Text

Appendix B to Provisional Operating License No. DPR-17 Draft of Proposed Environmental Technical Specifications
	ML18018B059
Person / Time
Site:	Nine Mile Point
Issue date:	10/05/1973
From:	; Niagara Mohawk Power Corp
To:	; US Atomic Energy Commission (AEC)
References
	Download: ML18018B059 (132)
	v • d • e

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(y jj $enfjp PROVISIONAL OPERATING LICENSE NO.

DPR-TI7/

FOR Nine i)ile Point Unit 1

NIAGARA MOHAWK P01IER CORPORATION DOCKFT NO.

SO-220 R.."RN TO REGULATORY. CEMT"" '

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DRAFT OF PROPOSED ENVIRONh1ENTAL TECHNICAL SPECIFICATIONS OCTOBER 5,

1973 74SB

t

CONTENTS

1. 0 Definitions 2.0 Protection Limits 2.1 Thermal 2.1.1 Haximum aT across the condenser 2.2 Chemical 2.2.1 Biocides 2.2.2 Corrosion Inhibitors 2.2.3 Suspended and Dissolved Solids 2.2.4 pH

2. 3 Radioactive Discharge 3.0 Design Features and Operating Practices 3.1 Intake System 3.2 Discharge System 3.3 Cnemical Usage 3.4 Land Hanagement 4.0 Environmental Surveillance and Special Study Programs 4.1 Biol ogi cal 4;1.1 Aquatic 4.1.2 Hater Chemistry Survey 4.1.3

~ Lake Temperature Structure 4.2 Physical

'I 4.2.1 Aquatic 4.3 Environmental Radiological Honitoring

~Pa e

1

~ 2 3

6 8

25 26 27 31 31 31 41 43 44 45

l J

CONTENTS (Cont'd) 5.0 Administrative Controls 5.1 Organi zati on and Res pons ibi1 ity 5.2 Review and Audit

5. 3 Action to be Taken if a Protecti on Limit or Report Level is Exceeded 5.4 Operating Procedures 5.5 Station Report Requirements 5.5.1 Semi-annual Reports 5.5.2 Non-Routine Reports 5.6 Records Retention 6.0 References

~Pa e

49 49 49 49 56 56 56 59 60 61

l

LIST OF TABLES 2.2 2.3-1 2.3-2 4.1.1-1 4.3 Chemical Liquid 'llaste Analysis Radioactive Liquid Haste Sampling and Analysis Radioactive Gaseous Waste Sampling and Analysis Frequency of Sampling for Ecological Studies in the Nine f/ile Point Area of Lake Ontario Sample Collection and Analysis - Site Radiological Environmental Monitoring Program Pacae 5

14 16 33 46

5. 5-1 5.2.2 Reporting of Radioactivity in the Environs Responsibilities and Authority for Environmental Review Organization 53

)

LIST OF FIGURES 4.1.1 5.1.1-1 5.1.1-2 5.2.1 Sampling locations - Nine Mile Point - 1973 Nuclear Site Operation Organization

~Pa e

34 50 Safety Organization-Hine Mile Point - James A. FitzPatrick Site 52 Nine Mile Point Nuclear Station Management Organization Chart 51

,I

1.0 DEFINITIONS Normal Station 0 eration - is with the reactor critical and above one percent rated power and in conformance with the requirements of the Techni cal Speci ficati ons.

Prior to Dilution liquid effluent concentrations prior to dilution are concentrations in the discharge tunnel, prior to dilution in Lake Ontario.

For other definitions, see Appendix A, Section 1.0.

2.0 LIMITING CONDITIONS FOR OPERATION Protection Limit 2.1 Thermal 2.1.1 Maximum aT Across the Main Condenser Honitori na Re ui rements 2.1 Thermal

2. 1.1 Maximum aT Across the Main Condenser OBJECTIVE OBJECTIVE The purpose of this Rrotection Limit is to limit.

the maximum aT across the.-ain condenser.

The nurpose of this jtonitoring Requirement is to provide sufficient information to assure that the maximum hT across the main condenser will not exceed the Protection Limit.

SPECI FI CATION SPECI FI CATION Maximum hT -across the main condenser during normal station operation shall be limited to 32 F. If, during normal station operation the main condenser AT exceeds 32 F for a period of ei ght hours in any given 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months period the. cause of this deviation shall be investigated and positive action shall be taken to reduce the bT to the specified maximum.

Positive action also shall be taken to orevent any such deviations in the future.

In addition, a report shall be submitted in accordance with Section 5.0.

The main condenser hT shall be monitored and recorded once per hour.

BASES BASES Nine Mile Point Unit 1 holds a permit from the Hew York State Department of Health to discharge cooling water to Lake Ontario when operating with a maximum 4T across the main condenser of 32 Fl.

Lake studies and operating experience indicate that mortality of plankton, eggs, and larvae entrained in the condenser will not have a si gni ficonf, effect on the populations of the species involved.

~~

The temperatures at the main condenser inlet and in the screenwell bay (upstream from the discharge tunnel ) are to be measured.

The sensors shall be accurate to 0.5 F.

The difference of these tempera-

tures, sT1, will be computed.

A AT1 of 31.2 F

corresponds to the gT Protection Limit of 32 F, because the water in the screenwell bay is a mixture of main condenser cooling water and service water.

The service water-flow is 40 cubic feet per second (cfs) with a maximum temperature rise of 20 F.

Mhen the main condenser flow of 557 cfs with a maximum temperature rise of. 32 F is mixed with the service water flow, the maximum temperature rise 'of the combined flow is 31.2 F.

A

2.Q 2;2 ING CONDITIONS FOR OPERATION Protection Limit Honi tori.n Re uirement Chemi cal 2.2.1 Biocides Chemi cal 2.2.1 Bioci des OBJECTIVE The purpose of this Specification is to protect the classifications and standards governing the quality and purity of Lake Ontario waters (Class A).

No moni to ring is required because no b ioci des shall be used in the main condenser cooling water system.

SPECI F! CATION No biocides shall be used in the main condenser cooling water system.

BASES The Specification will ensure that the lake water quality is not jeopardized by the introduction of bi oci des from the main condenser cool ing wate r sys tern.

2.0 IHITING CONDITIONS FOR OPERATION P rotecti on Limit t~oni torin Requirement 2.2.2 Corrosion Inhibitors 2.2.2 Corrosion Inhibitors

~ OBJECTI VE The purpose of this Protection Limit is to protect the cl ass ificati ons and s tandards governing the quality and purity of Lake Ontario waters (Class A).

OBJECTI VE The purpose of this Monitoring Requirement is to verify that the Protection Limit is mei.

SPECIFICATION The Station shall not discharge corrosion inhibitors to the lake.

SPECI FI CATION llaste tanks shall be analyzed for chromate (Cr04 2) as shown in Table 2;-2-1.

BASES Adherence to the Protection Limit will ensure that the lake water quality is not jeopardized by the introduction of corrosion inhibitors from-the Station.

Chromate corrosion inhibitor is used in the diesel generator closed loop cooling system.

The

'"ionitoring Requirement will ensure that any leakage of the chromate into other Station water systems will be detected.

1

TABLE 2.2 CHEMICAL LI UID HASTE ANALYSIS

~Sam le Cooling water Discharge

, Sample

~Fce uenc Monthly (1)

Composite Type 0f

~Anal sis pH

- Total Dissolved Solids Suspended Solids Sens itivity of Anal sis

+

0.5 pH units

+ 10.0 mg/liter

+

5. 0 mg/,1 i te r

'ooling

.eater Monthly (1)

Intak Composite pH Total Oissol ved Solids Suspended Solids

+

0.5 pH units

+ 10.0 mg/liter

+

5.0 mg/liter Itaste Tanks (2)

Each Batch

~

pH

+

0.5 pH units Monthly Proportional (3)

Composite pH Total Dissolved Solids Suspend d Soli.ds Ca+

Na+

SO 4

'PO' Cr04

+

0.5 pH units

+ 10.0 mg/liter

+

5.0

~ mg/1 iter

+

1. 0 mg/1 iter

+

1. 0 mg/1 iter

+

1. 0 mg/1> ter

+

1.0 mg/liter

+

0.05 mg/liter (1)

The cooling water intake and dis'charge are sampled continuously, for each

,week.

The.monthly composite includes an aliquot from each week's collection.

'I (2)

Includes floor drain sampl.e tanks, laundry tanks, and makeup demineralizer tank.

(3)

The proportional composite sample includes aliquots from each batch released.

k

LIYiITIi)6COHDITIOilS FOR OPERATIOi<

Protection Limit Monitorin Requirement 2.2.3 Suspended and Dissolved Solids OBJECTIVE The purpose of this Protection Limit is to limit the suspended solids, total dissolved solids and individual solute concentrations in the cooling water discharge to values consistent with the classifications and standards governing the quality and purity of Lake Ontario waters (Class.

A).

SPECI FICATION The maximum concentrations of suspended

solids, total dissolved solids, and individual solutes in the cooling w'ater discharge prior to dilution shall not exceed the corresponding lake ambient concentrations by more than the following values:

2.2.3 Suspended and Dissolved Solids OBJECTIVE The purpose of this monitoring Require-ment is to provide information on the concentrations of suspended solids, total dissolved solids, and individual solutes in liquid wastes discharged to Lake Ontario.

SPECIFICATIOil Liquid wastes discharged to Lake Ontario snail be monitored and analyzed as shown in Table 2.2.

Suspended Solids Total Dissolved Solids Calcium (as.Ca)

Sodium (as Na)

Sulfate (is SO

)

Total phosphor(s (as P)

Chromium.(as Cr) 15 mg/1 50 mg/1 5

mg/1 5

mg/1 3

mg/1 1

mg/1

. 0.05 mg/1 If tnese limits are exceeded, corrective action shall be taken to decrease concentrations to less than the Protection Limit.

BASES Maintaining the suspended solids, total dissolved

solids, and individual solute concentrations with-in the Protection Limit will ensure that the water quality standards and classifications of Lake Ontario are not jeopardized.

BASES The data obtained from waste tank monthly-proportional composite samples will be used with known flow rates to determine the increase in cooling water chemical concen-'rations over lake ambient concentrations

h

2.0 LIMITING CONDITIONS FOR OPERATION Protection Limit blonitorin Re uirement 2.2.3 (Cont'd)

BASES (Cont'd) resulting from waste tank rel ases.

Analyses of the cooling water intake and discharge will provide a check against gross errors in the proportional com-posite sample and analysis.

The analyses will provide the information necessary to verify that the concentrations of suspended

solids, total dissolved solids, and individual solutes in liquid wastes discharged to Lake Ontario do not exceed the Protection Limit.

2.0 LIt<ITING CONDITIONS FOR OPERATION Pro tecti on Limit Yionitorin Re uirement 2.2.4 pH BJECTIVE The-purpose of this Protection Limit is to limit the liquid effluent pH to a range of values consistent with tne classifications and standards governing

.the quality and purity of Lake Ontario waters (Class A).

SPECIFICATION The pH of treated water in tne waste tanks*.prior to being discharged into the discharg tyiinel shall be between 6.0 and 9.0..

If the pH limits specified above are. exceeded, dis-charges from the waste tanks* shall be terminated and:

a)

The cause of the pH anomaly determined.

b),

oH shall be corrected to within tne Protection Limit prior to the resumption of discharging contents of the waste neutralizer tank.

BASES Haintaining waste tank pH within the Protection Limit (6.0 to 9.0) will not jeopardize the water quality standards and classifications of Lake Ontario.

2.2.4 pH OBJECTI VE The purpose of this Monitoring Requirement is to provide sufficient information to ensure that the effluent pH will not exceed the Protection L'imit.

SPECIFICATION Sampling and analysis for pH shall be per-formed in accordance with Table 2.2.

BASES The analyses will provide sufficient information.to'ensure that the pH of 1 iqui d effluents d~ scharged to Lake Ontario is within the Protection Limit.

INCLUDES FLOOR DRAIN SAYiPLE TANKS LAUNDRY TANKS AND MAKEUP DE) IINERALIZER TANK~

2.0 LIMITING CONDITIONS - FOR OPERATION Protection Limit Nonitorina Re uirement

2. 3 Radioactive Discharge APPLICABILITY 2.3 Radioactive Discharqe APPLI CARI LITY Applies to the controlled release of radioactive liqui ds and gases from the faci 1 ity.

Applies to the periodic testing and recording requirements, and sampling and monitoring methods used for Stati on radi oacti ve effluents.

OBJECTI VE OBJECTIVE To define the limits and conditions for the controlled release of radioactive 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 instantaneous release rate for all effluent discharges should be within the limits specified in 10 CFR 20, Appendix B, Table II, Column 2.

To assure that the releases of radioactive material to unrestricted areas meet the as loiv as practicable

concept, the following objectives apply:

To ensure that radioactive liquid and gaseous releases from the Station are maintained within Protection Limits 2.3A and 2.38.

A.

Liquid Effluents a.

The annual total quantity of radioactive materials in liquid waste, excluding tritium and dissolved

gases, should not exceed 5 curies per unit, and the annual dose to the whole body or any organ of an individual due to the liquid effluents shall not exceed 5 mrem per unit.

This objective shall become applicable when planned modifications to the liquid radioactive waste sys tern, incl uding a second 1 iqui d waste concentrator, are completed and operable.

b.

The annual average concentration of radioactive materials in liquid waste, prior to dilution, excluding tritium and dissolved

gases, should not exceed 2 x 10-8 pCi/ml.

2.0, LIHITING CONDITIONS FOR OPERATION Protection Limit 2.3 OBJECTIVE (Cont'd)

A.

Liquid Effluents (Cont'd) c.

The annual average concentration of tritium in liquid waste prior to dilution should not exceed 5 x 10-6 pCi/ml.

B.

Airbo me Effluents The combined release rate of radioactive isotopes from the Nine Nile Point Stack and the FitzPatrick stack and vents, averaged over a yearly interval, except halogens and particulate radioisotopes with half-lives greater than eiqht

days, should be limited as follows:

of a~

s NHP-1

+

s Fitz

+ > iv Fitz

+1 0'0114 0'014 12'000 HPC where gs is the stack release rate in Ci/sec.

E is average gamma energy per disintegration, giv is the reTease rate in Ci/sec. of radioisotopes i from FitzPatrick building vents, and HPC is defined for radioisotopes i in Column 1, Table II of Appendix B

to 10 CFR 20.

The constants are determined by the annual average site meteoroloqy and the dose rate limit of 10 mrem/yr. to the whole body or any organ due to gaseous releases.

The release rate of halogens and other particulate radioisotopes with hal f-lives longer than eight days should result in a dose rate at the site boundary of less than 5 mrem/yr. to the whole bodv or to the thyroid of a 2 year old child from Nine Nile Point and FitzPatrick together.

2.0 LIMITING CONDITIONS FOR OPERATION Protecti on Limit 2.3 OBJECTIYE (Cont'd)

B.

Airborne Effluents (Cont d)

These objectives for gaseous wastes will be applicable when the augm'ented

.gas treatment system for the Nine Mile Point Unit 1.Station becomes operable.

1

2.0 LIMITING CONDITIONS FOR OPERATION Protecti on Limit Yoni torin Re uirement SPECI FI CATION SPECI FI CATION 2.3.2

~fi ff Efff 2.3.A Liquid Effluents 2.3.A.l The radioactivity release concentration in the discharge tunnel 'shall not exceed the values specified in 10 CFR 20, Appendix B, for unrestricted areas.

2.3.A.1 Each batch of radioactive liquid effluent shall be sampled and analyzed prior to release.

2.3.A.2 The cumulative discharge of radioactive liquid effluents per unit, excluding tritium and noble

gases, shall not exceed 10 curies during any calendar quarter.

This specification shall become effective when planned modi fications to the liquid radioactive waste system, including a second liquid waste concentrator, are completed and operable.

2.3.A.2 Station records shall be maintained of the radio-active concentration and volume prior to dilution of each batch of liquid effluent released and, of the average dilution flow and length of time over.

" which each discharge occurred.

2.3.A.3 During release of radi oacti ve 1 iqui d wastes, the following conditions shall be met:

a.

The radiation monitor on the discharge line from the waste disposal tanks to the discharge tunnel shall continuously monitor-released activity and shall be set to alarm prior to exceeding Protection Limit 2.3.A.l.

2.'3.A.3 Liquid radwaste sampling and analysis shall be performed in accordance with Table 2.3-1.

b. If Protection Limit.2.3.A.3.a cannot be met, continued release of liquid effluents shall be permitted only during the succeeding 48 hour5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months period.

Two independent samples of each tank shall be analyzed and two station personnel shall independently check val ving pri or to di scharge.

I

2.0 LIi1ITING CONDITIONS FOR OPERATION Protection Limit 2.3.A.4 The equipment installed in the. liquid radio-active waste system shall be maintained and shall be operated at all times to the fullest capacity consistent with maintenance require-ments.

2.3.A.5 When the cumulative discharge of radioactive liquid effluents, excluding tritium and n'oble

gases, exceeds 2.5 curies during any calendar

quarter, the licensee shall notify the Direc-torate of Licensing within 30 days,'identifying the. causes and describing. the proposed program of action to reduce such. release rates.

This specification shall become effective when planned modifications to the liquid radioactive waste

system, includihg the second liquid waste concentrator, are completed arid operable.

Nonitorinq Reouirement 2.3.A.4 Isotopic analysis of a representative batch of liquid waste shall be performed at least once per quarter.

Each batch of liquid waste shall be counted for gross beta activity, and when released on a radionuclide basis the analysis shall also include a gross gamma count and gamma scan.

If gamma energy peaks other than those determined by the previous isotopic analysis are found, a new isotopic analysis shall be performed and recorded.

An isotopic analysis shall also be performed, should there be significant changes in the gamma to beta ratio of the batch.

2.3.A.5 The liquid effluent radiation monitor (Protection

~Limit 2.3.A.3.a) shall be calibrated quarterly, shall have an instrument channel test monthly, and a sensor check daily.

2.3.A.6 The nerformance and results of independent samples and valve checks required by Protection Limit 2.3.A.3.b. shall be logged.

TABLE 2.3-1 RADIOACTIVE LI UID HASTE SAMPLING AND ANALYSIS HASTE TANK (floor drain sample

tanks, laundry tanks)-

SRMPII IR PRRILRRMSY TYPE OF ACTIVITY ANALYSIS SENSITIVITY OF ANALYSIS Each Batch Prior to Release Gamma Scan Gross Beta Gross Gamma 5 x 10 qCi/ml 10

~Ci/ml 10 pCi/ml One batcn/month Heekly Proportional Composite*

Monthly Proportional Composite

Dissolved fission and activation gases I131 B

140 Gamma Activity Balance (at least 905 of gamma emitters identified) 8.

Gross Beta Gross Gamma 10 pCi/ml

-6 10 pCi/m 5 x 10 pCi/ml 10 pCi/ml 10

>Ci/ml 10 yCi/ml quarterly Proportional Composite 5 89,90 10 vCi/ml

Samples include aliquots from each batch. released.

2.0 LIMITING CONDITIONS FOR OPERATION Protection Limit Monitorinq Requirement 2.3.8 2.3.8.1 Airborne Effluents The release rate of gross acti vity, except for halogens and particulates with half-lives longer than eight days, shall be limited as follows:

2.3 ~ 8 2.3.8.1 Airborne Effluents Sampling and analysis of airborne radio-activee effluents shall be performed as shown in Table 2.3-2.

E NYIP-1 s

0.57 where:

Q E FITZ 0.7 Q.

FITZ

+

3 lv 63 x IO liPC.

1 Q

FITZ 2.6 x 10 NMP-1 Q

FITZ 2.3 x 10 8.9 x 10 Q

=

stack release rate in Ci/sec.

E

=

average gamma energy per disintegration v

re 1 e a s e rate of i s oto p e i fro m bui 1 di n g ve nts in Ci/sec.

MPC.

=

defined for radioisotope i in Column 1, Table II of Appendi x 8 to 10 CFR 20.

2.3.8.2 The release rate of haloge'ns and particulates with half-lives greater than eight days released to the environs as part of the airborne effluents shall not exceed a'ate Q in curies/sec of,I-131 equivalent such that:

2.3.8.2 Station records of gross stack release rate of gaseous acti vity shall be maintained on an hourly basis by evaluation of the recorded data from the stack gas monitor to assure that the specified rates are not exceeded and to yield information concerning general integrity of the fuel cladding.

Records of isotopic analyses shall also be maintained.

Within one month following refuelings an isotopic analysis wi 11 be made of the gaseous acti'vity release rate.

From this sample a ratio of long-lived and short-lived activity will be established.

Samples of off-gas will be taken at least every 96 hours0.00111 days 0.0267 hours 1.587302e-4 weeks 3.6528e-5 months and gross ratio of long-lived arid short-lived activity. determined.

When these samples indicate a change in "the ratio of greater than 20 percent from the ratio established by the previous isotopic analysis, a

new isotopic analysis shall be performed.

A new isotopic analysis of off-gas will be performed at least quarterly.

Gaseous release of tritium shall be calculated on a monthly basis from'data

. measured quarterly.

15

l

TABLE 2.3-2 RADIOACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS A.

Stack (Sampled at iso-kinetic probe) 1~1: 1 Sampling FrecrFue n c Type of Activity Anal sis Detectable Concentration Gas Monthly and during each drywell purge Following 6 fi'ssion gases:

133,135,138

~85m,87,88

~

Calculate Z 22 fission gases 10 pCi/cc quarterly 10 yCi/cc Charcoal~

)

Continuous

sample, collection changed and analyzed weekly (3)

~ I131 10 pCi/cc one daily sample analyzed quarterly sample during drywell purge I

1 31 10 pCi/cc 10 pCi/cc Particulates Continuous

sample, gross

alpha, beta, collection changed

gamma. scan; 31, and analyzed weekly (3)

Ba-.La "0, I 10 pCi/cc

!1ontnly composite of weekly samples gamma emi tters Sr89,90 10 pCi/cc, Sampl.e during drywel 1 I131 pur ge 10 pCi/cc

l

TABLE 2.3-2 Cont'd B.

Condenser Air Ejector (Sampled at steam jet air ejector)

Sample T

e Sampling Frecruency Type of Activity Anal sis Detectable Concentration daily (At least every 96 nours) gross gamma count at 20 min.

and 2 nrs.

ratio of 2 counts.

10 pci/ml quarterly yr85m,87,88 g,

E 22 fission oasses calculated),

off-gas lioldup and E

determined..

~

i'(otes:

(1)

Gas samples from the stack and from the steam jet air ejector shoul'd be taken at th same time'iihenever possible so that holdup time beti'een ail ejector and stagk can be dete) mined.

(2)

!!hen the iodine and particulate release rate is greater than 8 percent of Protection Limit 2.3,B.2, the charcoal and particulate filters snail be changed and analyzed daily until a steady release rate is established.

(3)

Ilnen the gross release rate is greater than 1 percent of Protection Limit 2.3.8.1, and the average daily gross activity release rate increases by 50 percent over the=-previous

day, tne cnarcoal and particulate filters shall be changed and analyzed.

(4)

An isotopic analysis for the 6 major fission gases (Xe133,135,138 Kr

) shall be performed ivhenever the offgas sample ratio of long-lived to short-lived activity changes by mor than 20 percent from the ratio established by., the previous quarterly isotopic analysis.

l

~

2.0 LINITIH<G CQiHDI I N

i'lL Protection Limit Monltorln ice uiremeni 2.3.8.3 Tne rel ase rate of gaseous activity shall not exceed 16 percent of Protection Limit 2.3.8.1 or eight percent

.of Protection Limit 2;3 ~ 8.2 averaged over any calendar quarter.

Tnis speci fication shall become effecti ve when the augmented gas treatment system for i'line Mile Point Unit 1 Station becomes operable.

2.3.8.5 are exceeded, appropriate corrective action, such as an orderly reduction of power, shall be initiated to bring the releases within the limit.

l(hen the continuous release rate exceeds 4 percent of Protection Limit 2.3.8.1 for a period greater than 48

hours, the Director, Directorate of Licensing, shall.

be notified in writing within 10 days.

The report shall identify the causes of such activity and include the flow rate of the offgas system, the activity measured downstream of the condenser prior'o holdup, and the activity at a point 'upstream of the release point.

llhen the release rate averaged over a calendar quarter exceeds 8 percent of Protection Limit 2.3.8.1 or 4 percent of Protection Limit 2.3.8.2, the Director, Directorate of Licensing, shall be notified in writing within 30 days.

The report shall identify the causes of such activity and describe the proposed oroaram

'of action'o reduce the.release rate to the objective.

This speci fication shall become effective when the augmented gas treatment system for i/ine Mile Point Unit 1

becomes operable.

2.3.8.4 If Protection Limits of 2.3.8.1, 2,3.8.2 or 2.3.8.3 2.3. 8.3 Station records of stack release of iodines and particulates with half lives greater than eight days shall be maintained on the basis of all filter cartridges counted.

These cartridges shall be analyzed weekly when the iodine or particulate release rate is less than 8 percent of the maximum release rate given in Protection Limit 2.3.8.2, otherwise the cartridges shall be removed for analysis daily.

When the gross release rate exceeds 1 percent of the maxi-mum release rate gi ven in Protection Limit

2. 3. B. 1 and the average daily gross activity release rate increases by.50.percent over the previous day, tne cartridges shall be analyzed to determine the release rate increase for iodines and particulates.

2.3.8.4 At least once during each operating cycle the following activities shall be performed:

a)

Verify automati c initiation of offgas line insolation valve closure by both-offgas monitors.

b)

Verify automatic initiation of isolation of the mechanical vacuum pump line (closure of air-operated valve upstream of the pumps) by the main steam leone radioactivity monitors.

c)

Calibrate the main steam line radio-ac tivity moni tors

~

A 2.3.8.5 At least once during each quarter the offgas and stack gas monitors shall be calibrated.

18

2.0 6

C NDITIOHS FOR OPERATION Protection Limit t<nni tori n a Reaui remen t 2.3.8.6 One of the following conditions shall be met:

,a)

Botn offgas monitors shall be operable and capable of automatically closing the isolation valve in the offgas line at the maximum release rate specified by Protection Limit 2.3.8.1.

2.3.8.6 At least once during each shift a sensor check of the offgas monitors shall be performed; b)

One offgas monitor capable of automatic isolation and one of the two stack gas monitors shall be operable.

If neither of these conditions can be met, a

shutdown shall be initiated so that the reactor will be in the hot shutdown condition within 10 hours1.157407e-4 days 0.00278 hours 1.653439e-5 weeks 3.805e-6 months .

2.3.8.7 The automatic isolation devices required by Protection Limit 2.3.8.6 shall normally be set to isolate when Nine Nile Point Unit 1 releases exceed naif of Protection Limit 2.3.8.1 for combined iljkP-1 and JAF releases.

The devices may be set to isolate at a release rate greater than half the combined limit when the release rate at the FitzPatrick plant is sufficiently low to ensure that isolation will occur before the combined limit (2.3.8.1.) is exceeded.

2.3.8.8 The mechanical vacuum pump line shall be capable of automatic isolation by closure of the ai r-operated valve upstream of the pumps.

The signal to initiate isolation shall be from high radioactivity (five times normal) in the main steam line.

19

2.0 LIMITING CONDITIONS FOR OPERATIOfl 2.3 8ASES A.

~fi fd Af f Liquid radioactive waste release levels to unrestricted areas should be kept as low as practicable and are not to exceed the concentration limits specified in 10 CFR 20.

These levels apply to Nine Mile Point Unit 1 effluents, but provide reasonable assurance that the resulting annual dose to the whole body or any organ of an individual will not exceed 5 millirems from Nine Mile Point Unit 1 effluents.

At the sam time, tnese specifications permit the flexibilityof operation, compatible with considerations of health and safety, to assure tnat the public is provided a dependable source of power under unusual opera-ting conditions which may temporarily result in.releases higher than the design objective levels but still within the concentration limits specified in 10 CFR 20.

It is expected that by using this operational flexibility.under unusual operation 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 annual average concentration limits specified in 10 CFR 20.

The design objectives have been developed based on operating experience taking into account a combination of variables including fuel failure, primary system

leakage, and the performance of the various waste treatment systems.

Protection Limit 2.3.A.l requires the licensee io'.limit the concentration of radioactive materials in liquid effluents from the station to. levels specified in 10 CFR 20, Appendix B'or unrestricted areas.

Radioactive liquid effluents released from the Station to unrestricted areas on the basis of gross beta analysis are based on the assumption that iodine 129 and radium are not present.

Accordingly, Appendix B, Table II, Column 2'of 10 CFR 20 will permit.a concentration up to 1

x 10 7 pCi/ml in the cooling'water discharge canal.

If radioactive effluents are released to unrestricted areas on a radionuclide basis, the MPC shall be determined and controlled in the cooling water discharge canal in accordance with Appendix B, Table II, Column 2 of 10 CFR 20 and note 1 thereto.

Monitoring Requirement 2.3.A.4 provides that the release of liquid effluents on a radionuclide basis shall be based on an isotopic analysis of a typical waste batch.

This analysis shall be performed at least quarterly and shall include specific radiochemical separations for 90Sr and 131 I.

Along with an isotopic

analysis, a gross gamma and a gross beta counting efficiency shall be determined for the particular isotopic mixture. and a gamma/beta ratio established.

A required dilution factor for the isotopic mixture shall be determined using the following formula:

Required D.F.

= Cl

+

C2 C

~

+

n MPC1 MPC2 MPC Where:

Cl

= concentration of Isotope 1, etc.

MPC1

=

MCP for Isotope 1 from Appendix B, Table II, Column 2, 10 CFR 20

2.0 LINITIhG CONDITIONS FOR OPERATION 2.3 BASES (Cont'd)

~Li id Eff1 t.

(C

'd) ross concentration This dilution factor can be expressed as a

NPC for the isotopic mixture thus:

Mixture NPC = Required D.

This mixture NPC shall be used to determine the appropriate discharge rates for waste batches but can only be used for the particular mixture as determined above.

In order to verify that the mixture has not significantly changed, Monitoring Requirement 2.3.A.4 provides that each batch shall be counted for gross beta, gross gamma ahd shall have a

gamma scan performed.

Significant changes

(+ 50%) in the gamma/beta ratio or the appearance of new energy peaks in the gamma scan snail require a new isotopic analysis to be performed.

The minimum frequency of the isotopic analysis wi 11 be varied depending on the average discharge canal concen-tration.

The minimum of one isotopi c analysis per'quarter will be performed as long as the average concentration of the discharge canal is less than lX of the previously calculated Mixture HPC.

An average concentration of between 1/ and 105 of Mixture MPC shall require an. isotopic analysis at least monthly.

For average concentrations greater than 10$ of the Mixture NPC, each batch shall be isotopically analyzed.

The average concentration shall be calculat'ed daily and shall be a running average annual concentration.

Protection Limit 2.3.A.2 establishes an upper limit for the release of radioactive liquid effluents, excluding tritium and noble gases, of 10 curies from the iodine Mile Point Unit 1 Station during any calendar quarter.

.The intent of tnis specification is to permit the licensee the flexibilityof 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 Station and the liquid radwaste equipment are functioning as designed.

Releases of up to 10 curies from the Nine Nile Point Unit 1 Station during a calendar quatter will result in concentrations of radioactive material in liquid effluents at small percentages of the limits specified in 10 CFR 20.

It is also in compliance with NEPA requirem nts.

Protection Limit 2.3'.3 requi r'es that suitable equipment to control and monitor the releases of radioactive materials in liquid effluents are operating during any period these releases are taking place.

Monitoring requirement 2.3.A.l requires sampling of each waste batch prior to release to the discharge canal.

This

'rocedure is backed up by tne radiation monitors in the line from the waste disposal tanks to the discharge canal.

The hi-hi alarm point shall be set on these monitors such that they will warn of a higher than appropriate NPC in the discharge canal.

In the event of the hi -hi alarm, the discharge shall cease until the cause is corrected.

In the event the effluent monitor is out of service, two independent samples of each waste batch shall be taken and two Station personnel will independently check valving prior to discnarge of liquid waste batches.

Protection Limit 2.3.A.4 requires that the licensee shall maintain and operate the equipment installed in the liquid radioactive waste system to reduce the release of radioactive materials in liquid effluents to as low as practicable level consistent with the requirements of 10 CFR 50.36a.

Normal use and maintenance of installed equipment in the liquid radioactive waste system is expected to result in releases of not more than about 5

curies/yr during normal operations.

21

~

.2.0 LIYiITING CONDITIONS FOR OPERATION 2.3 BASES (Cont'd)

A.

~Li id Eff1

'(C

'd)

In addition to Protection Limit 2.3.A.Z, Protection Limit 2.3.A.5 requires that the licensee shall identify the cause whenever the release of radioactive effluents, excluding tritium and noble gases, exceeds 2.5 curies during any calendar quarter and describe the proposed program of action to reduce such release rate.

This report must be filed within 30 days.following the calendar quarter in which 2.5 curie release occurred.

There are no liquid radioactive waste tanks in the station which could be discharged directly to the environ-ment because of a component failure.

The liquid radwaste. discharge monitor would alarm in the case of high radioactivity and the flow would be terminated.

For these reasons no limit is placed on the amount of*activity that may be contained in a single tank.

B.

Airborne Effluents The levels specified in 2.3.B provide reasonable assurance that resulting annual exposure rate from noble gases at any location at the site boundary will not exceed 10 millirems per year from the combined Nine Hile Point Unit 1 and FitzPatrick effluents.

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

It is expected that using this operational flexibility under unusual operating conditions, and by exerting every effort to keep levels of radioactive mater'ial in gaseous wastes as low as practicable, the annual releases will not exceed a small fraction of the annual average concentration limits specified in 10 CFR 20.

The design objecti'ves have been developed taking into account a combination of system variables including fuel fai lures, primary system leakage, and the performance of radioisotope removal mechanisms.

Protection Limit 2.3.8.1 provides a method to be used in summing the airborne effluents. from the main stack of Nine Nile Point Unit 1

and from the stack and vents of FitzPatrick, excluding halogens and particulates wi th

'alf-lives greater than eight days, which will assure that the release rate does not exceed 10 CFR 20 for unrestricted areas at the Nine Nile Point site boundary.

The constants are determined by the annual average site meteorology and a dose rate o'f 500 mrem/yr to the whole body or any organ.

The release rate in curies/sec and the average gamma energy per disintegration used in the equation of Z.3.B.l and in that of the gaseous release rate objective will be based on the average composition of gases determined from the average of tne previous month's isotopic analyses.

The gamma energy per disintegration for those radio-isotopes determined to be present from the isotopic analyses shall be as given in "Table of Isotopes,"

C.

H.

Lederer, J.

M. Hollander, and I. Perlman, Sixth Edition, 1967.

Other documents may be used for the average en rgy, provided such documents reference the above works.

For example, for la-89 and Xe-138, the gamma energy per disintegration shall be as given in "Energy Release -from the Decay of Fission Products,"

Nuclear Science 5 Engineering:

3,726-746 (1958) until values are published i'n "Table of Isotopes."

22

2.0 LIMITING CONDITIONS FOR OPERATION

2. 3 BASES 8., Airborne Effluents (Cont')

Protection Limit 2.3.8.2 provides a method to be used in summing airborne halogens and particulates with hal'f-lives greater than eight days released from the main stack of Nine Mile Point Unit 1

and from the main stack and vents of FitzPatrick wnich will assure that the release rate does not exceed 10 CFR 20 for unrestricted areas at the Nine Mile Point site boundary.

Detailed calculations of ground level air 'concentrations of iodines and particulates with half lives longer than eight days at several offsite locations have been made as described in Appendix D of tne FSAR.

These calculations consider site meteorology and buoyancy characteristics of the effluent.

Based on these calculations, the release rate limit for these isotopes in the equation in Speci-fication 2.3.8.2 is obtained.

Use of this equation assures that releases will not result in offsite doses in excess of those specified in 10 CFR 20.

The assumptions used by the AEC Staff for these calculations were:

(1) onsite meteorological data for the most critical 22-1/2 degree

sector, (2) no building wake credit used, and (3) to consider possible reconcen-tration effects a reduction factor of 700 was applied to allow for the milk production and consumption mode of uptake.

The reduction factor of 700 has been incorporated into the equation in Protection. Limit 2.3.8.2.

Protection Limit 2.3.8.3 establishes an upper limit for the continuous release of noble gases at 16 percent and halogens and particulates at 8 percent of the instantaneous release limit averaged over any calendar quarter.

Protection Limit 2.3.8'.4 is to require the licensee to take such actions, including reducing Station power or other appropriate

measures, as may be necessary to keep the radioactive gaseous releases within specified 1 imits.

Protection Limit 2.3.8.5 is to monitor. the performance of the core.

A sudden increase in the activity levels of gaseous releases may be the result of the fuel cladding losing its integrity.

Since core performance is of utmost importance in the resulting doses from transients or postulated accidents, reports must be filed within the specified times following the specified increase in gaseous radioactive. releases.

Protection Limit 2.3.8.6 requires that monitoring devices and isolation functions be operable.

The isolation of the offgas system is initiated by high radiation in the offgas piping.

Backup for the offgas monitors is provided by two stack gas monitors.

The stack gas monitors will alert the operator of a high radiation-con-dition. so that the offgas piping can be manually isolated.

The radiation monitors for these systems are discussed in Sections VIII-C.3.1.1 and 3.1.2 of the FSAR.

Protection Limit 2.3.8.7 provides the administrative procedure by which the automatic isolation function of Protection Limit 2.3.8.6 will be accomplished taking into account FitzPatrick plant releases.

Operational flexibilitywithin the protection limits is provided by permitting the alarm to be set at a point. higher than half of the combined release rate limit'when FitzPatrick plant operating conditions are such as to ensure that Protection Limit 2.3.8.1 will not be exceeded with Nine Mile Point Unit 1 releases at the alarm point.

23

I>

2.0 LIilITING CONDITIONS FOR OPERATION 2.3 BASES B.

Airborne Effluents (Cont'd)

The purpose of isolating the mechanical vacuum pump line (Protection Limit 2.3.B.S) is to limit release of activity from the main condenser during a control rod drop accident.

During the accident, fission products would be transported from the reactor through the main-steam lines to the main condenser.

The fission product radio-activity would be sensed by the main-steam line radioactivity monitors and initiate isolation.

During purging the primary containment atmosphere i s normally exhausted directly to the stack.

Should the nitrogen atmosphere become significantly contaminated it is passed through the reactor building emergency ventilation system prior to release.

The monitoring requi rements provide assurance that liquid and gaseous wastes are properly controlled and monitored during any release of radioactive materials in tne liquid and gaseous effluents.

The monitoring requirements provide the data for the licensee and the Commission to evaluate the Station's performance relative to radioactive wastes released to the environment.

Reports on the quantities of radioactive materials released in effluents shall be furnish>ed to the Commission as described in Section 5 of these Technical Specifications.

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

hw

~

a

3. 0 IGA FEATURES AND OPERATIi<G PRACTICES 3.1 Intake System Cooling water for Unit 1 is withdrawn from Lake Ontario, at a rate of 600 cfs (268,000 gpm) into a hexagonal intake structure located in a water depth of approximately 18 feet below the mean lake surface elevation of 246.0 feet (USLS 1935 Datum).

The structure lies about 850 feet from the existing shoreline and is connected to the screenwell by a tunnel beneath the lake bed.

The intake structure is covered by a roof of sheet piling supported on steel

beams, and each of the six sides has a water inlet about five feet high by ten feet wide, with the inlet openings guarded by galvanized steel racks.

This design provides for water to be drawn equally from all directions with a mini-mum of disturbance and with no vortex at the lake surface, and also prevents the entrance of unmanageable flotsam to the circulating water system.

The velocity at the intake openings is approximately 2 fps when the Station operates at maximum output.

The intake tunnel runs under the lake from the intake structure to the screen-well and pump'ouse located on.shore, adjacent to the turbine building.

The water drops through a vertical concrete-lined shaft to a concrete-lined tunnel through which it flows to the foot of a concrete-lined vertical shaft under the forebay in the screenhouse.

The foot of this shaft contains a sand trap to catch and store any lake-bottom sand which may wash over the sills of the inlet structure.

The tunnel has a cross-sectional area of approximately 74 sq.

ft, which yields a tunnel velocity of approximately 8.0 fps.

There are two main condenser circulating water pumps in the pump house, with a total capacity of 250,000.gpm.

They take suction from three separate inter-connected bays in the screenwell.

Before reaching the

pumps, the circulating water passes through trash racks and traveling water screens.

The system design is flexible and partial flow can be maintained during system maintenance and servicing.

The traveling screens are backwashed with about 2,400 gpm of service water on an automatic time cycle of 3 minutes duration every 60 minutes.

Screen washings are sluiced into the discharge tunnel.

Trash racks ahead of the screens deposit their collected materials into receptacles.

This debris is periodically removed for disposal as land fill.

The operation of Nine Mile Point Unit 1

does not require circulating water algicide treatment.'he silt (fine glacial till) content in the raw lake-water has proven sufficient to prevent attachment of biological growth on exposed surfaces (condenser tubes) of the cooling system.

25

3.2 Discharge System A discnarge tunnel, approximately 78 sq. ft. in cross-section, runs under the lake -from the screenwell to the discharge structure.

The design velocity in the tunnel is approximately 8 fps.

The discharge structure is located at a.

point about 535 feet north of the screenwell.

Ilater is returned to the lake througn a bell-mouthed outlet surmounted by a hexagonal-shaped concrete discnarge structure.

The top of this structure is about 4 feet above lake bottom and 8 1/2 feet below the lowest anticipated lake level.

The geometry of the structure closely resembles the inlet structure, although reduced in size.

The six exit ports are about 3 feet high by 7 feet 4 inches wide.

The exit vel'ocity is approximately 4 feet per second.

Unit 1 operates at rated output with a main condenser flow of 557 cfs (250,000 gpm) and a maximum temperature rise of 32 F, and a service water flow of 40 cfs

'(18,000 gpm) with a maximum temperature rise of 20 F.

Total flow for Unit 1

is thus approximately 600 cfs (268,000 gpm), with a temperature rise of 31.2 F.

These water flows and temperature increases remain essentially the same through-out the year.

The seasonal temperature variation of the cooling water temperature at the intake is approximately 33 to 80 F.

The total time of travel of water though the cooling system from the intake point to the discharge point is about 6 minutes, of which passage through the condenser alone is about 14 seconds and travel time. from the condenser to the exit from the discharge structure is 3 minut'es.

3.3 Chemical Usage A.

Makeup System

'I The Station makeup system utilizes Lake Ontario water as a source, clarifies and softens the water, filters it, deionizes it and stores it in demineralized water storage tanks for use throughout the plant.

Lime and iron sulfate are used in the clarifier-softener.

The blowdown from this unit goes to a settling basin where the solids are thickened.

Approximately every 3 months these solids are disposed of'n a spoil area on site.

Dilute sodium hydroxide and sulfuric acid are used to regenerate the deionizers.

These solutions are routed to a neutralizer tank where the pH is adjusted.

They are then diluted in the main condenser discharge tunnel before discharge to the lake.

Approxi-mately 5000 lbs. of sodium sulfate are discharged to the lake each month.

.With a discharge flow of 1.2 x 1010 gallons per month the average concentration of sodi um sulfate in the discharge tunnel is about 0:02 parts per million in excess of the lake ambient concentration.

Radioactive Waste System Yarious chemicals such as concentrator corrosion inhibitors, solidification

agents, and filter pre-coat materials are used in the solid waste handling system.

However, these wastes

'are discharged only in the. solid waste form and are not released into the discharge tunnel.

C.

Laundry Waste Wastes from the laundering. of protective clothing -are processed in tne liquid.

radioactive waste system prior to disposal by mixing with. the circulating water discharge as discussed in Section 3,6.

A low foaming detergent is used containing about 50 percent by. weight of sodium hexametaphosphate.

During normal operation, about 100 pounds per month of this detergent is utilized to produce a laundry waste of about 130 gallongs per day (gpd).

After complete mixing with the circulating water, the incremental increase in the level of phosphates in the lake water measured as phosphorus is about 0 '

parts per billion (ppb).

During scneduled outages about 450 pounds per month of this detergent is utilized to produce a laundry waste of about 1,700 gpd.

After complete mixing with the circulating water, the incremental increase in the level of phosphates in the lake water measured as phosphorus

.is about 0.7 ppb..

D.

Diesel Generator Coolant Sodium chromate is used as a corrosion inhibitor in the emergency diesel generator coolant system.

This system contains approximately 300 gallons of an 1800 part per'illion solution of Ha2Cr04.

This system is not dis-charged through the liquid waste system.

Any disposal is performed in a manner which ensures that no chromate is released to Lake Ontario.

27

E.

Sanitary Waste System The sanitary sewage system collects sanitary waste from all nonradioactive sanitary fixtures within the Station.

This sanitary waste. is conveyed to an activated sludge package plant of the extended aeration-type, followed by chlorination and oxygenation.

The sanitary sewage passes through a communitor which reduces the solids to fine particles prior to entering the acti vated sludge aeration tank.

Digested sewage from the sludge tank is conveyed to a clarifer where inert solids are removed and the clear'verflow flows into a chlorination tank for disinfection by tne addition of chlorine.

The disinfected liquid is pumped to a 2,800 square foot oxygenation pond which has sufficient surface area to restore dissolved oxygen to the effluent before it cascades over a weir into a drainage ditch.

The ditch carries the effluent to a

rivulet which flows into the lake.

The residual chlorine content in this drainage ditch is less than 1 part per million.

3.4 Land Management It is Niagara Mohawk's policy to encourage growth of desirable species of trees, shrubs and ground covers which will preserve and enhance the ecological values of unoccupied land on its generating sites and transmission rights-of-way.

Transmission

.line maintainance is accomplished on a scheduled basis under the supervision of Niagara Mohawk personnel and includes selec-tive use of herbicides, approved for such use by appropriate governmental agencies.

The guides for the use of herbicides are as follows:

(a)

Selective use of herbicides shall be employed to maintain "tight ground cover",which will allow growth of compatible weeds and woody species and tend to encourage wildlife habitat growth.

(b)

No herbicide shall be used in an application for which it is restricted by the New York State Department of Environmental Conservation restricted use list.

(c)

Herbicides such as 2, 4, 5-T or similar compounds which are approved for use by the U.

S.

Environmental Protection Agency for the purpose intended shall be used as prescribed and directed by registered label.

(d)

No formulation with a dioxin contamination level that exceeds 0.1 parts per million should be used.

(e)

No contamination of potable water supplies shall be permitted.

(f)

Application of herbjcides to potential human foodstuffs in-cluding wild berries should be avoided.

(g)

No herbicides shall be used within 100 feet of watercourses.

(h)

Niagara Mohawk policy mandates fee ownership of transmission rights of way. If herbicides are to be applied to an area where a grazing easement is in effect, the holder of the easement shall be notified of product label requirements regarding grazing prior to application of the herbicide.

(i)

Treatment should not be more than once per year.

(j)

As soon as the Administrator of EPA issues standards for pesticide applicators, all spraying should be done by an individ'ual meeting these standards or under his immediate supervision.

(k) l/hen it becomes necessary to cut or spray vegetation which in the wilting stage has a potential for physiological harm to grazing animals, precautions shall be taken to preclude.

availability of such material to livestock.

3

3.4 Continued.

To this degree herbicides are employed for treatment of stumps in initial clearing operations to negate future sucker growth which would shade out and prevent the growth of more desir-able species.

Subsequently, as field observations

dictate, various herbicides and/or combinations of herbicides are employed on a selective basis to prevent the growth of those species which could result in interference and potential short circuit of transmission lines.

Erosion of areas of the site and transmission corridor is

'ontrolled by encouraging regrowth of ground cover and through seeding practices.

The Lake Ontario shoreline has been protected by constructing an extensive stone dike which counteracts wave action.

I Approximately 130 acres of the northwest corner of the Nine Nile Point site have been established (by'osting) as a natural wildlife refuge to preserve wildlife habitat in this area.

There are no plans for creation of a larger refuge.

30

4.0 ENVIRONMENTAL SURVEILLANCE AND SPECIAL STUDY PROGRAMS 4.1 4.1.1 4.1.1.A.

Biol ogi cal Aquatic General Ecological Survey OBJECTIVE h

To eval.uate the effects of plant operation on the aquatic environment of Lake Ontario in the vicinity of Nine Mile Point.

The specific aims of the General Ecological Survey are as follows:

1.

Determination of distribution and relative abundance of species in space and time in the biotic groups (phytoplankton, zoo-plankton, periphyton,

benthos, and fish);

2.

Determination of changes in biological parameters and their significance within and out of 'the area influenced by the thermal plume; 3.

Determination of the relationship of changes within and among biotic groups and with the physical and chemical characteristics of the environment; 4.

,Determination of the relationship of changes to the operation of the plant and significance oi'he effect of such changes on the ecosystem; 5.

Based on the results of the above analysis:

(a) either establish limiting conditions and report levels for the various identified biological parameters or establish tha't measurement of such parameters is unnecessary due to an insignificant impact.

(b) identify which of the biological parameters require continuing monitoring throughout the life of the plant.

SPECIFICATION 4.1.1.A.1 A General Ecological Survey has been conducted since Nine Mile Point Unit 1

became operational.

In 1973 the collection of data was extended and expanded;Zo relate to a surveillance program for the Nine Mile Point site (including Nine Mile Point Units 1 and 2, and the Fitzpatrick Nuclear Power Plant).

A detailed report of results of the first year of the expanded site program will be issued early in 1974.

This report will provide data to establish preliminary values of the protective limits and report levels for the various environmental parameters surveyed.

It will also include substantiated recommend-ations for modification of the monitoring program for Nine Mile Point

. Unit l.

31

The proposed protection limits shall not become binding until final values have been established.

These values shall be based on monitoring and evaluation of the operation of Nine Nile Point Unit 1 and the Fitzpatrick Power Plant.

At the end of the second year the results from the General Ecological Survey shall. be

analyzed, evaluated by the lie'ensee and submitted i n summarized form to the Directorate of Licensing.

The r'eport shall include proposed final values of the protection limits and report levels or appropriate substantiated recommendations for modifications or discontinuance of the various portions of the monitoring program.

For purposes of compatible interpretation of the data, as much as

possible, the data shall be collected and analyzed in accordance with the methods used in the International Field Year for the Great Lakes and other on-going studies on Lake Ontario.

The frequency of field sampling shall be in accordance with Table 4.1. 1.

Sampling locations and type of sampling shall be in accordance with Figure 4. 1. 1.

Phytoplankton - Honthly duplicate samples shall be collected from approximately one (1) meter below the surface at each of the samp1 i ng '1 oca tions in a 1 1 four trans ects.

Phytopl ankton density shall be determined (units/ml) for total phytoplankton,

diatoms, green, and blue-green algae present.

llhere possible identification shall be to species and the density of dominant organisms shall be reported.

Chlorophyll-a and primary productivity (as determined by light dark bottle 4C method) shall be determined for monthly samples at each of the sampling locations.

32

TABLE 4.1.1 - Frequency of Sampling for Ecological Studies in the Nine Mile Point Area of Lake Ontario.

Study/Biotic Group Frequency (April - December)

A.

General Ecological Survey Phytoplankton Zooplankton Periphyton

-Benthos Fish - Trawling, Seining, Gill Netting Lake Water Chemistry B.

Impingement of Organisms Collection of impinged fish C.

Entrainment of Organisms Through the

'Condenser Monthly Monthly Monthly Every Other Month Twice per Month

~ Twice. per Month Weekly Twice per Month, throughout the year 33

T-TRAWLI NG S-SEINING G-GILL NETTING P-PERIPHYTON 8-BENTHOS PP<<PHYTOPLANKTON ZP-ZOOPLANKTON EL-FISH EGGS 8 LARVAE FOR TRAWLINGTHIS IS ONE TRANSECT NMPW NMPP IFITZ TYPICAL T G jB PP ZP 60 WATER DEPTH FT (NOT TO SCALE) 50 T,G,B,P; PP,ZP OO G,B,P EL EL I +STACK NIAGARA MOHAWK-POWER COR P.

P.O l5 IO 5

S PLEASAN POINT T,B,P, PP,ZP G

B)P,PP,ZP P

S s

Cq~

8(>,

ALCAN CO.

TRANSECTS NMPW - WEST CONTROL NMPP -

NMP PLANT F I TZ - FITZPATRICK PLANT NMPE - EAST CONTROL 0 RADIO MAST W SGO SA MPLING LO CAT ION S NINE M I LE PO l N 7 l975 OSWEGO IO,OOO SCALE IN FEET 208000 FIGURE 4.1.1 34

Zooplankton - Monthly replicate samples shall be collected at sampling stations in all four transects by vertical tows from the bottom to the surface of the lake in such a way as to.ensure sampling of Mysis, Pontoporea, and Gammarus populations.

If these three populations are not properly sampled additional sampling with other sampling gear shall be done to ensure a total picture of zooplankton fauna.

Organisms shall be identified to the lowest-possible taxonomic level and enumerated.

Density in numbers per cubic meter shall be determined for major zooplankton taxa and dominant species.

Periphyton - Monthly, four (4) replicate samples shall be examined from artificial substrates at each of the sampling locations in all four transects.

The samples shall be analyzed for biomass, species composition, and relative abundance.

Benthos - Replicate samples of the macroinvertebrate community shall be collected every other month at each of the sampling locations in all four transects.

Organisms shall be identified to the lowest possible taxa and enumerated.

Results shall be reported in terms of total biomass and numbers of organisms per unit area of the substrate sampled.

Fish - Adult and immature fish shall be collected twice per month by trawling, gill nets,. and seines.

Wherever possible trapnets shall also be used to ensure a complete representation of fish populations in the area.

Trawling shall be done for approximately 15 minute duration for each sample at three stations each i n three transects.

The gill nets shall be set for 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months and fish shall be removed at approximat'ely 12 hour1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months intervals to correspond with diurnal cycle at all stations in all four transects.

Trawling shall also be done at night.

Age and growth studies shall be conducted-and food habits determined for three species:

Yellow perch (Perca Flavescence),

white perch (Morone americana),

and small mouth bass Micro terus dolomierue).

The number of individuals. of each species collected shall be noted along with individual lengths and weights.

For a large sample',

a representative random subsample'shall be satisfactory.

Coefficient of condition shall be calculated for each sex by months.

Fecundity measurements shall be made on species spawning in the vicinity of Nine Mile Point; periodicity of spajning shall be determined for these species.

35

J

4.1.1.A. 6 Continued Sampling for fish eggs and larvae shall be conducted at the following stations:

1/2 Mile Radius Station 1 - In 20 'ft of water on the west Station 2 - In 40 ft of water on the west Station 3 - In 60 ft of water off the plant Station 4 - In 40 ft of water on the east, Station 5 - In 20 ft of water on the east 1 Mile Radius Station Station Station Station Station 1 - In 20 ft of water on the west 2 - In 40 ft of water on the west 3 - In 80 ft of water off the plant 4 - In 40 ft of water on the east 5 - In 20 ft of water on the east 3 Mile Radius Station 1 - In. 20 ft of water on the west Station 2 - In 40 ft of water on the west Station 3 - In 100 ft of water off the plant Station 4 - In 40 ft of water on the east Station 5 - In 20 ft of ivater on the east 4.1.1.A.7 Samples shall be collected at surface, mid-depth, and bottom with appropriate sampling gear.

Samples shall be collected weekly during daylight and night from mid June to'mid September and only during daylight from April to mid June and mid September to December.

Lake water chemistry - Hater quality surveys shall be conducted to complement the sampling for biotic groups.

Samples shall be collected twice per month in 20 ft. and 60 ft. of water at the west and east controls and off Nine Mile Point and analyzed for:

Dissolved Oxygen Temperature Specific Conductance Carbon Dioxide pH Total and Orthophosphorus Total Kjeldahl Nitrogen Amonia Nitrogen Nitrate Nitrogen OOD(5)

COD

,Total solids Total Suspended Solids Silica Turbidity Chlorophyll-a 36

4.1.1.A.S The information gathered under the general ecological survey shall be analyzed in'ccordance with accepted biostatistical methods for significance and correlation within and amonq biotic groups in order to meet the stated objectives.

BASES The information outlined in the Specification will provide data for interpretative, analysis of the situation existing in the aquatic ecosystem of Lake Ontario in the Nine Mile Point area.

This information will provide data for determining significance of changes caused by the plant so that corrective measures may be taken if deemed necessary.I'7

Impingement of Organisms OBJECTIVE To estimate the number and weight of fish impinged on the trash racks and the traveling screens in the intake structure during day and night in various seasons so that the significance of this fish mortality to the ecosystem may be determined and corrective measures taken if deemed necessary.

Further to establish limiting conditions and report levels.

SPECIFICATION Niagara Hohawk has been sampling and evaluating (species,

numbers, lengths, weights and diurnal variation) the impingement of fish on the traveling screens of the main circulating water system since June, 1972.

Summaries of these studies have been submitted as part of the Nine Nile Point Unit 1 full term license application.

A final report concerning these studies (through December 1973) including recommendations regarding future efforts in this area shall be submitted to= the Directorate of Licensing early, in 1974.

Based upon the results, discussion,

=review and evaluation of the previous surveys and final report, Niagara Hohawk and the Atomic Energy Commission shall mutually determine and agree upon the need for and extent of any future survei llance program.

If it is determined that fish impingement is significant in this regard, proposed limiting conditions and report levels shall be established.

BASES The information described in the Specification was developed to assist a determination of the magnitude of fish impingement at Nine Nile Point Unit l.

The data on fish collected under the General Ecological Survey will be used to estimate levels of fish abundance in the Nine Hi le Point area.

The impingement data shall be.analyzed for the significance of impact on*the ecosystem in the light of fish abundance data.

38

t

Entrainment of plankton, fish eggs and larvae OBJECTI VE To determine extent of entrainment and the mortality of entrained organisms and to establish limiting conditions and report levels.

SPECIFICATION Niagara Flohawk has been s'ampling and evaluating the entrainm'ent of plankton, fish eggs, and larvae since June 19'72.

Summaries of these studies have been submitted as part of the Nine tlile Point Unit 1 full term license application.

A final report concern-ing these studies including recommendations regarding future efforts in thi s area shal 1

be submi tted to the Directorate of Licensing early in 1974.

Based on the results, discussion,

review, and evaluation of the previous surveys and final report, Niagara t'iohawk and the AEC shall mutually determine and agree upon the need for and extent of any future surveillance program.

If it is determined that

,mortality due to entrainment is significant in this regard, limiting conditions and report levels shall be proposed.

The current surveillance program. for plankton, fish eggs, and

larvae, which will be completed at the end of 1973, is desciiibed i.n this Specification.

Twice per month, replicate samples shall be collected during day and night for all entrained organisms at following locations:

(1) i ntake forebay, (2),discharge

forebay, (3) at the discharge before mixing with ambient water occurs, (4). in the mixing zone, and in the plume 2

F above ambient.

Simulated laboratory studies will be acceptable where actual field sampling is not possible due to design features.

~ Phytoplankton - The viability of phytoplankton after condenser passage and the concentrations of chlorophyll-a ard photosynthetic rate as determined by C uptake shall be determined at 7, 24, 48 and 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months after collection.

Zooplankton - Organisms shall be identified to,the lowest possible taxa and viability shall be determined

'as soon as possible after collection up'...to a

24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months period.'ttempts shall be made to identify size selective mortality.

Fish eggs, fry, and young of the year -

Two plankton. nets shall. be permitted to drift i.n the current in the forebay.

The contents of nets shall be examined for fish eggs and larvae which shall be identified and enumerated for approximately five (5) minute collections.

Extent of mortality shall be determired in field and laboratory thermal shock studies.

39

4.1.1.C.5 Early in 1974 the results from the study shall be analyzed, evaluated by the licensee and submitted in summari-zed form to the Directorate of Licensing.

The report shall include:

(a) proposed final values of the protection limits and report levels or appropriate substantiated recommendations for modifications or discontinuance of the various portions of the study.

(b) identification of those biological parameters which require continuing monitoring throughout the life of the plant.

BASES The data outlined in the Specification above is necessary to determine the extent of entrainment and of mortality of entrained organisms.

These data will be analyzed in the light of information obtained on plankton and fish eggs and larvae under the General Ecological Survey to determine the significance of entrainment mortality and to arrive at limiting conditions and report levels.

40

Samples shall be collected at the surface and bottom at the above mentioned stations in the lake at lease once per month to the extent weather permits.

These samples shall be analyzed for:

1.

Alakl ini ty 2.

5-day Biological Oxygen Demand (BOD )

3.

Chemical Oxygen Demand (COD) 4.

Total Solids 5.

Total Filterable Solids (Dissolved Solids) 6.

Total Non-Filterable Solids (Suspended Solids) 7.

Total Volatile Solids 8.

Total Kjeldahl Nitrogen 9.

Ammonia 10.

Nitrate ll.

Total Phosphorus 12.

Color 13.

Specific Conductance.

14.

Total Coliform Bacteria 15.

Fecal Coliform 16.

Organic Nitrogen 17.

Ortho-phosphate 18.

Sulfate 19.

Chloride 20.

Alumi num 21.

Cadmium 22.

Calcium 23.

Chromium 24.

Copper 25.

Beryllium 26.

Iron 27.

Lead 28.

Magnesium 29.

Mercury 30.

Nickel 31.

Potassium

'2.

Sodium 33.

Zinc 34.

Phenols 35.

Vanadium 36.

Silica 37.

Radioactivity (gross alpha,

beta, gamma and t samples only 38.

Alkyl Benzene Sulfonate (ABS) 39.

Arsenic ritium) lake Mater Chemistry Survey A water quality survey shall be conducted at two sampling stations in the vicinity of the station.

One Station shall be located in approximately 45 feet of water and the other in 25 feet of water.

Both sampling stations shall be located off the Nine Hile Point promontory between the Nine Mile Point and FitzPatrick Stations.

The data collected will be used to supplement data collected during previous surveys.

These surveys will also be conducted in such a

manner as to provide support for and complement the biological programs.

4.1.2 - Continued

'0.

Barium 41.

Carbon Chloroform Extract Residue (CCE) 42.

Cyani de 43.

Fluoride 44.

manganese 45.

Selenium 46.

Si 1 ver 47.

Ferro 5 Ferricynide 48.

Turbidity Sample results will be reviewed early in 1974.

The need for continued surveillance and analysis of each parameter shall be evaluated at this time.

P 42.

Lake Temperature Structure l<eekly surveys shall be conducted from April through November for one (1) year to determine the temperature structure offshore of the site.

Temperature measurements shall be made in 100 ft.

of water from surface to bottom in 1 meter increments offshore of the site and at the east and west control sites.

BASES The measurements will provide data to determine the extent of stratification that occurs and whether or not it is a seasonally stable condition.

43

4.2

4. 2.1 Physical Aquatic 4.2.1.A.

Thermal Plume Mapping OBEJECTI VE To determine the spatial distribution of the thermal discharge plume under varying and extreme lake and meteorological conditions during normal Station operation.

SPECIFICATION A number of temperature measurement surveys have been made since 1970 in the area of the discharge during normal Statio'n ooeration.

Surface and vertical profile measurements using a thermistor have been made from a boat traveling along several specific transects in the discharge area.

The transects and vertical profile stations have been sited using applicable standard methods.

Thermistors used have been accurate to 0.1 F.

The above studies were made during several different sets of critical lake conditions, e.g.,

high temperature, maximum lake current and low lake level.

The results of these surveys shall be evaluated by Niagara Mohawk Power Corporation and the Atomic Energy Comoission to mutually arrive at appropriate recommendations foi future surveillance of the Nine Mile Point Unit 1 thermal'ischarge.

plume in light of other activities underway and planned at the Nine Mile Point site.

BASES E

The temperature surveys show the extent of the Station's thermal discharge on the Nine Mile Point area under varying natural lake conditions.

4.3 Environmental Radiolo ical Honitorin OBJECTIVE An environmental radiological monitoring program shall be conducted to evaluate the effects of Station operation on the environs and to verify the effectiveness of the controls on radioacti ve materials sources SPECIFICATION An environmental radiological monitoring program shall be conducted as follows:

4.3.1 The envi ronmental radi ation monitoring program specified in Table 4.3 shall be conducted.

Variations from the frequency and location of samples are permitted if due to.sample un-availability or seasonal conditions.

4.3.2 Reporting requirements for the environmental radiological monitoring program are outlined in Section 5.5.

4,3.3 During the seasons that animals producing milk for human con-sumption are on pasture at locations that may.be significantly affected* by emissions from Nine Hile Point-l, samples of fresh milk shall be obtained weekly from those animals on oasture for which the milk chain dose has been calculated to exceed 1 mrem/year and analyzed for their radioiodine content, calculated as I-131.

Analysis shall be carried out within eight days (one I-131 half-life) 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, overall error (one sigma confidence level) of the analysis shall be within + 25 percent.

Results shall be reported with associated calculated error, as picocuries of I-131 per liter of milk at the time of sampling, in accordance with Reporting Requirements for Envi ronmental Radi ologi cal Honi toring.

Special attention shall be paid to those locations where milk is produced for direct consumption by humans; e.g.,

the family farm.

4.3.4 A census shall be conducted twice annually, (during the beginning and midpoint of the grazing season) to determine the location of'ows in potentially affected areas.

Ifit is learned via the census that:there are a considerable number of additional locations where milk is produced in the vicinity of the Station, location(s) may be chosen which may serve as valid indicator(s) of other locations in that meteorological

sector, rather than sampling every location.

For the purpose of this requirement, "Significantly affected" means that calculations, using standard AEC staff assumptions, predict that a two year old child drinking milk produced by animals at that location, may receive a thyroid dose of 1 mrem/year or greater.

TABLE 4.3 SAMPLE 'COLLECTION AND ANALYSIS SITE RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM A.

LAKE PROGRAM(l )

MEDIA ANALYSIS

~RBRUENCY~

LOCATIONS (2) 1; Fish 2.

Mollusks Garanarus 4.

Bottom Sediments 5.

Periphyton 6.

Lake Water

GeLi, B Sr Sr GeLi, BgSr 5 Sr

GeLi, B Sr 8 gOSr C~Li, @Sr.

8 'OSr GeLi GB, GSA3 or GeLi

~

H 3/yr 3/yr 3/yr 3/yr 3/yr M Comp.

Qtr.

Corno.

2 onsite 2 onsite 2 onsite 2 onsite

2. onsste 3(3) 1 offsite 1 offsite 1 offsite 1 offsite 1 offsite Notes:

'1)

Program continued for at least three years after the startup.of James A. FitzPatrick Nuclear Power Plant.

(2 Onsite locations samples collected in the vicinity of discharqes, offsite samples collected at a distance of at least five miles from site.

(3)

The three lake water samples to include Nine Mile Point Unit 1 intake water, James A. FitzPatrick intake water, and Oswego City water.

(4)

Samples of items 1 through 5 collected in spring, summer and fall when available.

(5)

GeLi analysis will have a

MDL of 3 times o of backqround based on a 400 minute count on a 55 cc GeLi system..

96

p

~

TABLE 4.3 (Cont'd)

SAMPLE COLLECTION AND ANALYSIS SITE RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM B.

LAND PROGRAM(>>

MEDIA 1.

Air Par ticul ates 2.

Precipitation 3.

TLD 4.

Radi ation Monitors 5.

Airborne - I131 6.

Mi 1 k 7.

Pasture Grass Human Food Crops 9.

Soil Notes:

(Conttnved)

ANALYSIS GB GSA GB GSA Gamma Dose Gamma Dose GSA I,

GSA, Sr GSA GSA, 90Sr

GSA, Sr FREIRUENCY W

M Comp.<<>

C W

W M Comp.

M(7)

NO.

OF LOCATIONS At least 10 At least 10 10 At least 10 4(7) 4(7) 9 onsite 6 offsite 14 onsite 6 offsite 9 onsite 9 onsite (8) 1 offsite 6 offsite (8)

(8)

LOCATIONS 9 onsite 6 offsite (6)

Onsite samples counted together, offsite counted together, (7)

Frequency applied only during grazing season.

(8)

Samples to be collected from farms within a 10-mile radius of radionuclides.

any high count samples counted separetely.

havinq the highest potential concentrations Abbrevi ati ons:

M Comp. - Monthly composite of weekly or bi-weekly samples GB - Gross beta analysis GeLi Gamma spectral analysis on' GeLi system (quantitative)

GSA Gamma spectral analysis on a NaI system (quanti tati ve)

A - Annually W - Weekly M Monthly C

Continuous I

BW - Bi-weekly (alternate wks.)

gtr. - quarterly SA - Semiannually

P~

BASES The Monitoring Requirements given under 2.3.A and 2.3.8 provide assurance that liquid and gaseous wastes are properly controlled and monitored during releases of radioactive materials in liquid and gaseous effluents.

These Monitorinq Requirem.o.nts provide data for the licensee and the Commission to evaluate the S.ation's performance relat':ve to radioactive liquid and gaseous wastes rele'ased to the environment.

Reports on the quantities of radioactive materials released in liquid and gaseous effluents shall be furnished to the Cormission on the basis of Section 5.5.

On the basis of such reports, and any additional information the C'ommission 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 appropri ate.

'The number and distribution of sampling locations and the various types of measurements described in Table 4.3 together with the'pre'operational background data, will provide verification of the 'effectiveness of Station effluent control and indication of measurable changes in the activity of the environment.

A concentration of I-131 in milk of 2.4 picocuries ner liter will res'ult in a dose to the thyroid of a 0-2 year old child of 15 mrem/year, based upon consumption of one liter per day for the year.

To assure that no child will receive a dose of greater than 15 mrem/year to the thyroid, it is necessary to know the radi oi odi ne concentration in the milk to the sensi tivity gi ven above,

0. 5 pCi /1 iter.

5.0 Administrati ve Controls OBJECTIVE Administrative controls for implementation of the Environm ntal Technical Specifications are the means by which environmental protection is subject to Station management control and independent review and audit.

These measures ensure that the Environmental Technical Specifications will be properly impl emented.

5.1 Or anization and Res onsibilit 5,1.1 The Station organization and its relationship to the site organization is shown in Figure 5.1.1-1.

The structure of corporate responsibility is shown in Fiaure 5.1.1-2.

5.1.2 The General Superintendent shall have direct responsibility for assuring that operation of all generating units at the site is.

conducted in such a manner as to provide continuing protection to the environment.

During periods when the General Superintendent is unavailable, he may delegate his responsibilities to either the Station Superintendent Nine tiile Point Nuclear Station or the Plant Superintendent James A. FitzPatrick Nuclear Power Plant.

5.1.3 Operation of the Station so as to implement the Environmental Technical Specifications. is the responsibility of the Station Superintendent with the assistance of the Station staff organization.

5.1.4 Environmental monitoring will be'performed by site technical personnel and when requested by environmental consultant personnel.

Enqineers from the corporate staff will be available for technical assistance when required.

5.2 Review and Audit 5.2.1 Units for review and audit of environmental matters shall be orqanized as shown in Figure 5.2.1.. In addition to the regular members of the Site Operations Review Committee, a responsible supervisor from each consultant organization performing environmental monitoring shall participate in Committee meetings as required.

5.2.2 The responsibilities and authorities'of the environmental review and audi t uni ts are shown i n Tab 1 e 5.2. 2'.

5.3 Action to be Taken if a Protection Limit or Report Level is Exceeded 5.3.1 Corrective action as permitted by the technical specifications shall be promptly initiated to bring the Station and its effects'ithin the appropriate specified limits.

Exceeding a protection limit or reoort level shall be promptly reviewed as specified in Section 5.2.

49

GENERAL SUPE BINTENDENT NUCLEAR OK%RATION NiINE MILE POINT NUCLEAR STATIQl ASSISTANTS TO TllE SUPERINmiDENT AS REQUIRED JA~M A. FITZPATRICK NUCLEAR POWER PLANT STATIQl SUPERINIENDEVf TRAINING SUPERVISOR PLAIT SUPERINfENDENT MAINTENANCE SUPERVISOR RESULTS SUPERVISOR OPFICE i'ENAiCE R)RElihi B ASSISTANT INSTRlDlEhT 4 CO!iTROL SUPERVISOR ASS ISTAliT RADIOGlP'ISTRY B RADIATIQl PROTECfION SUPERVISOR INSTRlÃmNT G CONTROl.

SUPERVlSOR REACTOR AlALYST.

SUPERVISOR ASS ISTATf REACIOR jWALYST:

SUPP-RVISOR RADIOCHEMISTRY AND RADIATION PROTECfIQi SUPERVISOR MAINTENANCE FOREMAI B ASSISTANT INSTRIDlENf fi CONTROL SUPERVISOR ASSISTANT RADIOCHEMISTRY fi RADIATICN PROTECflQN SUPERVISOR ASSISTANT TO THE SUPERI! TENDENT FOR OPERATION TEClCIICIAliS AS REQUIRED TEQMCIANS AS, REQUI RED TECHNICIANS AS REQUIRED

'SSISTANT TO %K SUPERINTEÃDEVf FOR OPERATION 5-STATION SHIFT SUPERVISOR

<<4-SHIFf OPERATING FORFilAI

~1-RELIEF OPERATOR R

4-AUXILIARY OPERATOR E-N

<<I-RELIEF OPERATOR P 4-AUXILIARYOPERATOR C-N I-RELIEF OPERATOR K 4-AUXIDIARY OPERATOR B I-RELIEF OPERATOR B issued ~7I Revised 6-21-73 MECHWICS AiD ELECTRICIANS AS REQUIRED

<<'enior Operator License

Operator License Tho normal station shift conplenent shall consist of at least five persons, including ono liconsod Senior Reactor Operator and two licensed Reactor Operators.

FIGURE 5.1.1-1 liHP-JAF NUCLEAR SITE OPERATION ORGANIZATICN

~

5-STATION SHI Ff SUPERVISOR

<<4-SHIFT OPERATING

<<1-RELIEF OPERATOR R

<<4-AUXILIARYOPERATOR E N

<<I-RELIEF OPERATOR P

4-AUXILIARYOPERATOR C-N I-RELIEF OPERATOR K 4-AUXILIARYOPERATOR B I-RELIEF OPERATOR B 50

Figure 5.1.1-2 Nine Mile Point Nuclear Station Management Or anization Chart President Executive Vice President-Engineering, Operations and Employee Relations Vice President and General blanager Central Division

'Vice President-Elect'ric Operations General Superintendent Nuclear Generation Station Superintendent Nine Mile Point lied 6-3D71 Revised 6-2t 73

Executive Vice President Engineering, Operations and Employee Relations (NMPC)

Vice President

- Engineering NhlPC)

Vice President

- Electric Operations (NMPC) axe ngxneer PASTY I

I I

i I

I l

t I

SArETY REVIEw r, AUDIT BOARD SITE OPERKl'IONS REVIE'h'OMMITTEE Staff Tcchnical Assistance Other Consultants As Re uired Staff Engineer or Manager -

Chm General Superintendent Nuclear Generation Staff Engineer Nuclear Staff Engineer Mech. or Electrical

,Staff Engineer - Environmental Consultant" PASNY Princi al Nuclear Engineer General Superintendent Nuclear Gen.

Chm Plant Superintendent

- FitzPatrick Plant Station Superintendent

- NMPNS Results Supervisor Reactor Analyst Supervisor Radiochemistry and Radiation Protector Supervisor Instrument P< Control Supervisor Maintenance Supervisor PASNY Resident Engineer

At least one technical member from outside Niagara Mohawk Power Corporation organization for the first few years of Station Operation rrGvRE 5.2-1 SAFETY ORGANIZATION NINE MILE POINT - JAhKS A. FITZPATRICK SITE l~~md~7l Rcvtscd 6-21-73 52

ls"

TABLE 5.2.2 RESPONSIBILITIES ND AUTHORITY FOR ENVIRONMENTAL REVIE>l ORGANIZATION Site 0 erations Review Committee RES PONS IBILITIES Safet Review and Audit Board Vice President-Engineering Vice President-Electric 0 erations Review resul ts of environmental monitoring programs, prior to sub-mittal in each semiannual environ-mental moni toring report.

Review proposed changes to the en-vironmental technical speci fications and the evaluated impact of the change.

Review proposed environmental techni cal speci ficati on chanaes or license amendments.

Submi t analysis to the Vice President-Engineering and Vice President-Electric Operations for the sub-mittal to the AEC.

The function of the Vice=President-Engineering and the Vice President-Electric Ooerations are identical for environmental matters with those described for safety in the Technical Specifications of Appendix A.

Review proposed changes or. m'odifi-cations to the station systems or equipment and the evaluated impact whi ch would require a change in the

. procedures or which woul'd affect the evaluation of the station's envir'on-'ental.

impact.

Review the environmental technical speci ficati on development wi th the safety technical specifications to avoid conflicts and. for cons istency.

Review all proposed procedures or changes which as determined by the station Superintendent may affect the station's environmental

.impact.

TABLE 5.2.2 Cont'd)

Site 0 erations Review Committee Investigate all reported violations of environmental technical speci ficati ons.

Where the investigation indicates, prepare and forward a report covering their evaluation and recommendation to prevent recurrence, to the General Superintendent Nuclear Generation, and the Chairman of the Safety Review and Audit Board.

AUTHORITY Safet

= Review and Audit Board Review violations of environmental technical specifications and submit an analysis to the Vice President-Engineering and the Vi ce Pres i dent-El ectri c Ooerati ons.

Vice President-Engineering Vice President-Electric Operations Advisory to the Cwneral Superintendent

- Nuclear Generation.

Hake tentative determinations as to whether or not proposals submitted to the committee involve a change in the station's environmental impact.

This determination subject to review by the Safety Review hnd Audit Board.

RECORDS The Board shall report to and advise the Vi ce Presi dent-Enqineering and the Vice President-Electric Operations in all.matters rel'atinq to environmental impact.

Separate minutes shall be kept of all meetings of the SORC when convened for review of environmental matters.

Copies shall be sent to the General Superintendent Nuclear Generation and to the Chairman of the Safety Review and Audit Board.

Site 0 erations Review Committee HEHBERSHIP The membership of the Site Operations Review Committee and the Safety Revi.ew and Audit Board shall be as shown in Figure 5.2.1-.1.

HEETING FRE

UENCY, UORUH The meeting frequency and. quorum requirements shall be identical with those listed in Figure-6.1.4 of Appendix A.

TABLE 5.2.2 (Cont'd)

Safet Review and Audit Board

\\f Vice Presi dent-Engineering Vice President-Electric 0 erations k

55

5. 3.2 As s peci fied i n Section 5.5. 2, a separate report for each occurrence shall be prepared and submitted to the Directorate of Licensing.

This report shall include an evaluation of the cause of the occurrence, a record of the corrective action taken, and recommendations for appropriate action to prevent or reduce the probability of a recurrence, 5.4 0 eratin Procedures 5.4.1 Detailed written procedures, includinq applicable checkoff lists and instructions, shall be prepared, approved as speci fied in Se cti on 5.4. 2 and adhered to for operation of al 1 systems and components involved in carrying out the environmental monitorinq program.

Procedures shall include sampling, instrument calibration,

analysis, and actions to be taken when protection limits or reoort levels are approached or exceeded.

Calibration frequencies for instruments used in performing the measurements required by the environmental technical specifications shall be included.

Testinq frequency of any alarms shall be included.

These frequencies shall be determined from experience with similar instruments in similar envi ronments and from manufacturers'echnical manuals.

5.4.2 Prior to implementation, all procedures described in 5.4.1

above, and changes

hereto, shall be reviewed as provided in Section 5.2 and approved by the Station Superintendent.

Temporary changes to procedures which do not change the intent of the oriqinal procedure

,may be made, provided such changes are approved by the Station Superintendent and one of the following Supervisors:

Assistant Radiochemistry and Radiation Protection Supervisor, Radiochemistry and Radiation Protection Supervisor, or Result Suoervisor.

Such changes shall be documented, subsequently reviewed as provided in Section 5.2 and approved on a timely basis.

5.5 Station Re ortin Re uirements 5.5.1 Semi-Annual Re orts A Semi-Annual Environmental ttonitoring Report covering the previous six months'perations shall be submitted within 60 days after January 1

and July 1 of each year.

In the event that some results are not available within the 60-day period, the report shall be submitted noting and explaining the reasons for.the missinq results.

The missing data shall be submitted as soon as possible in a supple-mentary report; In addition, results of all radiological samoles taken shall be summarized on a quarterly basis following the format of Table 5.5.1 for inclusion in the semi-annual report.

These reports shall include the'following:

a.

Records of monitoring the required surveys and samples.

b.

Analysis of environmental data.

c.

Records of changes in survey procedures.

d.

Records of any special environmental studies not required by the environmental technical specifications.

e.

Records of changes as described in Section 5.5.2.2.1 and 5.5.2.2.2.

TABLE 5.5.1 REPORTING OF RADIOACTIVITY IN THE ENVIRONS Sam le Locati on-(1)

External Radiation (2)

Fi 1 terable Airborne

a. Particulate Filters 1) 2)

etc.

b.

Charcoal Filters 1) 2)

etc.

(3) llater4~

a.

b.

etc.

(4)

Food (Human}

a.

b.

etc.

(5)

Other Media

. a. Vegetation (include pasture and other animal foodstuffs)

b. Soil s

c. Sediments d.

Fish

e. Mollusks

f. Plankton

g. Algae

h. etc.

Facility Nine Mile Point Unit 1

Sam le Results Docket No.

50-220 Average guarterl

)esults

~

Frequency and '

pe of Samoles Reporting Period Analysis Results2~

nucl i de or enti t )

dl Remarks

TABLE 5.5.1 Cont'd 1/ Explain any unusual measurements or deviation from sampling schedule.

2/

Use the follouing units; external radiation, mrem quarter; filterable airborne, water and milk, uCi/ml; soil, uCi/m (specify depth);precipitation,uCi/m; strean sediments and terrestrial and aquatic vegetation, pCi/'dry gm, otner media, specify units.

3/ Specify location and its distance and direction from the facility, and indicate which is used for background.

4/ Indicate whether precipitation, surface, ground, lake, river, ocean, etc.; soecify drinking water.

5/ Use separate table for each quarter.

6/ Type of sample means either grab, continuous, proportional, composite, etc.

~ a

If statistically significant variations of offsite environmental radionuclide concentrations are observed, a comparison of these results with effluent releases wi 11 be provided.

Individual samples which show higher than normal levels (25 percent above background for external dose, or twice background for radio-nuclide content) should be noted in the reports.

5.5.2 Won-Routine Re orts 5.5.2.1 Violations In the event that a protection limit or a report level is

exceeded, or other violations of the Technical Specifications

occur, a report shall be made within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months by telephone and telegraph* to the Director of the Regional Regulatory Operations Office, followed by a written report within 10 days to the Directorate of Licensing with a copy to the Director of the Regional Regulatory Operations Offices.

To the extent possible, the written report and the pre-liminary telephone and telegraph report, should:

(a)

describe, analyze

'and evaluate implications, (b) determine the cause of the occurrence and (c) indicate the corrective action (including any significant changes made in the procedures) taken to preclude repetition of the occurrence an'd to prevent similar occurrences involving similar components or systems.

The following conditions will be considered as violations unless otherwise specified by a particular specification:

a.

Tne occurrence of any condition in violation of an Environmental Tecnni'cal Specification.

b. If levels of Iodine-131 in the air-milk pathway indicate that the resultant annual dose to an individual from these levels could equal or exceed 120 mrem, a plan will be submitted within one week advisinq tne AEC of the proposed action to ensure the plant;related annual doses wi 11 be within the design objective of 15 mrem/yr.

For example, with an I-131 design objective. of 15 mrem/yr to the thyroid of any individual, if individual milk samples snow I-131 concentrations of 19 pCi/1 or greater, the results will be reported along with a proposed plan of action, as discussed above.

"Telegraph notification may be sent on -the next working day in the event of a violation during a weekend or holiday period.

c. If samples of the air-milk environmental pathway' collected over a calendar quarter show levels of I-131 that could result in accumulated Station-related doses to the thyroid of an individual of 7.5 mrem for that quarter, the results shall be reported and a

plan submitted and implemented within 30'days to limit conditions so that the annual dose.to the thyroid of an individual will not exceed 15 mrem.

5.5.2.2

~Chan ee 5.5.2.2.1 When a change to.the Station (that affects the environmental impact evaluation contained in the Environmental Report or the Environmental Statement}

or to the environmental monitoring procedures or equipment is planned, a report of the change shall be submitted to the AEC for information prior to implementation of the change.

This is not intended to preclude making changes on short notice that are significant in terms of decreasing adverse environmental impact, etc.

However, these changes will be promptly renorted.

The report will include an evaluation of the imnact of the chanqe.

5.5.2.2..2 Changes or addi.tions to permits a'nd 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 aaency for

approval, they Hill also be submitted to the Deouty Director for Reactor Projects, "Directorate of Licensing, USAEC, for information, The submittal should include an evaluation of.the environmental impact associated with the chanae.

5.5.2.2.3 Request for changes in E'nvironmental Technical Speci fications shall be submitted to the Deputy, Director of Reactor

Projects, Directorate.of Licensing, USAEC, for prior review and authorization.

The request will include an evaluation of the envi ronmental impact associated with the change.

5.6 Rec'ords Retention 5.6.1 Records and logs relative to specifications contained in Section 5.0 of the Environmental Technical Specifications shall be retained for five years except as described in 5.6.2.

5.6.2 All records and logs relative to the following areas shall be retained for the life of the Station:

a.

Records and drawing changes reflecting Station design modifications made to systems and equipment as described in Section 5.5.2. 2.

b.

Records of environmental monitoring data.

o. 0 REFERENCES 1.

New York State Department of Health Permit to Discharge Sewage or ~lastes into the llaters of the State, issued to Niagara flohawk Power Corporation for the Nine Nile Point Nuclear Power Station on April 28, 1965.

This Permit is presented as Item 5 of Appendix G in the Nine Nile Point Nuclear Station Unit 1 Environmental Report.

2.

Nine Nile Point Nuclear Station Unit 1 Environmental

Report, Sections 5.1.3,

5. 5.1-5". 5. 4, 9. 5.1.2. 2 3.

Nine Nile Point Nuclear Power Station Unit 2, Effect of Circulatin( Hater Systems on Lake Ontario Hater Temperature and Aquatic Biology, Volume I.

Regulatory

ML18018B059

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