2 MAXTI1UM DISCR\RGE TEMPERATURE Objective To limit thermal stress to the aquatic ecosystem. by limiting the plant discharge water* temperature.

Specification

1. The maximum condenser discharge water temperature shall not exceed 104°F for more. than two conse~utive hours within any 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months period with all six circulating water pumps in operation.

2. In the event that fewer than six circulat:ip.g water pumps are in operation.., the maximum condenser discharge water temperature shall not exceed ll.5°F for more than eight consecutive hours within any 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months periodp 3o In the event-specifications 2.l.2ol or 2.lo2.2 are exceeded corrective action shall be taken to reduce the condenser discharge water temperature* to within specification. Such cor}:'ective action.could include cleaning condenser water boxes or reduction of unit power level, unless an emergency need for power e.~ists:

Monitoring Reo irement 11 Discharge temperature shall be monitored every hour utilizing the average of the computer printout of the discharge tempera-ture measureoents. The discharge temperature is measured at a*point downstream of the condenser in each of the two 84-inch .

. ID discharge lines from each condenser shell. The range of this instrumentation is 0-150°F and accuracy is+ 0.5°F.

If the plant computer is out of service~ the discharge temperature shal.l be monitored every two ho":lrs utilizing local reading instrumentation until the plant computer is returned to service.

2.1-5

Bases Ichthyological Associates (IA) studies performed from June 1968 through December 1973, show 25 records of r.tver tempera-o tures > 84 F. Twenty-one of these records were at river surface and only one was at night. From 1970 through 1973 the Uo S. Geological Survey temperature sensor at Reedy

. 0 Island recorded temperatures~ 84 Fon only four dateso *The earliest calendar date of record by IA was June 26 (in 1969);

the.latest was September 7 (in 1973)0 During this period for potentially high temperatures, phyto-plankton, zooplankton, and ichthyoplankton have been annually collectedo These non-motile organisms encountering the plume can experience mortality only i f lethal time-temperature histories are e..xperienced. At the predicted velocity range, effects on drifting organfsms and passive life stages of motile species are minimized by short exposure timeo Effects on sessile benthos in the near -field (outside the area of maximum temperature and velocity and -scouring) will be negligible* since the plume will be primarily a surf ace phenonmenon.

Motile organisms encountering a thermal plume will either (1) pass through it, * (2) pref er it over ambient conditions, or (3) avoid it. Avoidance can be considered detrimental in that its result is similar to a loss of potential habitat.

However, only a minor portion of the total available habitat will be made unavailable by the temperature-velocity pattern.

Delaware River organisms will not be isolated from environ-mental conditions pre_sently available to them~ The discharge velocity will exclude most motile organisms from the maximum temperatures.

. 2.1. 3 RATE OF CHANGE OF DISCHARGE TEMPERATURE Objective To minimize thermal stress to the aquatic environment due to sudden changes in water temperature.

Specification

1. The rate of change of discharge temperature shall not exceed 8°F per hour during normal plant shutdowns.

If this specification is exceeded, the rate of reduction of plant power level shall be reduced such that the rate of change of discharge temperature is within specification.

This limitation may be exceeded for brief periods as necessary to protect plant equipment and for certain safeguard operations which cannot be limited or negated by plant operation. These safeguard operations include automatic plant trips and compliance with the Safety Technical Specifications.

2. Both units shall not be intentionally shut down concurrently during the period of November through April. This specification is not applicable if shutdown is required to protect the health and safety of the public or for compliance with the Safety Technical Specifications.

Monitoring Requirement Same as Specification 2.1.2, except that the discharge temperature shall be monitored every 15 minutes during power reductions of greater than 25% of full power.

2.1-7

Bases All. organisms have lower lethal temperatures. In temperate latitudes, such lethal temperatures are generally reached only when the ambient water temperature approaches freezing. The phenomenon of "cold shock" has been found to be most severe during the period of low ambient water temperatures (2_ 40°F).

The likelihood of reaching lower lethal temperatures can be minimized by maintaining a heated discharge. during the period when ambient temperatures are < 40°F. The potential for cold shock and its effects will be minimized since the thermal effluent from one unit will compensate for possible shutdown of the other unit *

. 2.1-8

2.2 CHEMICAL 2.2.1 BIOCIDES Objective To insure that the chlorine residual released from the Circulating Water and Service Water Systems is controlled and will not have an adverse effect on the natural aquatic environment of the receiving waters.

Specification

.J-. The concentration of free chlorine in.the Circulating Water System and Service Water System shall not be greater than 1.0 mg/liter at the outlet of the final heat exchanger.

If this specification is exceeded, the chlorine addi-tion rate shall be reduced as necessary to operate within the specification.

2. Circulating Water and Service Water pump intakes shall not be chlorinated more than 3 times per day. Chlori-nation periods shall not exceed 30 minutes. Chlorina-tion of more than 3 Circulating Water pump intakes at one time shall not be permitted.

Monitoring Requirement The outlet water boxes of the condenser shells that are being chlorinated shall be continuously monitored foi free chlorine residual during treatment. The Service Water System shall be monitored at the 30-inch supply header to the turbine generator area during treatment.

2.2-1

The continuoui monitoring (during treatment) .shall be per-formed using a ~allac~ & Tiernan Series 50-236 free chlorini residual analyzer equipped with a strip chart recorder. The

_ Circulating Water System and the Service Water System each have a sep~rate free chlorine residual analyzer.

The chlorine monitors shall be calibrated once per month with an amperometric titrator and using ASTM Methods D-1235 and D-142, to 0.01 ppm accuracy.

If the chlorine monitors are inoperable, free chlorine residual shall be determined by manual analysis of a grab sample taken during the chlorination cycle.

Bases The Water Quality Certificate issued by the Delaware River Basin Cormnission.for Salem Nuclear Generating Station limits the free chlorine residual in circulating w.ater discharged from the plant to maximum of O~l mg/liter. This also conforms to EPA-NPDES requirements of 0.2 to 0.5 mg/liter~

Intermittent treatment of cooling circuits .in fresh and brackish water environments with a biocide (chlorine, sodium hypochlorite) is a reliable method for maintaining these circuits free frora fouling.

It has been determined from past experience that treatment with chlorine at a concentration of 0.5 mg/liter free chlorine residual at the heat exchanger outlet (e.g.,

condenser) for 30 minutes three times a day is usually sufficient for maintaining system cleanliness.although higher concentrations in the heat exchangers may be needed periodically. The discharge will be diluted sufficiently, 2.2-2.

however, to maintain the free chlorine residual discharged to the river at 0.1 mg/liter or less.

The circulating water will be chlorinated by controlled injection of sodium hypochlorite into the intake water to the condensers. Three of the twelve intakes are chlorinated at a time as a group. The period of chlorination will be no greater than 30 minutes and will be done 3 times per day. The rate of sodium hypfchlorite addition is controlled to maintain a 1.0 mg/liter free chlorine residual or less at the condenser outlet. The discharge is diluted with unchlorinated water and the free chlorine residual of the discharge to the river will therefore be less than 0.1 mg/liter.

The service water system will be chlorinated at a frequency not to exceed 3 times a day for periods of no greater than 30 minutes, and not at the same rime as the Circulating Water System. The free chlorine residual of 1.0 mg/liter, or less which will be maintained at the outlet of the final heat exchanger, will therefore be diluted to less than 0.1 mg/liter at the discharge to the river.

2.2.2 SUSPENDED SOLIDS Objective: To insure that suspended solids released from Non-Radioactive Chemical Waste Disposal System are controlled and will not have an adverse effect on the natural aquatic environment of the receiving waters.

Specification The average suspended solids concentration in the effluent from the Non-Radioactive Chemical Liquid Waste Disposal System shall not exceed 25 mg/liter on an annual basis *.

Monitoring Requirement A grab sample shall be taken once per day from the collect-ing basin discharge pipe and analyzed for suspended solids using a method which is acceptable to EPA. The sample shall be taken at the in-line pH monitoring probe in the discharge pipe. Samples shall be taken during periods of actual discharge and only on days when the collecting.basin is discharged.

Bases The non-radioactive chemical liquid waste basin is licensed to operate under permits issued for Industrial Waste Treatment Plants by the State of New Jersey. The suspended solids limitation is that which is requ'ired by the permits.

The filtration/g~avimetric method is the present means recognized by EPA for the measurement of suspended solids.

However, Proposed Water Quality Information, Vol. II, October 1973, by EPA, page 88, states that "accuracy data on actual samples cannot be obtained at this time."

2.2-4

2.2.3 pH Objective*

To insure that the pH of the effluent released from the Non-Radioactive Chemical Waste Disposal System is controlled and will not have an adverse effect on the natural aquatic environment of the receiving waters.

Specification The pH of the Non-Radioactive Chemical Liquid Waste Disposal System shall be within the range of 6.5 to 8.5 pH units.

If this specification is exceeded, the discharge shall be terminated until the pH is corrected to within Specification.

Monitoring Requirement The pH of effluents released from the collecting basin shall be monitored continuously at the pump discharge using an in-line pH probe with an accuracy of + 2%.

Bases The 6.5 to 8.5 pH limit on the Non-Radioactive Chemical Liquid Waste Disposal System has been set by the New Jersey Department of Environmental Protection and the Delaware River Basin Commission.

The collecting basin discharge valve is controlled by the continuously operating pH probe. The valve will not open unless collecting basin pH is within the range of 6.5 to 8.5 pH units.

No significant change in the background. J>H of the river water is expected: due to the operation of the Salem Station.

2.2-5

LIMITING CONDITIONS FOR OPERATION Radioactive Effluents Objective: To define the limits and conditions for the controlled release .

of radioactive materials in liquid and gaseous effluents to the environs to ensure that these releases are as low as practicable. These releases should not result in radiation exposures in unrestricted areas greater than a few percent of natural background exposures. The concentrations of radioactive materials in effluents shall be within the limits specified in 10 CFR Part 20.

To ensure that the releases of radioactive material above background to unrestricted areas be as low as 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 10 mrad, and an air dose due to beta radiation of less 2.3-1

than 20 mrad, at any location near ground level which could be occupied by individuals at or beyo~d the boundary of the site.

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

e. The annual total quantity of iodine-131 *discharged from each reactor at a site should not exceed 1 Ci.

2.3.l Specifications for Liquid Waste Effluents

a. The concentration of radioactive materials releas.ed in liquid waste effluents from all reactors at the site shall not exceed the values specified in 10 CFR Part 20, Appendix B, Table II, Column 2, for unrestricted areas.

b. The cumulative release of.radioactive materials in liquid waste effluents, excluding tritium and dissolved gases, shall not exceed 10 Ci/reactor/ca1endar quarter.

c. The cumulative release of radioactive materials in liquid waste effluents, excluding tritium and dissolved gases, shall not exceed

/

I I

20 Ci/reactor in any 12 consecutive months.

d. During release of radioactive wastes, the effluent control monitor shall be set *to alarm and to initiate the automatic closure of each waste isolation valve prior to exceeding the limits specified in

2. 3.1. a above.

e. The operability of each automatic isolation valve in the liquid 2.3-2

I radwaste discharge lines shall be demonstrated quarterly.

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

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

h. If the cumulative release of radioactive materials in liquid effluents, excluding tritium and dissolved gases_, .exceeds 2.5 Ci/reactor/calendar quarter, the licensee shall make an investigation to identify the causes for such releases, define and initiate a program of action to reduce su~h releases to the design objective levels listed in Section 2.3, and report these actions to the NRC in accordance witli. Specification 5. 6. 2 *. c (1) *

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

This notification shall be in accordance with Specification 5. 6. 2. c(3) ./

I 2.3.2 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 discharge and the average dilution flow and length of time over which each discharge _occurred. Sample analysis results and other reports shall be submitted as required by Section 5.6.1 of these Specifications.

2.3-3

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

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

,_. of each principle gamma emitter in accordance with Table 2.3-1 to demonstrate compliance with Specification 2.3.l us.ing the flow rate into which the waste is discharged during the period of

~is charge.

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 ta.nk volumes shall be recirculated.

d. The.radioactivity in liquid wastes shall be continuously monitored and recorded during releases. Whenever these monitors are inoperable for a period not to exceed 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months , two independent samples of each tank to be discharged shall be analyzed and two plant personnel shall inde~endently check valving prior to the discharge. If these monitors are inoperable for a period exceeding 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months , no release from a liquid waste tank shall be made and any release in progress shall be terminated.

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

f. All liquid effluent radiation monitors shall be calibrated at least quarterly by means of a radioactive source which has been calibrated to a National Bureau of Standards source. Each monitor shall also have a functional test monthly and an instrument check prior to making a release.

2.3-4

g. The radioactivity in steam generator blowdown shall be continuously monitored and recorded. Whenever these monitors are inoperable, the blowdown flow shall be diverted to the waste management system and the direct release to the environment terminated.

Bases: The release of radioactive materials in liquid waste effluents to unrestricted areas shall not exceed the concentration limits specified in 10 CFR Part 20 and should be as low as 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 unrestricted area will not exceed 5 mrem. At the same time, these specifications permit the flexibility of operation, compatible with considerations of health and safety, to assure that the public is provided a dependable source of power under unusual operating conditions whicn may temporarily result in releases 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 operating conditions,' and exerting every effort to keep levels of radioactive material in liquid wastes as low as practicable, the annual releases will not exceed a small fraction of the concentration limits specified in 10 CFR Part 20.

The design objectives have been developed based on operating experience taking into account a combination of variables including defective fuel, primary system leakage, primary to secondary system leakage, steam generator blowdown and the performance of the various waste treatment systems, and

~-*

are consistent with 10 CFR Part sp.36a *.

2.375

Specification 2.3.1.a requires* the lic~nsee to limit the concentration of radioactive materials in liquid waste effluents released from the site to levels specified in 10 CFR Part 20, Appendix B, Table II, Column 2, for unrestricted areas. This specification provides assurance that no member of the general public will be exposed to liquid containing radioactive materials in excess of limits considered permissible under the Commission's Regulations.

Specifications 2.3.1.b and 2.3.1.c establish the upper limits for the release of radioactive materials in liquid efflu~nts. The intent of these Specifica-tions is to permit the licensee the flexibility of operation to assure that the public is provided a dependable source of power under unusual operating conditions which may temporarily result in releases higher than the levels normally achievable when the plant and the liquid 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 requirements of 10 CFR Part 50, Appendix A, Design I

/

Criterion 64, Specifications 2.3.1.d and 2.3.1.e require operation of suitable equipment to control and monitor the releases of radioactive materials in liquid wastes during any period that these releases are taking place.

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 :~P liquid effluents to as low as practicable consistent 2.3-6

,f;.,_

~ ....

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 design objective annual quantity during any calendar quarter.

Specification 2.3 .* 1.g restricts the amount of radioactive material that could be inadvertently released to.the environment to an amount that will not exceed the Technical Specification limit.

In addition to limiting conditions for operation listed under Specifications 2.3.1.b and 2.3.1.c, the reporting requirements of Specification 2.3.1.h delineate 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 any calendar 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 calendar quarter in which the release occurred as required by Specification 5.6.2 of these Technical Specifications.

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 assur~ce that radioactive materials in liquid wastes are properly 2.3-7

controlled and monitored in conformance 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 .. Reports on the quantities of radioactive materials released in liquid waste effluents are furnished to the Commission according to Section 5.6.1 of thes~

Technical Specifications. On the basis of such reports and any additional information the Commission may obtain from the licensee or others, the Connnission 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 2.3.2 include all the monitored release points as provided for in Table 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 !

I considered)

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

,; ?Q. sum of the individual noble gas radionuclides determined

l. l.

to be present by isotopic analysis K = the average total body dose factor due to gamma emission (rem/yr per Ci/sec)

L = the average skin dose factor due to beta emissions (rad/yr per Ci/sec) 2.3,-8

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, L, M and 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/QT) l.Q;L.

]_ ]_ ]_

M = (l/QT) liQiMi N = (l/QT) IiQiNi Where the values of K., ]_

L.,

1 M.]_ and N.1 are provided in Table 2.3-5, and are site dependent gamma and beta dose factors:

Q = the measured release rate of the radioiodines and radioactive materials in particulate forms w~th half-lives greater than eight days.

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

< 1 and J < 1 2.3-9

(2) The release rate limit of all radioiodines and radioactive materials in particulate fonn with half-lives greater than eight days, released to the environs as part of the gaseous wastes from the site shall be such that:

5 1.5 x .10 ~ < 1

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

< 1 and

< 1 (2) The average release rate of noble gases from the site during any 12 consecutive months shall be:

< 1

< 1 (3) 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 shall be such that 13 [i.s 5 x 10 Qv J < 1 (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 c~nsecutive months shall 2.3-:-10.

be such that:

5 25 [i.5 x 10 Qv] . < 1 (5) The amount of iodine-131 released during any calendar quarter shall not exceed 2 Ci/re~ctor.

(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 inyestigation 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.

(1) If the average release rnte of noble gases from the site during

.any calendar quarter is such that:

so[ QTvNv J > 1 or

> 1 (2) If the average release rate per site of all radioiodines and radioactive materials in particulate form with half-lives greater than ~ight days during any calendar quarter is such that:

50 [1.5 x 105~ J .> 1 2.3-11

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

d. During the r*elease of gaseous wastes from the primary system waste gas holdup system the effluent monitors listed in Table 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 aut.omatic isolation val:ve 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).

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 form requires notification. This notifica-tion shall.be in accordance with Section 5.6.2.c(3).

2.3.4 Specifications for Gaseous Waste Sampling and Monitoring

a. Plant records shall be maintained and reports of the sampling and analyses results shall be submitted in accordance with Section 5.6 of these Specifications. Estimates 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 noted in Specification 2.3.4.c, -shall be continuously monitored for gross radioactivity and the flow continuously measured and recorded. Whenever these monitors 2.3-12

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 gas holdup system, the gross activity monitor, the iodine collection devices and th~ particulate collection device shall be operating.

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 forms and radioiodines shall be *performed in accordance with Table 2o3-2.

Bases:. 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 practical 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 radiation will not exceed 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 will receive an annual dose greater than 15 mrem from fission product noble gases, and that the annual dose to any organ of an individual from radioiodines and radioactive material in particulate 2.3-13

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 public is provided with a dependable source of power under unusual operating 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 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 back-ground 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 Part 20.

For _Specification 2.3.3.a(l) '* gamma and beta dose factors for the individual noble gas radionuclides have been calculated for th~ plant gaseous release 2.3-14

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 Draft Regulatory Guide LAA.*

Dose calculations have been made to determine the site boundary location with the highest anticipated dose rate from noble gases using on-site meteorological data and the dose expressions provided in Draft Regulatory Guide 1.AA. The dose expression considers the release point location, building wake effects, and the physical characteristics of the radionuclides.

The off site 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 radionuclide pathways to man. The pathways which were examined for these Specifications are: 1) individual inhalation of airborne radio-nuclides, 2) deposition of radionuclides onto green leafy vegetation with subsequent consumption 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 Draft Regulatory Guide LAA. 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 on-site meteorological data and the expressions described in Draft Regulatory Guide l.AA.

2.3-15

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.'

For radioiodines and radioactive material in particulate form with half-lives greater thari eight days, the most restrictive location is a dairy farm located 6600 meters in the NW direction (vent X/Q = 1.1x10- 7 3 sec/m ).

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 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 any calendar quarter and that the proposed program of action to reduce such release rates to the design objec-tives shall be described.

Specification 2.3.3.d requires that suitable equipment to monitor and control the radioactive gaseous releases are 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 2.3-16

quantity should assume instantaneous ground release, a X/Q based 5 percent meteorology, the average gross* energy ~s 0.19 Mev per disintergration (considering Xe-133 to be the* princ~pal 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 ~uidelines.

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 assurance that radioactive materials reieased in gaseous waste effluents are properly controlled and monitored in conformance 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 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 5.6.1 of these Technical Specifications. On the basis of such reports and any additional information the Commission may obtain from the licensee or others, the Commission may from 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.

2.3-17

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_ principle radionuclide composition.of all radioactive solid waste shipped offsite.

b. Reports of the radioactive solid waste shipments, volumes, principle radionuclides, and total curie quantity, shall be submitted in accordance with Section 5.6.1.

Bases: The requirements for solid radioactive waste handling and disposal given under Specification 2, 3. 5. _:pr_oyide assuran.ce that solid radioactive materials stored at the plant and shipped of£site are packaged in conformance with 10 CFR Part 20, 10 CFR Part 71, and 49 CFR.Parts 170-178.

2.,3-18

TABLE 2.3-1 RADIOACTIVE LIQUID SAMPLING AND ANALYSIS Detectabre Liqu:d Sampling Frequency Type of Concentr<Jtions So*Hct! and Analysis Activity Anarysis (µCi/ml) a b

A. Monitor Tank Releases

Each Batch Principal Gamma Emitters 5 x 10-7 One Batch/Month Dissolved Gases f 10-:-s Weekly Compositec Ba-la-140, l-131 10-6 Monthly Compositec H-3 10-s Grosso: 10-1 Quarterly Compositec Sr-89, Sr-90 5 x 10-s B. Weeki yd 10-6 Primary Coolant . 1-131, 1-133 b

c. Steam Generator Blowdown Principal Gamma Emitters 5 x 10-i Weeki ye Ba-La-140: 1-131 10-6 One Sample/Month* Dissolved Gases f 10-s

.. Monthly Compositec H-3 10-s

..*.. - .. Gross a: 10-1 Quarterly Compositee Sr-89, Sr-90 5 x 10-&

aThe detectability limits for activity analysis are bnsed on the technical feasibility and on the potential significance in the environment of the qu.:intities released_ For some nuclides, lower detection limits may be readily achievable, and

.. when nuclides are measured below the stated limits, they should also be reported_

bFor certain mixtures of gamma emitters, it may not be possible to measure radionuclides in concentrations near their

. sensitivity limits when other nuclides are present in the sample in much greater concentrations_ Under these 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:uantity of liquid sampled is proportional to the quantity of liquid waste ciischarge d. .

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

"To be representative of the average quantities and concentrations of radioactive matedals 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.

f For dissolved noble gas~s in water, assume a MP,C of 4 x 10*5 µCi/ml of water.

TABLE 2.3-2 RADIOACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS Detectable Gaseous Sampling Frequency Type of Concentrations Source and Analysis Activity Analysis (µCi/ml)a b

Each Tank to Principal Gamma Emitters 10-4 A. Waste Gas Decay Tank Rele_ases be Released H-3 10-6 c

Principal Gamma Emitters 10-4 B* Containment Purge Releases Each Purge H-3 10-6 10-.ib* c C. Condenser Air Ejector Monthly Principal Gamma Emitters H-3 10-6 c

0. Environmental Release Points Monthly Principol Gamma Emitters 10-4 b.

.. (Gas Samples)

H-3 10-6*

Weekly (Churcoal Sarnple) 1-131 10-12 Monthly (Charcoal S_amp!t:') 1-133, 1-135 10-10 Weekly (Particulates)d Principal Gamma Emitters (Ba-La-140, I-131 and others) 10-11 Mo.nthly Composited (Pa rt icul ates)

.. Gros~ a . 10-11 Oi.1arterly Composited Sr-89, Sr-90 10-11 (Particulates) .

~The above detectability limits for activity analysis are based on technical feasibility and on the potential ~ignificance in the environment of the quantities released. For some nuclides, lower detection limits may be readily achievable, and when nuclides are measured below the s.tated limits, they should also be reported.

bFor certain mixtures of gamma emitters, it may not be possible to measure radionuc!ides at levels near their sensitiv-ity limits when other nuclides are 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 measurable.

c Analyses shall also be performed fa flowing t?ach refueling, startup, or similar operational occurrence which could alter the mixture of radionuclic;les.

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 .3-20

TABLE 2.3-3 SALEM STATION LIQUID WASTE SYSTEM LOCATION OF PROCESS AND EFFLUENT MONITORS AND SAMPLERS REQUIRED BY TECHNICAL SPECIFICATIONS Grab M!!asurement High Radiation Auto Control to Gross Activf ty Sample Gross Dissolved Isotopic Liquid Process $tream or Release Point Alarm Isolation Valve Continuous Station Activity I Gases Alpha H-3 Analysis *Level Monf tor

Alarm Miscellaneous Monitor Tanksb x x x x x x x Chemical Drain Tank x. x x x x x x Laundry and Hot Shower Tanksa.

.. x x .*x x x x x Primary Coolant System .. "

x x I\)

w Liquid Radwaste Discharge Pipe x x x x . ,*

~

I-' *Steam Generator Slowdown Sy.stem x " x x ., *x *x x x x .X Outdoor Storage Tanks (potentially radioactive)

Primary Water Storage Tank Xe x x x Refueling Water Storage Tank . *'

Component Cooling Systems X* x x Turbine Building Sumps {Floor Drains) \..

xd'. x x \

x a The contents of the Laundry and Hot Shower Tanks are sampled, analyzed, and then filtered prior to release through the liquid radwaste d1 sc~arg!!

r.

p.ipe. . . .

b Includes Waste Monitor Tanks, Waste Monitor Holdup Tank, CVCS Monitor Tanks.

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

d Grab sample to be t.aken and analyzed each 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months whenever the gross activity .in the secondary coolant system exceeds 10-5 uC1/ml (Except H-3).

TABLE 2.3-4

.1 SALEM STATION GASEOUS WASTE SYSTEM LOCATION OF PROCESS AND EFFLUENT MONITOhS AND SAMPLERS REQUIRED SY TECHNICAL SPECIFICATIONS Grnh Process .Stream or Release Poin~

Rad1 at1on Alann Auto Control to

!solution Vulv1:

Continuous Monitor . Silmp!o

.S1;1t1on Noble Gas I Measurement Particulate H*3 Alpha Waste Gas Decay Tanks x x x x x x Condenser Air Removal System x x x x x x x I x

Plant Vent ..

x xb x x x x x x Building Ventilation Systems Reactor Containment Building (whenever there is flow) x x xd x x x x x x N

Auxiliary Building and Radwaste Areaa Xe x x x x x VJ

.I rv Fuel Handling & Storage Buildinga Xe x x x x x N ; .*.

a ..

Turbine Gland Seal Condenser Xe x x x x x Waste Gas Discharge Line x x x*

., a Since these process str~ams or building ventilation systems are routed to the plant vent, the need for a continuous* monitor at the individual dis-

. charge point to the main exhaust duct is eliminated, One continuous monitor at the final release point is sufficient.

b Includes continuous noble gas monitor and continuous iodine and particulate samplers which are continuously monitored.

c Grab sample stations from which monthly gas samples (Table 2.3-2) are to be taken. Also, grab samples should be taken and measured*to determine the process stream or building ventilation system source whenever an unexplained increase.is indicated by the plant vent sampler-monitors *

. d Includes continuous noble gas monitor

/

TABLE 2.3-5 GA.i.'1MA AND BETA DOSE FACTORS FOR --,

I SALEM, UNITS 1 AND 2 X/Q -6 sec/m3 @ 1270 Meters, North

= 1.2 x 10

nose Factors for Vent K. L. M. N.

1.V 1.V 1.V 1.V Total Body . Skin Beta Air Gamma Air Noble Gas (rem/yr) (rem/yr} (rad/yr) (rad/yr}

Radionuclide (Ci/sec) (Ci/sec) (Ci/sec) (Ci/sec)

. -5 Kr-83m 8.6 x 10 0 0.043 0.35 I\.)

\,.)

Kr-85m 0.97 1.8 1.0 2.4 I

N

\,.).

Kr-85 0.012 1.6 0.012 2.3 Kr-87 3.0 12 3.1 12 Kr-88 7. 2.8 7.8 3.5 Kr-89 1.3 :J-2 1.4 13 Xe-13lm 0.34 0.57 0.43 1.3 Xe-133m 0.26 1.2 0.36 1.8 Xe-133 0.31 0.37 0.38 1.3 Xe-135m 1.2 0.85 1.3 0.89 Xe-135 1.4 2.2 1.5 2.9 Xe-137 0.18 15 0.19 15 Xe-138 2.9 5.0 3.0 5.7

3.0 ENVIRONMENTAL SURVEILLANCE The objective of the. Environmental Surveillance Program is to determine the effects o.f 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 Generation 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 "base-line" levels will reveal changes and trends that could be attributed to plant operation. As operating experience and surveillance data are obtained, the Environmental Surveillance Program will be modified to reduce or eliminate surveillance of those parameters that.have not been significantly. affected by plant op.eration.

3,0-1

.I

3.1 NON RADIOLOGICAL SURVEILLANCE e 3.1.1 ABIOTIC 3.1.1.1 Chlorine Objective To determine the concentration of free and total residual chlorine in the station effluent water in an ef f Drt to maintain an optimum chlorination P.rogram for prevention of heat exchanger fouling while minimizing the environ-mental impact on the receiving waters *.

Specification Grab samples shall be taken weekly (weather permitting) during a chlorination cycle and analyzed for free and total residual chlorine. The samples shall be taken in the Vicinity of the circulating water discharge, from the station intake water and from a point that is outside and dovmstream of the discharge water mixing zone.

Reporting RequireCTent In the event the analysis of° the sample taken from the point outside and downstream of the discharge water mixing zone indicates that the totai residual chlorine at the point exceeds the ambient total residual chlorine level in the river by 0.1 mg/liter, a report shall be made in accordance with Specification 5.6.2.

Bases This monitoring program will provide data on the

.1

l chlorine demand of the receiv~ng water as well as the concentration of fouling organisms present.

These parameters are subject to seasonal variation I

and will aid in maintaining an* optimum chlorination I [

program for prevention of heat exchanger fouling.

f 3.1.1.2 Dissolved Gases f I

.. Objective f

f.

To ascertain that the dissolved* oxygen level is not [

lt depressed to the extent that it may be harmful '

l to the indigenous population of the receiving l waters as a restilt of station operation.

Specification The dissolved oxygen levels shall be monitored once per month (weather permitting) utilizing the Winkler titration method in accordance with. APHA specifi-cation 218B 13th edition. Grab samples shall be taken at the intake structure, the outfall of the discharge and a point outside and downstream of the

.mixing zone. The samples shall be taken at depths of 10 feet 8 feet, and 18 feet, respectively. The standard deviation is expected to be within + 0.1 mg/1.

Reporting Requirement

_If dissolved_oxygen level is found to be less than 6 mg/1 at the discharge, a comparison study of the intqke, discharge and downstream dissolved oxygen levels shall be conducted to determine if the oxygen

depression has been caused by station, operation. If it is so determined, a report shall be made in accordance with Specification 5.&.2.

Bases Monthly analyses of dissolved oxygen will aid in differentiating between normal seasonal fluctuations and changes due to station ~peration.

The 6 mg/liter limitation is. required by the Water Quality Certificate issued by the Delaware River Basin Commission.

3.1.1.3 Suspended Solids Objective To determine the effect of plant operation on suspended solids in the.receiving waters.

Specification Suspended solids shall be monitored once per month (weather permitting). Grab samples shall be taken at the intake structure, the outfall of the discharge and at.a point outside and downstream of the mixiLg zone. The samples shall be taken at depths of 10 feet, 8 feet, and 18 feet, re*spectively. These samples shall be analyzed for suspended solids by means of a method acceptable to EPA. Dissolved solids shall not be monitored.

Reporting Requirement Reporting levels shall be developed after the initial phases of plant operation. Post-operational data will be related to preoperational data to y~eld norms from 3.1-3

which report levels will be established. An initial e~aluation of the reporting levels will be provided in the first annual report *.

Bases Monthly analyses of suspended solids will aid in differentiating between normal seasonal fluctu~tions, changes due to tide, wind and current, and those due to station operation.

The filtration/gravimetric method is the present means recognized by EPA for the measurement of suspended solids. However, Proposed Water Quality Information, Vol. II, October 1973, EPA, page 88 states that "accuracy data on actual samples cannot be obtained at this time."

Dissolved solids will not be measured since none of the applicable Regulatory agencies have issued guide-

lines for this parameter for the De"iaware River zone in the vicinity of the Sta~ion site .

Other Chemicals . .

Objective To determine the effects of plant operation' on the quality of the receiving water6.

Specification Grab samples shall be taken once per month (weather

.. permitting) and analyzed for the parameters listed in Table 3.1~1. The samples shall be taken at the intake structure, the outfall of the discharge and at a point outside and downstream of the mixing zone. The samples shall be taken at depths of 10 feet, 8 feet, and 18 feet, respectively. These* samples 3.1-4

shall be analyzed for the parameters listed in Table 3.1-1 by a method acceptable to EPA.

Reporting Requirement Reporting levels will be developed after the initial phases of plant operation. Post-operational data will be related to preoperational data I

to yield norms from which report levels will be established.

Bases This monitoring program will serve to determine the effect of station operation on the quality of the receiving water. An evaluation of the program, after six months of full power operation; will be performed and those parameters which can be shown to be not significantly affected by station operation will be.eliminated from the monitoring program subsequent to NRG staff review and approval. This program is in conformance with NPDES requirements.

The utilization of tests prescribed by EPA will insure the employment of current, state-of-the-art methods and accuracies.

3.1.1.5 Chemical Releases Objective To insure that chemical releases from the plant are identified by compound and quantity.

Specification A physical inventory of identifiable chemicals, excluding spent laboratory reagents and condenser tube corrosion products, discharged directly to the river shall be maintained and submitted as part of the annual report.

Monitoring Specifications The physical inventory of identifiable chemicals, excluding spent laboratory reagents, discharged directly to the river can be in the form of an estimation of discharge quantity by purchase order and inventory differential.

Bases Documenting the discharge of chemicals shall allow comparison with estimated releases given in Table 3.1-3. If chemical usage differs significantly (a factor of 3) from that indicated in the table (3.1-3) or if the need for other chemicals is determined, then a brief assessment of environmental impact shall be made.

Spent chemical reagents from the chemistry. laboratories are not to be included in the reporting requirement D.ecause of their small quantities and insignificant concentrations in liquids released. Condenser tuoe corrosion products are not a part of this chemical inventory.

3.1-6 I

3.1.1.6 Meteorological Monitoring Objective The objective of meteorological monitoring is to adequately measure and document meteorological conditions at the site.

Specification The ~eteorological monitoring. system shall conform to the recommendations in Regulatory Guide 1.23, Onsite Meteorological Programs, dated February 17, 1972, and include instruments to sense wind speed and direction, air temperature and vertical air temperature difference at heights above ground that are representative of atmospheric conditions that exist at all gaseous effluent release points.

Reporting Requirements Meteorological data shall be summarized and reported in a format consistent with the:recommendations of Regulatory Guide 1.21, Measuring, Evaluating, and Reporting Radioactivity in Solid Wastes and Releases of Radioactive Materials in Liquid and Gaseous Effluents from Light-Water-Cooled Nuclear Power Plants, Revision 1, dated June, 1974 ~nd Regulatory Guide 1.23, Onsite Meteorological Programs, dated February 17, 1972, and observations in a form 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 3.1-7

time of any of the meteorological instruments exceeds seven consecutive days, the total ~utage time and dates.

of outage, the c~use of the ~utage, ~nd the instrument(s) involved shall be reported within 30 days of the initial time of the outage to the U.S. Nuclear Regulatory Conunission, Division of Reactor Licensin*g. Any modifications to the meteorological monitoring program as described above shall have the written approval of the U.S. Nuclear Regulatory Commission, Division of Reactor Licensing, prior to initiation of the modification.

Bases The collection of meteorological data at the plant site will provide information which may be used to develop atmospheric diffusion pararne.ters to estimate potential radiation doses to the public resulting from actual routine or accidental releases o[

radioactive materials to the atmosphere. A meteorologi~al 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 10 CFR Part 51.

3.1.2 BIOTIC 3.1.2.1 General Ecological Survey The primary objective of this survey is to determine the effect of plant operation on the ecology and

.environment of the Delaware River f.stuar::r: and*

environs. The preoperational biological.monitoring e.

3.1-8

was initiated in 1968 and monitoring will be continued for 5 years after

_Unit No. 2 becomes operational. The program shall be discontinued only after approval by NRC staff. These studies will serve as a basis for assessment of the effects of plant operation on the ecology.

Study Plan The study area includes the Delaware River Estuary and some tributaries within an approximate 10-mile radius of the station. The biological parameters monitored are listed in Table 3.1-2 and the general sampling locations are shown in Figure 3.1-1.

Physiochemical parameters will be monitored in the various sampling programs and will typically include dissolved oxygen, temperature, salinity, pH, and water transparency.

Specification

1. Aquatic Studies

a. Phytoplankton Replicate phytoplankton samples shall be taken with a Van Dorn*.

sampler. Surface and near bottom samples shall be collected biweekly (weather permitting) within the study area illustrated in Figure 3.1-1.

These samples shall be examined quantitatively for chlorophyll a using the spectrophotometric method of Lorenzen(l). The standard error of cholorophyll a analysis at the 5 ug level is + 0.18 ug for the mean of two determinations( 2 ,J).

3.1-9

Generic identifications and enumerations shall be conducted. Distributions exhibited by the dominant taxa shall be emphasized.

A productivity study shall be performed bimonthly (weather permitting) at appropriate control and thermally affected stations along with chlorophyll~ analysis. Dissolved oxygen concentrations shall be determined.

The azide modification of the Winkler method(4) shal1 be used to determine dissolved oxygen levels in both light and dark bottles as well as in control samples. The precision of oxygen determination based on replicate samples is+/- 0.01 mg oxygen/liter.

b. Ichthyoplankton Ichthyoplankton samples shall be collected monthly (weather permitting) within the study area illustrated in Figure 3 .1-1. Surface and* ,near-bottom samples shall be collected at all stations. In addition, mid-water samples shall be collected at off shore stations where depth exceeds 20 ft. Replicate samples shall be taken at selected stations.

All samples shall be collected with metered 1/2 m plankton nets (0.5-mm mesh) towed at a constant" speed sufficient to keep the upper net at the surface. Bottom nets will be equipped with depressors to facilitate sampling near bottom.

3,1-10

"""'7-------* ,.:.,.:-~*

Ichthyoplankton shall be identified and enumerated. Identification*will be to species or to. the* lowest taxonomic level which specimen *condition permits. Results shall be expressed as number of organisms per cubic meter.

c. Zooplankton - Microplankton Microplankton samples shall be collected

'.o 2 ft below thesurfac~ and just above the bottom with a plankton pump. filter system using No. 20 nets (0.08 mm mesh) within the study area illustrated in Figure 3.1-1.

Additionally, integrated (surface to bottom) samples will be taken near the intake and at two sta~ions on a transect extending 1.5 miles offshore. The sampler design is modified from one described by Icanberry and RichardsonCS). It consists of a reinforced suction* hose coupled to an air-tight Plexiglas cylinder. Water.is pulled through the hose and cylinder by a portable gasoline centrifugal pump. The volume of water filtered shall be measured inboard of the cylinder by a flowmeter.

Samples shall be collected monthly (weather permitting) at all stations. Additional samples shall be collected at 4-hour intervals over a 12-hour period once per month (weather permitting) on the three-station transect extending west from the plant site.

3,1-11

Replicate subsamples shall be counted in a counting.cell with a compound microscope. Results will be presented as numbers of organisms per cubic meter.

Most zooplankters shall be identified to species. Poorly preserved or immature speciments shall be identified to the lowest .taxonomic level which their condition permits.

Although all zooplankton organisms collected shall be identi*fied; the emphasis in reports shall be on. dominant species.

d. Zooplankton -.Macroplankton Macroplankton analyses shall be performed on samples taken under Specification 3.1. 2.1.1. b (Ichthyoplankton), and in accordance with Spe.cification 3 .1. 2 .1.1. c (Zooplankton - Microplankton).

e. Benthos Benthos collections shall be made monthly to bimonthly (weather permitting) within the study area illustrated in Figure 3.1-1.

Based on variability observed in preoperational samples, three replicates shall be taken at each station. Samples shall be collected with a Ponar grab sampler which samples an area 0.05 m2 to. a depth of approximately 15 cm. Most 3.1-12

benthic organisms shall be identified to species. For specimens damaged in sampling, identification shall be to the lowest possible taxonomic level. The organisms shall be counted, dried, and weighed.

f. Blue Crab Commercial crabbers shall be censused throughout the crabbing season (usually May through November) by means of daily questionnaires which ask data on the number of pots checked, number of bushels of hard crab, and number of individual moulting crab taken. The numbers of soft crab, mating crab, and egg-bearing female crab

observed in pot catches are also noted.

Additionally data on blue crab shall be collected monthly by interviewing and accompanying selected crabbers during their operations. Crab are also collected in the course of the fisheries sampling programs .

.g. Fish Fishes will be sampled by seine, trawl, and *I gill net within the area illustrated in Figure 3.1-1. Sites shall be sampled on a biweekly to quarterly schedule (weather permitting) throughout the year. Appropriate stations and zones shall be sampled during daylight and at night. Trawl hauls in the 3,1-13

river zones shall be of 10-)'llinute duration with a 16-~t semi-ballobn otter trawl and in the creeks they shall be *of 5-minute duration with a ~-f~ semi-balloon otter trawl. Trawl hauls shall be made at a uniform speed, traveling with the tide. Seine collectipns shall be made parallel to the shore line. Seines shall be used in combination and may include a 1/4-inch ~esh, 25-ft bag seine; a 1/4-inch mesh, 10-ft flat seine; a 1/8-inch mesh, 10-ft flat seine; and a 1/2.-inch mesh, 225-ft seine. Fishes shall be identified and enumerated by species, and repre~entative subsamples shall be measured for length.

Gill' nets shall he fished in the spring to sample populaticnl's.

of anadrornous fiShP.S, Gill net gangs of stretched mesh sizes 5 1/2 inches and 3 1/8 inches shall. be drifted after being set perpendicular to the current. Specimens*

shall be identified* to species, sexed~

measured,* and weighed.

2. Terrestrial Studies Studies of the Terrestrial Environment shall include:

1. Monitoring.of nesting by the diamondback terrapin on Sunken Ship Cove Beach and in regions outside the thermal plume.

3.1-14 I

1-. -.. - .. -., - ........ .

2. A monthly (weather permitting) bird survey in the area of Artificial Island.

2. Monitoring of occurrence and nesting of the osprey and southern bald eagle within a general 5-mile radius of the station.

Reporting Requirement Reporting levels shall be developed after one year of full power operation of Unit 2. Post-operational data will be related to preoperational norms from which report levels will be established.

Bases All biological parameters sampled will provide background data for determining the environmental effects of station operation. Results of the operational studies will be compared with preoperational studies by statistical metnods.

The various sampling locations were selected on the basis of their representa-*

tive cUstribution throughout th.e region. As the data from these sites are analyzed, it will be determined whether additional sites are needed or old sites can be eliminated. The frequency of sampling has been established in much the same manner.

3.1.2.2 Impingement of Organisms 1 Objective The principal objectives of the impingement study are to: (1) determine the species composition, and (2) quantify the numbers of fishes and other organisms which become impinged on the circulating and service water intake screens.

3.1-15

Specification Impinged organisms shall be sampled for three 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months periods per week.

The total weight of the 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months sample shall be determined. All fishes and other organisms shall be identified by species. If the sample is greater than 100 lbs, two random subsamples of 50 lbs each shall be taken from each sampling period. All specimens in the two subsamples shall be identified by species and each series weighed and used to compute total weight per species for each sample. All fish of a given species shall be used to compute modal length, maximum length, and modal weight. If greater than 100 fish are collected during a sample, a random subsample of

I at least 100 fish shall be used for the above listed measurements. Estimates of the total number of each species impinged per 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months sampling period shali. be computed. Number of circulation pumps in operation during sampling shal+ be recorded.

After one year of full power operation of Unit 1, the impingement data shall be analyzed. Suggested changes in sampling frequency shall be submitted for review and approval by the staff prior to implementation.

Reporting Requirement Monthly results from this study shall be submitted to the NRC within 20 days after the end of the month. Report of each sample period shall contain the following information: the date of sample, the species collected, the number impinged in 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months for each species, the modal length for each. species, the maximuni length for each species, the modal weight for each species, and the number of pumps operating during sample collection. A summary of the 3 *. 1-16

rr

. i i

'/

impingement study shall be included in the annual environmental report.

Bases This survey and subsequent data analyses will aid. in verification of the effectiveness of the intake design in minimizing impingement of organisms.

3.1.2.3 Entrainment of Plankton Organisms Objective The objective of the entrainment study is to determine the effects of operation of the Circulating Water System on planktonic organisms.

Specifications In order to obtain estimates of numbers of orga~isms passing through the circulating water system, a sampling program shall be implemented. The first ph~se of the program consists of sampling the plankton during the _initial start-up of the* Circulating Water System. Ambient temperature water shall be circulated through the various componehts of the system.

3.l.17

Since there will be no heat added to the water at this time, mortalities due solely to mechanical damage and pressure may be assessed. During the second phase, sampling shall be continued with varying heat load rejection to the Circulating Water System under different station operating conditions. This will provide an estimate of organism mortality related to the various operating modes of the Circulating Water System.

Intake samples shall be taken immediately before the intake structure; discharge samples shall be taken through sampling ports. During .the testing and start-up phases of plant operation, sampling shall be regulated by the station operating schedule. After tlJe plant begins comrnercial operation sampling shall be done monthly.

Samples from the same water mass shall be obtained from the intake and discharge by coo*rdinating their collection with circulating water passage time. Whenever possible entrainment sampling will be coordinated with the collection of river samples on the transect extending westward from the site.

3.1.18

Physicochemical parameters to be monitored at sampling will, -wheneve1: po.ssible, include water temperature, dissolved oxygen, salinity, and pH.

Phytoplankton Studies Replicate samples.shall be taken with a Van Dorn sampler. Surface, mid-depth, and bottom samples shall be collected monthly during a 24-hour period at 4-hour"intervals from in front of the intake trash racks. Discharge samples shall be collected through sampling ports.

Phytoplankton samples shall be analyzed quantitatively for chlorophyll ~ using the techniques presented in Specification 3.1.2.1.1.a.* Add~tionally systematic studies shall be done to determine dominani taxa.

Microzooplankton Studies Surface, near-bottom and integrated (near-bottom to surface) samples shall be collected monthly during a 24-hour period at 4-hour intervals. These samples shall be taken at. the intake with the filter-pump system described in Specification 3.1.~.l.l.c and at the discharge through sampling ports.

Samples will be immediately stained with neutral red to enable separation of live and dead zooplankton. A dead organism count and specimen identification to the lowest possible taxon shall be done in the laboratory. An additional discharge sample shall be c_ollected, stained with neutral red, and maintained 3.1-19

in.a water bath at ambient river temperature .. This sample shall be periodically monitored over a 12-hour period to determine latent mortality.

Ichthyoplankton .and Macrozooplankton Studies Ichthyoplankton shall be sampled at the intake and discharge biweekly during the appropriate season as determined by preoperational* studies. Samples shall be taken over 24-hour periods at 4-hour intervals.

Replicate samples shall be collected at the intake with a high capacity pump sampler if present experimental efforts prove its suitability for sampling. If this pump sampler does not prove acceptable, metered plankton nets will be fished at surf ace, mid-depth, and near bottom in fron of the intake structure.

Samples of discharge water shall be taken through sampling ports.

Specimens collected shall be identified to the lowest possible taxonomic level, and densities shall be calculated. Irrunediate mortality shall be determined for intake and discharge samples based on the following criteria:

Live: Swirruning vigorously, no apparent orientation problems, behavior normal.

Stunned: Swirruning erratically, struggling and swirruning on side,. some twitching but motile.

Dead: No vital life signs-, body or opercular move-ment, no response to gentle probing.

3.1-20

Specimens determined to be alive or stunned shall be held separately for 12 to 24-hour periods at ambient river temperature to determine latent mortality.

Reporting Requirement Report levels shall be ~eveloped from the data collected during the first year of operation.

Bases This study and subsequent data analyses will aid in determining whether passage through the Circulating Water System will have a deleterio~s effect on planktonic organisms.

3.1.2.4 References

1. Lorenzen, C.J. 196]. Determination of chlorophyll and phaeo-pigments spectrophotometric equations.

Limnol. and Oceanogr. 12 :343-346.

2. Strickland, J. D. H., and T. R. Parsons. 1968 .

. A manual of seawater aDalysis. Bull. 125, Fish. Res. Bd. Canada. 203 pp.

I 3. Strickland, J. D. H., and T. R. Parsons. 1968. A

practical handbook of seawater analysis. Bull. 167, Fish. Res. Bd. Canada. 311 p.

4~ American Public Health Association, et al. 1974.

standard Nethods for the Examination of Water and Waste Water. American Public Health Association.

874 pp.

3.l-21

5. Icanberry, J. W., and R. W. Richardson. 1973.

Quantitative sampling of live zooplankton with a filter-pump.system. Limnol. and Oceanogr.

18 (2) : 333-:335.

3. 1-22

TABLE 3.1-1 WATER QUALITY ANALYSIS PARAMETERS Parameter *PPM, as Parameter PPM, as Solids, Non-Filterable (Diss.) Nitrate (NO). . NO 3

Solids, Filterable (Susp.) Conductivity (µmhos)

Solids, Total Volatile Turbidity (JTU)

Calcium (Ca)* Caco Reducing Substances H S 3 2 Magnesium (Mg) Caco Chemical Oxygen Demand COD 3

Sodium (Na) Caco 3

Total Organic Carbon c Potassium (K) Caco

Chlorine Demand, 30 Sec. Cl 3

.w__, Iron, Tbtal (Fe) Fe Chlorine Residual, Free Cl I Copper, Total (Cu) Cu Chlorine Residual, Combined Cl N

w Manganese (Mn) Mn Chlorine Demand, 3 Min. Cl Zinc (Zn) Zn Biochemical Oxygen Demand BOD Chromium (Cr) Cr Phenol Ammonia (NH ) NH . Carbon Dioxide, Free .co 3 3 2 Kjeldahl Nitrogen N Sulfides s Chloride (Cl) Caco Dissolved O_xygen 02 3

Chloride (Cl) NaCl Phenophathalein Alkalinity Caco 3

Sulfate (so ) Caco Methyl Orange Alkalinity Caco 4 3 3 Sulfate (so ) so pH 4 4 Silica (Si0 ) Si0 Phosphate (Po )

2 2 4

TABLE 3.1-2 e

SUMMARY

OF AQUATIC, TERRESTRIAL AND AERIAL SAMPLING PROGRAM Areq. Sampled Relative Sample Method SamEling Freguenc~* to Station (Mile 0)

Aquatic *North South Phy top.lank ton Water bottles and other Biweekly to quarterly to 7 .5 miles; to 5.0 miles gear as appropriate Zooplankton Me.tered filter pump Monthly 7.5 5.0 system fitted to plankton net Benthos Ponar grab Monthly to bimonthly 4.5 5.0

'lue Crab Trawl haul, Biweekly to quarterly 8.~ 9.0

) commercial crabbers Fisheries Seines (Estuary) *Biweekly to monthly 6.5 4.0 Trawls (Estuary) Biweekly to monthly 8.5 9.0 Trawls (Creek) Biweekly to monthly 5.0 2.0 e

Gill nets (Estuary) Biweekly to quarterly 8.5 9.0 Seines (Creek)" Biweekly to quarterly 5.0 o.o lchthyoplnnkton Metered plankton net Biweekly to monthly 7.5 5.0 Terrestrial and Aeiial Birds Visual observations Biweekly to quarterly Within 3-5 mile radius of site Mammals Visual observations Biweekly to quarterly Within-3-5 mile radius of site

In the appropriate season.

3.1. -24

.e

. *TABLE* 3~ 1-3 ANTICIPATED CHEMICAL WASTE DISCHARGE (SALEM STATION)

AVE.NATURAL AVE.NET ?'JAX.NET AMOUNT AVE.NET AVERAGE AMOUNT MAX.NET MAXIMUM CHEMIC~ CONC.IN INCREASF. INCREASE WATER DISCHARGED INCREASE INCREASE DISCHARGED CONSTITUENT (%) (lbs/day) - (mg/l) ( %)

(mg/l) (lbs/day) (mg/l)

<O.l c1 ,residual,free 2 . 0 870 <O.l 870

-2 1.4xl0 -2 100 135 5.lxl0- 3 5.lxlo- 3 374 ;l..4xl0 Calcium as Ca S.Oxl0- 3 2.lxl0- 3

. Magnesium as Mg 240 56 2.lxl0- 3 8.Sxl0- 4 134

--3 w 600 -2. 2x10

-2 1.lxl0- 3 1338 5.0xl0- 2 2.5xl0

~ SodiulCI as Na 2000 I 55 2.0xl0- 3 2.9xl0- 3 142 5.3xl0- 3 7.6xl0 -3 l'-.J potassium as K 70 4xl0- 3

~

> 110 4.9 Copper as Cu 0.082

- - -2 -1' -2

. SxlO 0.01 "" 3218 1. 2xl0 2.lxlO Sulfate as so 4 570 1590

-4

-3' 1. 4xl0 .

-4 350 -i. 3xl0- 2 3.5xl0

_ Chloride as Cl 370,0 138 5.lxlO

-4 -2 9.0xlO -s 2xl.o"'." 3 25.6 9.6xl0 l.7xl0 Nitrate as N0 3 5.6 2 .*4

-3 -3

1. 7xl0 92 3.SxlO Silica as Si0 2 46

-4 -3 0. 2 '3 4.lxlO 0.06 40 l. 5xl0 Phosphate as P0 4 0.66 11

-3 -4 l.SxlO 9.3 3.4xl0 Volatile - Amines 4.2

-6 -6

- 1. SxlO 0.05 1. 9xl0 Hydrazine 0 0.04 Suspended Solids 170 <1000 <0.04

- - -*****~--*~

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

fisheries trawl zcnes.

Fisheries seine stations.

Sampling loc2tions:

B a benthos

. I = ichthyoplan~ton P

phytoplankton z n zooplankton Creek Mileage Designations (east of shipping consider Salem discharge location as Mile SCALI ,..........

0 MIUiS 1.0 I

PUBLIC SERVICE ELECTRIC M~D GAS COMPANY Biological Sampling Stations in the Vicinity of Artificial Island SALEM NUCLEAR GEHERATING STATION FIG. 3.1-1

3. l-25

3.2 RADIOLOGICAL SURVEILLANCE 9

Objective An environmental radiological monitoring program shall be conducted to assist in verifying that radioactive effluent releas.es 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 shown on Figure 3.2-1.

2. Reports shall be submitted in accordance with the requirements of Specification 5.6.

3. 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 radioiodine content (calculated as I-131). Analyses shall be performed within eight days of sampling. Suitable analytical procedures shall be used to determine the radioiodine concentration to a sensitivity of 0.5 picocuries per liter of milk at the time of sampling. For activity levels *at or above 0.5 picocuries per liter, the determinate error of the analysis shall be within+ 25%.* Results shall be reported, with associated calculated error, as picocurie~ of I-131 per liter of milk at the time of sampling.

3.2-1

4. A census of milk animals within a 1-mile radius from the plant site or within the 15 mrem/yr isodose line, whichever is larger, shall be conducted at*the beginning and at the middle of each grazing season by using a door to door or equivalent counting technique to determine their location and number with respect to the site. A census shall be conducted within a 5-mile radius for cows and a 15-mile radius for goats, with enumeration by using referenced information from county agricultural agents or other reliable sources.

If it is learned from this census that milk animals are present at a location which yields a calculated infant thyroid dose greater 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 assumptions presented in Regulatory Guide 1.42, Interim Licensing Policy on As Low As Practicable for Gaseous Radioiodine Releases from Light-Water-Cooled Nuclear Power Reactors, Revision 1, dated March 1974. Following the addition of any new location, a sampling location yielding a lower calculated dose may then be dropped. from the surveillance program at the end of the grazing season during which the census was conducted.

Any locations from which milk can no longer be obtained may be dropped

. from the surveillance program upon written notification to.the Commission that milk animals are no longer present at the location, sufficient quantity of milk cannot be. obtained or that there exists a lack of cooperation in obtaining samples.

e 3 .2..:..2

If the calculated dose to a child 1 S thyroid at any location where there is an animal producing miJ:k. for human consmnption exceeds 15 mrem/yr, milk sampling shall be done weekly with a I-131 analysis being p.erformed on each sample.

5. Deviations shall be permitted from the required sampling schedule if specimens are unobtainable due to hazardous conditions, seasona~

unavailability, 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 upon written notification to the NRC of the reasons for this action. Any location which is dropped shall be replaced by a suitable alternate location.

Reporting Requirement An annual report shall be submitted_ in accordance with the requirements of Specification 5.6.1.

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

Bases The magnitude and :fluctuation of radioactivity levels in the environment 3.2-3

J surrounding the plant have been determined during implementation of the preoperational environmental radiation monitoring program. This information serves as a solid baseline for evaluating any changes in environmental radioactivity levels during plant operation. The operational environmental radiation monitoring program was derived using the preoperation~l environmental radiation monitoring program as a basis.

The monitoring program utilizes a series of sampling locations which were determined by consideration of the spatial distribution of station effluents, including areas where concentrations of effluents in the environment are expected to be greatest, sitemeteorology, population

e. distribution and ease of access to the sampling stations. The selection of sampling media was based on an evaluation of potential critical pathways or. radiation exposure to man.

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

3.2-4

TABLE 3.2-1 OPERATiONAL ENVIRONMENTAL RADIOLOGICAL MONITORING PROGRAM EXPOSURE COLLECr ION METHOD TYPE & FREQUENCY PATHWAY STATION CODE LOCATION & FREQIJENCY OF ANALYSIS I. AIRBORNE 1001 3.9 mi SSW of vent composite Sr 89 composite Sr 90 performed quarterly (a) p 2Sl on site A

R T

I lFl 5.8 mi N of vent Continuous l~w volume air Gross beta analysis on each weekly c sampler. Sample callee ted sample done weekly u every week alot].g with filter L change A 2F2 8. 7 mi. NNE of vent Composition Gamma scan quarterly T

E s

.... 3H3 110 mi NE of station 16El 4.1 mi NNW of vent lODl 3.9 mi SE of vent (b) I 0

D I

N A silver zeolite flow-through Iodine 131 analyses are performed weekly E 1_6El 4.1 mi NNW of vent cartridge is connected to air 0

particulate air sampleL and is callee ted weekly ***

2F2 NJ;. 8.7 mi NNE of vent 2Sl on site

.... 3H3 110 mi NE of vent e II.

lODl 3.9 mi SSW of vent, 16El 4.1 mi NNW of vent

. 3Gl 16,6 miles NE of vent 10 soil plugs to a depth of

Gamma spectrometry performed an each 2

6 11 over an area of 25 ft are sample on collection

.... 3H3 110 mi NE of station composited and sealed in a plastic bag at each location* A sample will Sr-90 analyses on one sample from each lFl 5.8 mi N of vent be collected from each location location on collection 2F2. NJ, 8. 7 mi NNE of vent once every 3 yea:rs 5Dl 3.5 mi E of vent 2Fl 5 mi NNE of vent 2El 4.4 mi NNE of vent 2Sl** on site

Soil samples are taken in ac;cordance 'with procedures outlined in HASL-300 (Rev. 5/73)

'** if suitable sample exists

- - If silver zeolitc is uot available, charcoal cannisters will be used after NRC is notified.

Control Station 3.2-5

TABLE 3.2-1 (Cont,)

.' OPERATIONAL ENVIRONMENTAL .RADIOLOGICAL MONITORING PROGRAM COLLECTION METHOD TYPE & FREQUENCY EXPOSURE STATION CODE LOCATION FREQUENCY OF ANALYSIS .

PATHWAY III. DIRECT lODl 3.9 ,;,i SSW of verit 16El 4.1 mi NNW of vent 2F2 8.7 mi NNE of vent 13Fl Middletown, Del; 9.8 miles W of vent

!Fl 5.8 mi N of vent 2 dosimeters will be collected Gamma dose-quarterly from each loca~ion quarterly 3Gl 16.6 miles. NE of vent 32 mi NE of vent

-> 3Hl 2Hl 38.5 mi NNE of vent 6Sl

2 miles ESE of vent 7Sl Station personnel gate 14Dl 3.9 mi WNW of vent Cooling water At least one dosimeter collected lOSl from this location quarterly 150 ft SSW of e IV. WATER Approximately 650 ft SW. of vent (a) s u .. 12Cl 2-1/2 mi WSW of vent Two gallon sample to be collected Gamma scan monthly H-3, Sr-89 and R monthly providing winter icing Sr-90 analyses of quarterly composites F conditions .:illow sample collection A

c E 7El. l mi W of Mad Horse Creek; 4.5 mi SE of vent (b) G

.R 4Sl on site 0

u N .... 3El 4.5 mi NE of vent Two gallon grab sample is callee. ted Gamma sc.an - QC H-3 analyses are done*

D monthly monthly (c) D R

I 2F3 (raw) Salem Water Co.;

NNE of vent Bmi l- 50 ml aliquot is taken regularly and composited to a monthly sample Gross beta monthly Gamma scan - QC H-3 monthly Sr 89 and Sr 90 analyses J

N of two gallons on quarterly composites K

I 2F3 (treated) Salem Water Co * ;

N NNE of vent 8 mi G

.. Control Station 3.2-6

TABLE 3, 2-1 (Cont,)

OPERATIONAL ENVIRONMENTAL RADIOLOGICAL MONITORING PROGRAM e

.EXPOSURE COLLECTION METHOD TYPE & FREQUEN.CY PATHWAY STATION CODE LOCATION & FREQUENCY OF ANALYSES v.. AQUATIC B 7El 1 mi W of M.6.d Horse Creek; E 4. 5 mi SE of Vent N

T ... 12Cl 2-1/2 mi WSW of Vj!nt A benthos sample consisting Gafllna spectrometry of each sample H of benthic organisms and semi-ann1Ja 11 y; Sr-39 and Sr-90 0 associated sediment is taken semi-annually on organisms, s semiannually. Sr-90 semi-ann:Jd l ly 011 sedir::ent llAl Outfall area; 650' SW of vent VI. INGESTION 15Fl 5.2 mi NW of vent Four gallon grab sample of Gamma scan monthly; Sr-89 and Sr-90 fresh milk is collected monthly; I-131 monthly 1-131 weekly (a) M 5 mi NNE of vent from each farm monthly. if calculated dose exceeds 15 mrem I Collected weekly if calculated to child's thyroid L 5Fl 6.5 mi E of vent dose exceeds 15 mrem. to child 1 s K thyroid *.

14Fl 5.5 mi WNW of vent 3Gl 16. 6 miles NE of vent Outfall area; 650 1 SW of

}

(b) F llAl Two key samples of fish Gamma scan of edible I vent are sealed in plastic portion on collection 5 bag or jar and frozen H -> 12Cl 2-1/2 mi WSW of vent semi-annually or when in season (c) C llAl Outfall area; 650 1 SW of Two key samples of crab Gamma scan of edible R. vent are sealed in a plastic portion on collection A bag or jar and frozen B semi-annually or when in sea.son

+ 12Cl ~~t~*.liank oppo~~ta Artificial Islana,

2-1/2 mi WSW of vent (d) FJUJITS -> lGl 10.2 miles N of vent Samples are collected Radi!.oiodine determination during the normal har- of green leafy vegetables or 21;:1 4,45 Jljj. lfflE o{ yent vest seqson, sealed in on collection plastic, and frozen if VEGETATION 2Fl 3 mi NNE of vent perishable. Sufficient Gamma scan on collection sample is callee ted to 0th.tr loeattou NJ 'M -b.clt11ted 1f a rara yield 500 grams of dry

11~um:i.ae*eo sr- tha ....,1.. or cow:..ni.

weight and done annually J}

(e) G xxx Station vicinity east Musk.rats are skinned Gamma scan on edible A side of estuary and frozen semi-annually portion only o.n col-M lection E -> xxx West side of estuary, 3-5 mi from vent xxx Within 10 mi of Station Beef portion of cow is***

Sampled and frozen Semi-annually QC

Quarterly composite XXX

location given at time of collection

'***

This sample is subject to availability of slaughtered cow

+ Control Station 3.2-7

~.

TABLE 3.2-2 Exposure Pathway Analysis

Units Io Airborne A. Air Particulate Gross beta 75 91 l0-15µCi/ml Sr 89 Note 1 Sr 90 Note 1 yemitters Note 2 Be 7 54 21 - l0.-15µCi/ml Cs 137 2 .. 9 208 l0..,.;15lici/ml Ce 144 25.0 32.6 l0-15µCi/ml Zr 95 3.5 4ol l0-15µCi/ml Bo Air Iodine I-131 Note *3 e IL Soil Sr 90 5.2 3o3 10-1 µCi/ml yemitter _. Note 1 and Note 2 III. Direct Gamma Dose 4.4 *6 mrad/std mo

TLD's (Quarterly)

IV. Water A. Surface H-3 2.4 1.4 l0- 7µCi/ml Sr 89 Note 2 Sr 90 Note 2 (y E:llli t ter s) Note 2 K-40 5.4 4~1

-9 10 µCi-/ml e 3.2-8

TABLE 3.2-2 (Con' t)

- Exposure Pathway Bo Ground Analysis H-3 Q

xi Note 2 Units (Yemitters) Note 2 K-40 802 4o3 l0- 8µCi/ml

H-3 -7 Ce Drinking 108 .,9 ~O µCi/ml Sr 89 Note 1 (raw or treated Sr 90 1006 5o3 10-lOµCi/ml water) . *cross beta 2.,6 10-9µCi/ml 4o3 yemitters Note 2.

.v. Aquatic Benthos Sr 89 Note 1 Sr 90 Note 1 (yemitters) Note.* l VI. Ingestion

A., Milk I-131 Note 3*

Sr 89 Note 2 Sr 90 4o2 205 10-9 µCi/ml (yemitters) * . Note 2 Cs 137 Note 2 l0- 6µCi/ml B. Fish (yemitters) Note 1

c. Crabs (yemitters) Note 1 D. Fruits or (Yemitters) Note 1 Vegetables I-131 Note 3 E * .Game (yemitters) . Note 1

Table 3.2-2 (Con't)

Note 1: Insufficient data Note 2: Several means and deviations could not" be calculated because of abundancy of NDL valueso Note 3: Because most values were MDL means and deviations could not be determined~ however the following review points have been established:

I-131 in milk Review point = 2c4 pCi/l I-131 in leafy vegetables Review point = 110 pCi/l I-131 in air Review point = ~5 pCi/m3 3.2-9a

TABLE 3.2-3 SENSITIVITY LEVELS FOR ENVIRONMENTAL.SAMPLE ANALYSES SA.MPLE TYPE TYPE OF ANALYSIS SENSITIVITY

Air Particulates Gross beta 5 x 10-15 µCi/ml

-14 II II Gamma scan 1 x 10

-15 II II Sr 89 5 x 10

-15 II II Sr 90 1 x 10

-14 II Air Iodine I 131 4 x 10 II Soil .Gamma scan 1 x 10-7 µCi/g-dry 8

Sr 90 5 x 10- "

Thermoluminescent Gamma approx. 5mrem/yr Dosimeters 9

Surface water Gamma scan 1 x 10- µCi/ml 7

Tritium 2 x 10- II II 9

Sr 89 5 x 10- II II 9

Sr 90 1 x 10- II II 9

Ground water Gamma scan 1 x 10- II II 2 x 10-7 II II Tritium 9

1 x 10-II Drinking water Gross beta II 9

Gamma scan 1 x 10- II II 7

Tritium 2 x 10- II II

- 5 x 10-9 Sr 89 II 9

Sr 90 1 x 10- II 7

Benthos Gamma scan 1 x 10- µCi/g-dry 7

Sr 89 5 x 10- " "

7 Sr 90 1 x 10- " II Fish Gamma scan *3 x 10-8 µCi/g-wet 3.2-10 e

TABLE 3.2-3 (Cont'd)

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

8 Milk Gamma scan 1 x 10- µCi/ml 9

Sr 89 5 x 10- " II Sr 90 1 x 10-9 " II I 131 5 x 10

-10 11 8

Fruits and Vegetables Gamma scan 5 x 10- µCi/g-wet 8

I 131 5 x 10- " II Meat Gamma scan 8 x 10- 8 " II Game Gamma scan 8 x 10-S " II

The sensitivity of the gamma scan analysis are for Cs 134 and Cs 137 3.2-11

PUBLIC SERVICE ELECTRIC AHO GAS COMPAHY LOCATIONS OF RADIOLOGICAL SAMPLING STATIONS WITHIN A 10 MILE RADIUS OF THE SITE SALEM NUCLEAR GENERATING STATIO" FIG. J.2-1 3.2-12

4.0 SPECIAL SURVEILLANCE AND STUDY- ACTIVITIES 4.1 EXPERIMENTAL ENTRAINHENT STUDIES Objective

To estimate the effect of rapid temperature and pressure changes in the Circulating Water System on ichthyoplan_kton and zooplankton.

Specification Responses to short duration increases in temperature and pressure which closely approximate those in the c*irculating Water Systems will.

be determined for the more common entrainable organisms in the vicinity of Artificial Island.

The following species of fishes and crustaceans will be tested e* * (contingent upon their availability): white* perch, Moron'e americana; st.riped bass, Morone saxatilis; alewife, Alos*a pseudoharengus; blueback herring, Alosa aestivalis; scud, Gammarus sp.; opossum shripm, Neomysis americana; sand shrimp, Crangon septemspinosa; and grass shrimp, Palaemonetes pugio. Other qpecies will be tested as they are available and as scheduling pe~mits. ,Size range of test organism£ will be between 2 and 50 mm (0. 07 and 1. 96 inches) total length.

Organisms will be considered acclimated to prevailing conditions at their point of capture and will be held under similar conditions for periods up to about one week prior to testiiig. Larval fishes will be hatched in the la.boratory under conditions similar to those in the spawning areas.

Tests will be conducted in a rigid transparent PVC apparatus in which the effects of temperature.and pressure can be evaluated independently

e and concurrently. Temperature will be measured with a standardized mer~ury thermometer (pre~ision, 0.5 C) within the test chamber and pre~sure with a Robertshaw test gauge (precision, 1/2 mm Hg) connected to the atm?sphere in .the test chamber.

Other variables monitored will include salinity, pH, and oxygen content. Salinity of the water will be measured with a salinometer (precision, 0.1 ppt) ~rior to testing. Determi~ation o{ pH will b~*

made with a pH meter (precision, 0.1 pH unit) before testing. Oxygen content of the water will be verified with an oxygen meter (precision, 0.1 mg 02/l) prior to testing.

Water used in testing will be taken from Appoquini~ink Creek at high tide. This approximates the water quality of the Delaware River in the vicinity of Artificial Island at high tide.

Test organisms will be exposed to various combinations of test coridi-e tions. Acclimation temperature will vary seasonally within the range s0 to 30° C (41-86°F). Test salinities will be appropriate levels within the range 0 to 12 ppt, pH between 7.0 and 8.0, and oxygen content near air saturation. Temperature incr~ases for test organisms will be from 7.5° to 1S 0 c (13.5-27°F) above ambient (acclimation). Test organisms will be exposed to pressures from 69 to 180 mm Hg absolute

(-1.4-20.1 psig) in a sequence simulating passage through the condenser cooling system.

A general contr61 group will be placed in a holding container. A handling control will receive ~tandard handling in the apparatus, but will not be exp~sed to changes in ~ither temperature or pressure.

Test organisms will be exposed to *one of three experimental conditions:

pressure ch~nges ?nly, temperature changes*only, or both temperature and pressure changes concurrently *. Observations will be made on the test organisms during and immediately .after testing and at appropriate 4.1-2

intervals through a 96-hour .. period* to d*etermine immediate and long-term effects.

The~e studies will be conducted for a period of 1 year after Unit 1 becomes operational.

Reporting Requirements Results of these studies shall be reported in accordance with Specification 5.6.1.

Bases These studies and subsequent data analyses will aid in determining whether the temperature and pressure conditions in the Circulating Water System will have a deleterious effect on entrainable organisms.

4 .1-3 .

4.2 THERNAL AND CHEMICAL RESPONSES .OF ESTUARINE ORGANISMS Objective The principal objectives of these studies are to determine:

(1) temperature preference, (2) temperature and chemical avoidan~e, and (3) cold _shock temperatures for th.e various common fishes and macroinvertebrates in this region of the Delaware River estuary.

Specification.

4.2.1 GENERAL All studies will be conducted throughout the year tinder near air-saturated levels of dissolved oxygen at appropriate salinities within a range of O.O to 12.0 ppt and acclimation temperatures within a range of 5° to 30°c (41-86°F). Levels of temperature, .salinity, dissolved 9.* oxygen, light, and pH, as well as size of.test specimens will be measured and recorded for all tests in al1 studies. Water. for all studies will be taken from* Appoquinimink Creek, a tributary of the Delaware River, at high tide. This source approximates the water quality of the Delaware River in the vicinity of Artificial Island at high tide.

Species to be .tested in all studies will include the bay anchovy~

Ancho*a mitchilli; the Atlantic silverside, Nenidia menidia; the white perch, Marone americana; and the grass shrimp, Palaemonetes pugio.

Other fishes and macroinvertebrates will. also be tested depending upon .

availability. Specimens_ to be tested will be acclimated to the approximate temperatures and salinity at which they were captured for a period of 24 to 96 hours0.00111 days 0.0267 hours 1.587302e-4 weeks 3.6528e-5 months prior to testing.

These studies will be ~onducted. for a period of one year after Unit l.beGomes operational.

e

4. 2-1

4.2.2 TEMPERATURE PREFERENCE STUDIES Temperature preferences will be determined in a horizontal temperature gradient in a trough approximately 13 ft long, 6 inches wide, and 1 ft.

deep, having a stainless steel bottom in the central 12 ft. The trough will be partially enclosed with polyethylene sheeting for light control.

Tests will be generally conducted at a lightning of either 4 or 40 foot-candles at the *surface of the water~ Light level will be measured**

with a foot-candle meter whose precision is 2 foot-candles.

Initially the trough will be filled with water of the acclimation salinity and temperatiire of the test specimens to a depth which will permit horizontal but restrict.vertical movement. Specimens will then be randomly placed in the trough a"nd allowed to remain for several hours prior to the establishment of a thermal gradient. The horizontal thermal gradient may extend to l0°c above and below the acclimation temperature. Observations wil.l be made at 5 or 10-minute intervals, e depending on specimen activity. The tempe'rature at the position of each specimen will be recorded using thermistors (placed at 6-inch intervals along

___________ **--The-preci-s.ic:n1-*ar-tlie-readot_{t i;-0*:5o;~-----The test win be concluded the trough) which are CO!].p~cted---to- a-te.m-pera~e readout.

when the specimens select the same- temperature for four successive obersavation times *.

4.2.3 TEMPERATURE AND CHEMICAL AVOIDANCE STUDIES The avoidance design to be employed in these studies is a modification of the clesign employed first by Shelford and Allee (l). In this modified design a control and a replicate are determined simultaneously.

The apparatus is constructed such that, in thermal tests, water of differing temperatures flows into the opposing ~nds of a divided trough and then drains at the center. In chemical tests, various concentrations of the compound are sub~tituted for the temperature increase. *nue to

. 4. 2-2

the sharp gradient at the center drain the apparatus is effectively divided into quadrants. The water temperature. (or chemical composition) is the-same in diagonally opposed quadrants, but different in those directly opposed. One set of diagonally opposed quadrants is designated as experimental, the other s~t as control. Temperatures in the directly opposed quadrants are increased in step .gradients, with the exp'erimental quadrants being *3o to 5° F higher than the control quadrants. In the chemical tests, only the chemical concentration in the experimental quadrants is increased. Equal numbers of specimens are placed in each quadrant. The length of time spent by each specimen in each respective quadrant is continuously measured over a 5 to 15-minute test period.*

This results in a frequency distribut~on which is then analyzed statistically

.to determine the significance of the response to the chemical concentration or temperature increase. Tests begin at ambient temperature and continue through the step gradient until a significant'~voidance response is given in both subtroughs. Responses to chlorine (both free and combined states) will be determined. Responses to other chemical compounds will be determined as needed or recommended.

Oxygen and pH will be monitored throughout I .

all tests. The precision of the oxygen measurements is 0.1 mg/l; that of pH is 0.1 pH unit.

Free and combined chlorine residuals will be determined by amperometric titration or an equivalent methods. The precision of these measurements

is O. 01 ppm and the limit of detectability is O. 02 ppm chlorine. The thermal conditions in temperature tests will be monitored by a multi-channel temperature recorder connected to thermocouples at 6-inch intervals.** The precision of the temperature measurements is O. 5°F. If more suitable instrumentation becomes available, it may pe employed.

The trough is *enclosed for light level regulation as well as to permit movement around the trough area. Due to the increase in specimen activity which accompanies temperature increases, observations for temperature tests will be made via closed-circuit television.

4. 2-3 .

4.2.4 COLD SHOCK STUDIES Responses .to sudden.decreases in temperature will be determined over test periods of 96 hours0.00111 days 0.0267 hours 1.587302e-4 weeks 3.6528e-5 months . Test organisms will be exposed to instantaneous change from ambient temperatures to levels which permit estimation of the median lethal temperature decrease. Mortality will be defined as a total cessation of gill movement and when prodding with a glass rod elicits no response.*

Reporting Requirements Results of these experimental programs will be reported in accordance*

with Specification 5.6.1.

Bases The results of these stud_~es __ will aid *in estimating the effects of

e -- the. thermal

prliffi;-;:;h; motile organisms in the recieving waters.

References

1. Shelford, V. E., and W. C. Allee. 1913. The Reactions of fishes to Gradients ot Dissolved Atmospheric Gases. Jour. Exptl.

Zool. 14: 207-266.

4.2 4.3 THERMAL PLUNE MAPPING Objective To insure a minimal envirorimental impact to aquatic life due to the thermal discharge resulting from station operation.

Specification A field survey will be performed throughout ~ complete tidal cycle to determine the characteristics of the thermal plume. This survey will be performed within the first year foilowing the simultaneous full power operation of Units 1 and 2.

Reporting Requirement The thermal plume survey results will be reported in accordance with Specificaiion 5.6.1.

Bases Extensive model work has been performed by Pritchard-Carpenter, Con-sultants (see Dispersion and Cooling of Waste Heat Released into the Delaware River Estuary, a study performed for Salem Nuclear Generating Station utilizing the U. S. Army Corps of Enginee_rs' model at Vicks-burg, Mississippi, Salem*FSAR, Appendix A.4), to determine the best discharge locati6n and configuration for minimum thermel impact and recirculation. Attempts have*been made by PSE&G to continually monitor river temperature. The current in the river, river traffic and theft of buoys.has.necessitated a review of the need for continual thermal monitoring. It is the opinion of Pritchard-Carpe.nter, Consultants, that continuous thermal monitoring is of no value. Pilfered and damaged equipment, together with. system malfunctions, makes continuous monitoring impractical. It is believed that a single set of accurate data is ample for model verification.

4.1-1

4.4 Intake Velocity Study e Objective To measure the intake velocity in the vicinity of the traveling screens for both the cooling and service water intakes.

'/,..

E_pecification A one time study shall be performed to measure the intake velocity in the vicinity of the traveling screens for both the cooling and service water intakes. Measurements shall be taken at 10 points in front of each screen during both high and low tidal conditions. All pumps shall be operating normally during the period of measurement.

This study shall be performed within the first year following the simultaneous full power operation of Units 1 and 2.

~ Reporting Requirement The intake velocity study results shall be reported in accordance with Specification 5.6.1.

Bases The results of this study will aid in estimating the. effects of intake velocity on entrainment and impingement levels reported.

4.4-1

. *-~ ..... -..-.--- ... I - ...

5.0 ADMINISTRATIVE CONTROLS '

5.1 RESPONSIBILITY 5.1.1 The implementation of the surveillance programs,

_including sampling, samp.le analysis, evaluation of results and the preparation of required reports is the responsibility of the Nuclear Licensing and Environmental Studies Group in the Mechanical Division of the Engineering Department. This group is responsible for the assignment of personnel to the above functions, for assurance that appropriate written procedures, as described in Section S.S.l, are utilized in the surveill~nce program activities and for assuring the quality of surveillance program results, as described in Section S.5.3.

5.1. 2 The Station Superintendent or his delegated alternate is responsible for operating the plant in compliance with the.limiting conditions for operation as specified in.the Evnironmental Technical Specifications. His responsib~lity includes assurance that plant activities 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 S.S.

5.1-1. .

5.2 ORGANIZATION 5.2.1 Figure 5.2-1 identifies the corporate relationship between the Nuclear Licensing & Environmental Studies Group and the Station Superintendent. Figure 5.2-2 identifies the organization of the Mechanical '.

_Division of the Engineering Department and Figure 5.2~3 identifies the Production Department Station Organization.

5.2.2 The Nuclear Review Board (NRB) and Station Operations Review Committee (SORC) are shown in Figure 5.2-1.

They are advisory groups to the Vice President -

Production and Station Superintendent, respectively.

These groups perform the independent review and audit

activities for these Environmental Techanical Specifications. The SORC is composed of Station supervisory personnel and the NRB is composed of management and technical supp_ort personnel from the general office staff. The Station Superintendent is a *member of the NRB. There is. no direct relationship between.the two groups except that the NRB is charged with the r'esponsibility to review SORC activities.

Detailed descriptions of these organizations are presented in the Salem FSAR, Chapter 12, "Conduct of Operations".

5.2-1

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5.3 REVIEW AND AUDIT 5.3.1 NUCLEAR REVIEW BOARD (NRB)

The NRB shall have the following responsibilities corwerning the environmental impact of the plant:

1. The NRB shall review:

a. Proposed Environmental Technical Specification changes or license amendments.

b. Violations of Environmental Technical Specifica-tions.

c. Environmental Monitoring Program and Evaluations.

d. Routine and non-routine reports required by the Env~ronmental Technical Specifications.

2. The NRB shall, at least once ez,ch year, conduct (or cause to have-conducted) and evaluate audits of:

a. Plant *operation 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 CONHITTEE (SORC)

~he SORC shall have the following responsibilities concerning the environmental impact of the plant:

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

b. Review proposed changes to the Environmental Technical Specificatiorts.

5.3-1

c. Review environmental monitoring program results and evaluations.

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

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

5. 3-2 I

5.4 ACTION TO BE TAKEN IF A LIMITING CONDITION FOR OPERATION IS EXCEEDED 5.4.1 Remedial action as permitted by the Envirorunental Technj.cal Specification shall be taken until the condition can be met.

5.4.2 Exceeding a limiting condition for operation shall be investigated by the Station Operatior. Review Committee.

5.4.3 A report for each occurrence shall be prep~red and submitted as specified in Section 5.6.2.

5.4-1

. **:w;

5.5 PROCEDURES ..

5.5.1 Detailed written procedures, including applicable check lists and instru~tions, shall be prepared and followed for all activities involved in carrying out the Environmental Technical Specifications.

Procedures for the environmental surveillance and special s_tudy programs de_scribed in Sections 3 and 4 shall be r:epared by personnel responsible for the particular monitoring program. Procedures shall incluJ2 ~~npling, data recording and storage, instrument calibration, measurement"s and analyses, and actions to be taken when limits are ~pproached or exceeded. Testing frequen~y of any alarms shall be included. These frequencies shall be determined

from experience with similar instruments in similar environments and from manufacturers' technical manuals.

5.5.2 In addition* to the procedures specified in S~ction 5.5.1, the plant operating procedures shall include provisions to ensure the plant and all its systems an.... components are operated in compli.,3.nce with the limiting conditions for operation established as part of the Environmental Technical Specifications.

5.5.3 Procedures will be established to assure quality results. Procedures will.include:

a. Audits to assure organizations performing program activities are following policy directives and are using the appropriate written instructions.

5.5-1

~. A corrective action.plan that identifies, _-... __

controls and corrects deficiencies .

. c. A plan to investigate anomalous or suspect results.

5.5-2

PLANT REPORTING REQUIREHENTS 5.6.1 ROUTINE REPORTS Annual Environmental Operating Report l.*o .Nonr~diologi~al Report A report on the environmental surveillance programs for the previous 12 months of operation shall be submitted to the Director of the Regional Inspection and Enforcement Office (with *c-0py to the Director of Licensing) 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 in*itial criticality.

The report shall include summaries, interpretations, and statistical evaluation 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 2c0) for the report period~ including a comparison with

e. preoperational studies, operational controls (as appro-priate), 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 analys~s of the problem and a proposed course of action to alleviate the problemo

b. Reports to Other Agencies Copies of rou~ine reports required by Federal, State, local, and regional authorities for the protection of the environment shall be submitted to the Director, Division of Reactor Licensing, USNRC, for information.

5.6-1

/

2.. Radiological Report

a. A report on the radiological environmental surveillance 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 of Reactor Licensing) 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 summaries, interpretations, and statis-tical evaluation of the results of the radiological environmental surveillance activities for the report period, including a compar-ison with preoperational studies, operational controls (as appro-priate), 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.

b. Results of all radiological environmental samples taken shall be summarized on an annual basis following the format 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 missing data shall be sub~

mitted as soon as possible in a supplementary report.

5.6-2

5.6.1.2 Radioactive Effluents Relt;2.se 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 of Licensing) within 60 days after January 1 and July 1 of each year.

The report shall include a summary of the quantities

of radioactive liquid and gaseous effluents and solid waste released from the plant as outlined in Ref er-ence 1, with data summarized on a quarterly basis following the format of Appendix B thereof.

2. The report shall include a summary of the meteo-rological conditions concurrent with the release of gaseous effluents during each quarter as outlined in Reference 1, with data summarized on a quarterly basis following the format of Appendix B thereof. Calculated offsite dose to humans resulting from the release of effluents and their subsequent dispersion in the atmosphere shall be reported as recommended in Reference 1.

5.6.2 NONROUTINE REPORTS 5.6.2.1 Nonroutine Environmental Operating Reports A report shall be submitted iri 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 Section 3.0, "Environmental Surveillance")

5.6-3

or(c) an unusual or important event occurs that causes a significant environmental impactr that.affects potential environmental imoact from plant operation, or that has high public or potential public interest concerning environ-

mental impact from plant operation. \*

1 I

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

lo Prompt Report.* Those events requiring prompt reports within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months by telephone, telegraph, or facsimile transmission to the Director of the Regional Inspection and Enforcement Off ice 0vith copy to the Director of Licensing).

2. 30-Day Report.* Those events not requiring prompt rep~rt shall be reported within ~O days by a written report to the Director of the Regional Inspection and Enforcement Off ice (with copy to the Director of Licensing).

Copies of non-routine reports required by Federal, State, local, and regional authorities for the protection of the environment shall be reported to the Director, Division of Reactor Licensing, USNRC, for information.

Written 10-day and 30-day reports and, to the extent possible, the preliminary telephone, telegraph, or facsimile reports shall (a) describe, analyze, and evaluate the occurrence, includi..~g 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 pr_cclude repetition of the occurrence and to prevent similar occurre_nces involving sir.rilar components or systems.

Note: The significance of an unusual or apparently important event with regard to environmental*i~pact may not be obvious or fully appreciated at the time of occurrence. In such cases, the NRC shall be informed 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:..4

5.6.2.2 Nonroutine Radiological Environmental Operating Report i.* Anomalous Measurement Report If a confirmed measured level of radioactivity in any environmental medium exceeds 10 times the control station value, a written report shall be submitted to the.Director of the Regional Inspection and Enforcement Office (with copy to the Director of Licensing) within 10 days after confirmation. This report shall include an evaluation of any release conditions, environme~tal 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 3.8 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 member of the general public.

3. Fresh Leafy Vegetable and Inhalation Pathway* Measurements**

a. If .green leafy vegetable samples collected over a calendar quarter

. show 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.

-~~~~~~~-

- Milk pathway measure~ents apply when this pathway is *controlling with respect to atmospheric radioiodine releases. If the milk pathway is not controlling then the reporting requirements far the fresh leafy vegetable and inhalation pathway are in effect.

5. 6-5

b. If air san1ples collected over a calendar quarter show average concentrations of I-131 of 2 picocuries per cubic meter 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 desi*gn 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 materials in liquid effluents, excluding tritium and dissolved gases, should exceed one-half the design objective annual quantity during any calendar quarter, the licensee shall make an investigation to identify the causes of such releases and define and initiate a program of action to reduce such releases to the design objective levels. A written report of these actions shall be submitted to the NRG 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 investi-gation to identify the causes of the release rates and define and initiate a program of action to reduce the release rates to design_ objective 5.6-6

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

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

b. If the average release rate per site of all radioiodines and radioactive materials in particulate form with half-lives greater than eight days during any calendar quarter exceeds one-half the design objective annual 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 materials in excess of 0.5 curie in liquid or in excess of 5 curies of noble gases or 0.02 curie of radioiodines in gaseous form requires notification. This notification must be made by a written report within 30 days to the NRC. The report shall describe the event, identify the causes of the unplanned or uncontrolled release and report actions taken to prevent recurrence.

5.6.3 Changes in Ertvirorunental Technical Specifications 5.6.3.1 A report shall be made to the Connnission prior to implementation of a change in plant design, in plant operation, or in procedures described in Section 5.5 if the change would have a significant effect on the environment or 5.6-7

involves an environmental matter or question not previously reviewed and evaluated by the Commission. The report shall include a description and evaluation of the changes and a supporting benefit-cost .analysis.

5.6.3.2 Request for changes in environmental technical specifications shall be submitted to the Director, Division of Reactor Licensing, 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 additions to permits and certificates required by Federal, State, local, and regional authorities for the protection of the environment will be reported. When the required changes are submitted* to the concerned agency for approval, they will also be submitted to the Director, Division of Reactor Licensing, USNRC, for information. The submittal will include an evaluation of the environmental impact of the c_hange.

References

1. Regulatory Guide 1.21, Mea$uring, Evaluating and Reporting Radioactivity in Solid Wastes and Releases of* Radioactive Materials in Liquid and Gaseous Effluents from Light-Water-Cooled Nuclear Power Plants, Revision 1, June 1974.

5.6-8 e

~

J' TABLE 5.6-1 ENVIRONMENTAL P.ADIOLOGICAL MONITORING PROGRAi."1

SUMMARY

Name of Facility - - - - - - - - - - - Docket No.

Location of Facility Reporting Period - - - - - ' -

(County, State)

.. Analysis and Lower Limit Number of Helium or Pathway Total Number of All Indicator Locations Location with Highest Annual Mean Control Locations Nonroutine Sampled of Analyses Detection a/ Mean b/ Name Mean b/ Mean b/ Reported (Unit of Measurement} Performed (LLD) - Range-.!!_/ Distance and Direction Range-.!!_/ Range-.!!_/ Measurements £./

Air Particulates (pCi/m3) B 416 0.003. 0.08 (200/312) Middletown 0.10 (5/52) 0.08 (8/104) 1 (0.05-2.0) 5 miles 340°* (0.08 - 2.0) (0.05-1.40) y 32 137Cs 0.003 o.os (4/24) Smithville 0.08 (2/4) <LLD 4 (0.03-0.13) 2.5 miles 160° (0.03 - 0.13) 0.003 0.03 (2/24) Podunk 0.05 (2/4) 0.02 (1/8) l (0.01-0.08). 4.0 miles 270° (0.01 - 0.08) 40 0.002 <LLD <LLD 0 40 0.0003. <LLD <LLD 0

.Fish pCi/kg (dry veight) 80 <LLD <LLD 90 (1/4) 0

<LLD <LLD <LLD 0 80 120 (3/4) River Mile 35 See Column 4 <LLD 0 (90-200) Podunk River a/ Nominal Lower Limit of Detection (LLD) as defined in HASL-300 (Rev. 8/73), pp. D-08-01, 02, 03.

~/ Mean and range based upon detectable measurements only. Fraction of detectable measurements at specified locations is indicated in parentheses.

c/ Nonroutine reported measurements are defined in Section S.6.2b.

! Note: Tl1c e~nmp l c en

-, It a arc prov iled 1 for illustrative purposes only.

J

5.7 RECORDS RETENTION

-- 5.7.1 Rec~rds and logs relative to the following areas shall*

he made and retained for the life of the plant:

a. Records and drawings de.tailing plant qesign

. changes and modifications made to system and equipment as described in Section 5.6.3.

b. Records of all data from.environmental monitoring, SUFVeillance, and special surveillance and study

- activities required by these environmental technical specifications.

5.7.2 All other records and logs relating to the environ-

~ental technical specifications shall be retained for five years following logg.ing or record:(.ng.

5. 7-1

...

ML19031A149

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