ML17053D589

Amend 51 to License DPR-63,deleting App B ETS Nonradiological Water quality-related Requirements

ML17053D589
Person / Time
Site:	Nine Mile Point
Issue date:	03/11/1983
From:	Vassallo D Office of Nuclear Reactor Regulation
To:	Niagara Mohawk Power Corp
Shared Package
ML17053D590	List: ML17053D589 ML17053D591
References
DPR-63-A-051 NUDOCS 8303290030
Download: ML17053D589 (88)

Text

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UNITEDSTATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 NIAGARA MOHAWK POWER CORPORATION DOCKET NO. 50-220 NINE tIILE POINT NUCLEAR STATIOt~'NIT NO.

1 AMENDMENT TO FACILITY OPERATING LICENSE.

Amendment No.

51 License No.

DPR-63 1

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The Nuclear Regulatory Commission (the Commission) has found that:

A.

The application for amendment by the Niagra Mohawk Power Corporation (the licensee) dated February 10, 1983, complies with the standards and requirements: of the Atomic Energy Act of 1954, as amended (the Act) and the Commission's rules and regulations set forth in 10 CFR Chapter.I; B.

The'facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.

There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D.

The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.

The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.

8303290030 83031 k PDR ADOCK 05000220 P

PDR

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2 2.

Accordingly, tPe license is amended by deleting paragraphs 2.D. (2) and 2.0.(3) and by changes to the Technical Specifications as indicated in the attachment to this license amendment.

Paragraph 2.C.(2) of Facility Operating License No.

DPR-63 is hereby amended to read as follows:

(2) Technical S ecifications I

The Technical Specifications contained in Appendices A and B., as revised through Amendment No. 51, are hereby incorporated in the license.

The licepsee shall operate the facility in accordance with the Technical Specifications.

3.

This license amendment is effective as of the date of its issuance.

FOR THE NUCLE R

REGULATORY COMMISSION

Attachment:

Changes to the Technical Specifications Date of Issuance:

March 11, 1983 Domenic B. Vassal lo, Chief Operating Reactors Branch g2 Division of Licensing

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ATTACHMENT TO LICENSE AMENDMENT N0.~1 FACILITY OPERATING LICENSE NO. DPR-63 DOCKET NO. 50-220 Replace the Appendix B Technical Specifications with the enclosed completely revised Appendix B Technical Specifications.

ENVIRONMENTAL TECHNICAL SPECIFICATIONS APPENOIX S

TO FACILITY OPERATING LICENSE NO.

OPR-63 FOR NINE MILE POINT NUCLEAR STATION UNIT 1

NIAGARA MOHAWK POWER CORPORATiON OOCKET NO. 50-220 COMPLETE REVISION Amendment Ho.

51

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TABLE OF CONTENTS Table of Contents.

List of Tables Pacae

1. 0 OEF INIT IONS 1.1 1.2 1.3 1.4 1.5 1.6 Reactor Operating Conditions Major Refueling Outage Operating Cycle Equipment Status Instrument Test Procedures Prior to Oilution 2.0 LIMITING CONG IT'IONS FOR OPERATION 2.1 Radi oacti ve 'Oi scharges 2.1.1 2.1. 2

'2 1.3 2.1. 4 Specifications Speci ficat ions Monitoring Specifications Specifications Monitoring for Liquid Waste Effluents for Liquid Waste Sampling and for Gaseous Waste Effluents for Gaseous Waste Sampling and 5ll l

2.1. 5 Specifications for Solid Waste Handling and Oisposal 23 3.0 ENVIRONMENTAL SURVEILLANCE 3.1 Meteorological Monitoring

. 3.2 Radiological Environmental Monitoring

4. 0 ADMINISTRATIVE CONTROLS 24'4 27 31 4.1 4.2 4.3 4.4 4.6 Responsibility Organization r

Review and Audit Action to be Taken if a Limiting Condition for Operation is Exceeded Procedures Plant Reporting Requirements 4.6.1 Routine'eports 4.6.2 Nonroutine Reports 4.6.3 Changes in Environmental Technical Specifications 31 31 31 32 32 33 33 33 38 l.

'4.7 Records Retention 38 Amendment No. Sl

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LIST OF TABLES Table 2.1-1 2.1-2 2.1-3 2.1-4 3.1-1 3.1-2 3.'2-1 4.6-1 Title Radioactive Liquid Sampling and Analysis Location of Process and Effluent Monitors and Samplers Required by Technical Specifications Average Energy Per Oisintegration Radioactive Gaseous Waste Sampling and Analysis Meteorological Measurement Meteorological Oata Format Sample Collection and Analysis - Site Radiological Environmental. Monitoring Program Radiological Environmental Monitoring Program Report 7

12 17 25 26 28 34 Amendment No.

51

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1. 0 OEF INITIONS

l. 1 Reactor 0 eratin Conditi'ons a.,

Power 0 eratin Condition (1)

Reactor mode switch is in startup pr.run position.

(2)

Reactor is critical or criticality is possible due to control rod withdrawal.

b. 'ormal Station 0 eration Normal operation is with the reactor critical and above one percent rated power and in conformance with the requirements of the Technical Specifications.

c.

Hot Shutdown Condition (1)

(2)

(3)

The reactor mode" switch is in the shutdown position.

No core alterations leading to an addition of reactivity are being performed.

Reactor coolant temperature is greater than 212F.

1.2 Ma'or Refuelin Outa e

I For the purpose of designating frequency of testing and surveillance, a

major refueling outage shall mean a regularly scheduled refueling outage;

however, where such outages occur within 8 months of the end of the previous refueling outage, the test or surveillance need not be performed until.the next regularly scheduled outage.

1.3 ~0i C

An operating cycle is that portion of Station operation between reactor startups following each major refueling outage.

~M<<

a.

~0erabl e A system or component shall be considered operable when it is capable of performing its intended function in its 'required manner.

b.

~0eratln Operating means that a system or component is performing its required'functions in its required manner.

Amendment No.

51

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1.5 Instrument Test Procedures a.

Instrument Channel Calibration Instrument channel calibration means adjustment of channel output such that it resonds, with acceptable range and accuracy, to known values of the parameter which the channel measures.

Calibration shall encompass the entire channel including equipment actuation, alarm, or trip.

b.

Instrument Channel Test Instrument channel test means injection of a simulated signal into the channel to verify its proper response including, where applicable, alarm and/or trip initiating action.

c.'ensor Check A sensor check is qualitative determination of acceptable operability by observation of sensor behavior during operation.

This determination shall include, where possible, comparison of the sensor with other independent sensors measuring the same variable, 4

1.6 Prior to Oilution Liquid effluent concentrations prior to dilution are concentrations in the circulating water discharge tunnel, prior to dilution in Lake Ontario.

Amendment No.

51

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2.0 LIMITING CONOITIONS FOR OPERATION 2.1 Radioactive Oischarges OBJECTIVE To define the limits and conditions for the controlled release of radioactive materials in 1iquid and gaseous effluents to the environs to ensure that these releases are as low as reasonably achievable.

The release rate for all effluent discharges shall be uithin the limits specified in 10 CFR Part 20.

I To ensure that the releases of radioactive material above background to unrestricted areas wi 11 be as low as reasonably achievable as defined in Appendix I to 10 CFR Part 50, the following design objectives apply:

For liquid wastes:

a.

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

b.

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

gases, discharged from each reactor should not exceed 5 Ci.

For gaseous wastes:

c.

The annual total quantity of noble gases above background discharged from the site should result in an air dose due to gamma radiation of less than 10 mrad, and an air dose due to beta radiation of less than 20 mrad, at any location near ground level which could be occupied by individuals at or beyond the boundary of the site.

d.

The annual total quantity of all radioiodines and radioactive material in particulate forms above background from all reactors at

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a site should not result in an annual dose to any organ of an individual in an unrestricted area from all pathways of exposure in excess of 15 mrem.

I e.

The annual total quantity of iodine-131 discharged from each reactor at a site should not exceed

1. Ci.

Amendment Ho.

51

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2.1.1 SPECIFICATIONS FOR LI UID WASTE EFFLUENTS a.

The concentration of radioactive materials released in liquid wastes from all reactors at the site shall not exceed the values

.specified in 10 CFR Part 20, Appendix B, Table II, Column 2, for unrestricted areas.

b.

The cumulative release of radioactive materials in liquid waste effluents, excluding tritium and dissolved

gases, shall not exceed 10 Ci/reactor/calendar quarter.

c.

The cumulative release of radioactive materials in liquid waste effluents, excluding tritium and dissolved

gases, shall not exceed 20 Ci/reactor in any 12 consecutive months.

d ~

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 Specification 2.1.1.a.

e.

g, h.

If Specification 2.l.l.d cannot be met, continued release of liquid effluents shall be permitted only during the succeeding 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> period.

Two independent samples of each tank shall be analyzed and two Station personnel shall independently check valving prior to d'ischarge.

The equipment installed in the liquid radioactive waste system shall be maintained and shall be operated to process radioactive liquid wastes prior to their discharge when the projected cumulative release could exceed 1.25 Ci/reactor/calendar

quarter, excluding tritium and dissolved gases.

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

If the cumulative release of radioactive.materials in.liquid effluents, excluding tritium and dissolved

gases, exceeds 2.5 Ci/reactor/calendar

quarter, the licensee shall'make an investigation to identify the causes of such release

rates, define and initiate a program of action to reduce such releases to the design objective levels listed in Section

2. 1, and report these actions to the Commission within 30 days from the end of the quarter during which the release occurred.

Amendment No.

51

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2.1.2 SPECIFICATIONS FOR LIOUIO WASTE SAMPLING ANO MONITORING a.

Plant records shall'e maintained of, the radioactive concentration and volume before dilution of liquid waste intended for discharge, and the average dilution flow and length of time over which each discharge occurred.

Sample analysis results and other reports shall be submitted in accordance with Section 4.6.

1 of these specifications.

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

b.

Prior to release of each batch of liquid waste, a sample shall be taken from that batch and analyzed for the concentration of each significant galena energy peak in accordance with Table

2. 1-1 to demonstrate compliance with Specification 2.1.1 using the flow rate of the stream into which the waste is discharged during the period of discharge.

,k c.

Sampling and analysis of liquid radioactive waste shall be

'erformed in accordance with Table 2.1-1.

Prior to taking samples, at least two tank volumes of entrained fluid shall be recirculated through the mixing nozzles.

d.

The radioactivity in liquid wastes shall be continuously monitored during release.

Whenever the monitor is inoperable for a period not to exceed 72 h'ours, two independent samples of each tank to be discharged shall be analyzedwnd-two plant personnel shall independently check valving prior to the discharge.

If the monitor is inoperable for a period exceeding 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, no release from a liquid waste tank shall be made and any release in progress shall be terminated.

e.

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

f.

The liquid effluent radiation monitor shall be calibrated at least quarterly by means of a radioactive source which has been calibrated to a National Hureau of Standards source.

Each monitor shall also have an instrument channel test monthly and a sensor check prior to making a release.

g.

The location of process and effluent monitors and samples shall be

. as stated in Tabl.e 2.1-2.

REPORTING RE UIREMENTS Exceeding limiting conditions for operation contained in this section shall be reported on the prompt schedule.

amendment No.

51

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TABLE 2.1-1 RADIOACTIVE LI UID SAMPLING AND ANALYSIS Liquid Source Sampling Fre uenc Type of Activit Anal sis Detecta e

Concentrations uCi/ml (>>

'a.

Haste Tank Releases Each Batch 1.

I-131

-6 1.

10

-7 (2) 2.

Principal Gamna Emitters (Ba-La-2.

5 x 10 140

. B.

Primar Coolant One Batch/Month Monthly Composite(1)

Heekl (4) 1.

Dissolved Gases 1.

H-3 2.

Gross al ha 3.

Sr 89 90 1.

I-131 I-l)3

-5 1.

10 1.

10

-7 2.

10

-8 3.

5 x.10 1.

10 NOTES FOR TABLE 2.1-1 1.

A composite sample shall be formed by mixing together individual samples, each of which is proportional,in volume to the volume of liquid discharge during the period represented by the sample.,

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2.

For certain mixtures of gamna emitters, it may not be possible to measure radionuclides in concentrations near their sensitivity limits when other 'nuclides are present in the sample in much greater 'concentrations.

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

3.

The detectability limits for activity analysis are based on technical feasibility and on the potential significance'in the environment of the quantities released.

For some nuclides, lower detection limits may be readily achievable.and when nucli des are measured below the stated limits, they should also be reported.

4.

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

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TABLE 2.1-2 Nine Mile Point Unit 1 Liquid Waste System Location of Process and Effluent Monitors and Samplers Required By Technical Specifications Process Stream or Release Point AIarm Auto-Control to Isolation Valve Continuous Monitor Measurements Grab Sample Gross Dissol ved Isotopic Station

~Activit I

Gases

~A1 ha

~3

~Anal sis High purity waste

- sample (test) tank*

~ Fl oor drain waste sample (test) tank Chemical waste sample (test) tank (a)

(a)

(a)

X' X

X X

X X

X X

X X

X X

X

'Detergent waste collector tank**

'I Primary coolant system Liquid radwaste

. discharge pipe Service water discharge pipe

-Emergency cooling system vent

. Nuclear closed

cooling system s

(a)

(b)

(c)

(c)

(c)

(c)

X I

X X

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X X

X X

X X.

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NOTES TO TABLE 2.1-2 (a)

High liquid level alarms are provided'for these tanks.

(b)

A conductivity alarm is provided for this system.

(c)

Radiation alarms are provided for these locations.

In some BWR's the High Purity Waste Storage may not have a waste sample (test) tank.

The processed liquid will be routed directly to the condensate storage tank or to the floor drain waste sample (test) tank.

In most BWR's the contents of the detergent waste collector tank are sampled, analyzed

• and then filtered prior to release through the liquid radwaste discharge pipe.

The detergent waste system must be designed with either a split tank or two separate collection or sample (test) tanks to permit isolation of the tanks for mixIng, sampling and analysis prior to release.

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BASES FOR LI UIO WASTE SPECIFICATIONS The release of radioactive materials in liquid waste effluents to unrestricted areas shall not exceed the concentration limits specified in 10 CFR Part 20 and should be as low as reasonably achievable in accordance with the requirements.of 10 CFR Part 50.36a.

These Specifications provide reasonable assurance that the resulting annual dose to the total body or any organ of an individual in an unrestricted area will not exceed 5 mrem.

At the same time, these Specifications permit the flexibilityof 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 Part 20.

It is expected that by'sing this operational flexibilityunder unusual operating conditions, and exerting every effort to keep levels of radioactive material in liquid waste as low as reasonably achievable, the annual releases will not exceed a small fraction of the concentration limits specified in 10 CFR Part 20.

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

leakage, and the performance of the various waste treatment

systems, and are consistent with Appendix I to 10 CFR Part 50.

Specification 2.1.1.a requires the-licensee to limit the concentration of radioactive materials in liquid waste effluents released from the site to levels specified in 10 CFR Part 20, Appendix B, Table II, Column 2, for unrestricted areas.

This Specification'rovides assurance that no member of the general public wi 11 be exposed to liquid containing radioactive materials in excess of limits considered permissible under the Commission's Rules and Regulations.

Specifications 2.1.1.b and 2.1.l.c establish the upper limits for the release of radioactive materials in liquid effluents.

The intent of these Specifications 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 plant and the liquid waste treatment systems are functioning as designed.

Releases of up to. these limits will result in concentrations of radioactive material in liquid waste effluents at small percentages of the limits specified in 10 CFR Part 20.

Specifications 2.l.l.d and

2. l.l.e require that suitable equipment to control and monitor the releases of radioactive materials in liquid wastes is operating during any period these releases are taking place consistent with the requirements of 10 CFR Part 50, Appendix A, Oesign Criterion 64.

Amendment Ho.

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BASES FOR LIOUID MASTE SPECIFICATIONS (Cont'd)

J Specification 2.1.l.f requires that the licensee maintain and operate the equipment installed in the liquid waste systems to reduce the release of radioactive materials in liquid effluents to as low as reasonably achievable consistent with the requirements of 10 CFR Part 50.36.

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

Specification 2.1.1.g limits the amount of radioactive material that could be inadvertently released to the environment to an amount that will not exceed the. Technical Specification limit.

In addition to limiting conditions for operation listed under Specification 2.1. l.b ahd

2. 1.1.c, the reporting requirements of Specification 2.l.l.h delineate that the licensee shall identify the cause whenever the cumulative release of radioactive materials in liquid waste effluents exceeds one half the design objective annual quantity during any calendar qua~ter and describe the proposed program of action to reduce such release~o

.design objective levels on a

timely basis.

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

The sampling and monitoring requirements given under Specification 2.1.2 provide assurance that radioactive materials in liquid wastes are properly controlled and monitored in conformance with the requirements

'f Oesign Criteria 60 and 64.

These requirements provide the data for the licensee and the Commission to evaluate the plant's performance relative to radioactive liquid wastes released.to the environment.

Reports on the quantities of radioactive materials released in liquid waste effluents are furnished to the Commission according to Section

4. 6.1 of these Technical Specifications in conformance with Regulatory Guide 1.21.

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

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2.1.3 SPECIFICATIONS FOR GASEOUS WASTE EFFLUENTS a.

(1)

The release rate limit of noble gases from the site shall be:

IfQ'is(1.6 Eig+0.3 Eip)+Qis(2.7 Ei~+0.5 Eip) + Qiv(11.0 Ei~+24.0 Eig)51 where Q'

s Qs Qv release rate from Nine Mile Point Unit 1 main stack in Ci/sec (as elevated release) release rate from the FitzPatrick main stack in Ci/sec (as elevated release) release rate from the FitzPatrick vents in Ci/sec (ground release) i

= the individual nuclide the average gamma energy per disintegration

= the avet age beta energy per. disintegration (2)

Refer to Table 2.1-3 for E< and Zp values to be used.

The release rate limit of all radionucl ides and radioactive materials in particulate form with half-lives greater than eight days; released to the environs as part of the gaseous wastes frort the site shall be:

/

1.2 x 10 (Q s + 0.08 Qs + 5 5 Qv) c 1 where Q'

release rate from Nine Mile Point Unit 1 main stack in Ci/sec (as elevated release)

Qs

= release rate from the FitzPatrick "main stack in Ci/sec (as'levated release)

Qv

= release r ate from the FitzPatrick vents in Ci/sec (ground release)

Amendment No.

51

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TABLE 2.1-3 AVERAGE ENERGY PER OISINTEGRATION Isoto e

Kr-83m Kr-85 Kr-85m Kr-87 Kr-88 Kr-89 Kr-90 Xe-1 31m Xe-1 33 Xe-133m Xe-135 Xe-135m Xe-137 Xe-138 Eg mev/dis 0.00248 0.0022 0.159

0. 793 1.95

2. 22 2.10 0.0201 0.0454

0. 042 0.247 0.432 0.194 1.18 Ref (1)

(1)

(1)

(1)

(2)

(2)

. (1)

(1)

(1)

(1)

(1)

(1)

(1) mev/dis

0. 0371 0: 250

0. 253 1.32

0. 377 1.37 1.01

0. 143

0. 135 0.19

'.317.

0. 095 1.64

0. 611 Ref (1)

(1)

(1)

(1)

(1)

(2)

(2)

(1)

(1)

,(1)

(1)

(1)

(1)

(1)

(1)

ORNL-4923, Radioactive Atoms - Su lement I, M. S. Martin, November 1973.

'2)

NED0-12037, "Summary of Gamma and Beta Emitters and Intensity Oata";

M. E. Meek, R. S. Gilbert, January 1970.

(The average P energy was computed from the maximum energy using the ICRP II equation, not the 1/3 value assumption used in this reference.)

(3)

The.average P energy includes conversion electrons.

Amendment No.

51 12

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2.1.3 SPECIFICATIONS FOR GASEOUS WASTE EFFLUENTS (Cont'd) b.

(1)

The average release rate of noble gases from the site during any calendar quarter shall be:

<iP I.O.g Q'is + 1." Qis + "" o Qivj-1 1

AND 4 <ig I.10-0 Q'is + 17.0 Qis + 71-0 Qivj+1 (2)

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

4~ip l.l 8 Q is + 3.4 Qis + 149 ~ 0 Qivj cl AND (3)

(4)

f. ~iM L21 0 0'is

+ 35 0 Qis

+ 142.0 Qivj -1 The average release rate from the site of all iodines and radioactive materials in particulate form with half-lives greater than eight days during any calendar quarter shall be:

1.5 x 105 (Q s + 0.08 Qs + 5.5 Qv) 4 1 The average release rate from the site of all iodines and radioactive materials in particulate form with half-lives greater than eight days during any period of 12 consecutive

- months shall be:

3.0 x 105 (Q s + 0.80 Qs

+ 5 ~ 5 Qv)-1 (5)

The amount of iodine-131 released during any calendar quarter shall not exceed 2 Ci/reactor.

(6)

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

Amendment No.

51 13

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'.1.3 SPECIFICATIONS FOR GASEOUS WASTE EFFLUENTS (Cont'd)

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

c.

Should the conditions of 2.1.3.c(l),

(2), or (3) listed below

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exist, the licensee shall make an investigation to identify the causes of the release, rates, define and initiate a program of action to reduce the release rates to design objective levels listed in Section 2.1 and report these actions to the Coranission within 30 days from the end of the quarter during which the releases occurred.

(1) 5 <18 L'3 6 0'is

+ 68 0is

+ >880 0iy3) 1 OR

[41 0 0 is + 68 0 0is

+ 310 0 0iyj )1 (2)

If the average release rate from the site of all iodines and radioactive materials in particulate form with half-lives greater than eight days during any calendar quart'er is:

5.8 x 105 (Q s

+ 0 08 gs

+ 5 5 gv) 0 1

(3)

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

Amendment No.

51

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2 1.3 SPECIFICATIONS FOR GASEOUS WASTE EFFLUENTS (Cont'd) d.

An air ejector off-gas.monitor shall be operating and set to alarm and to initiate the automatic closure of the waste gas discharge valve prior to exceeding the limits specified in 2.1.8.a above.

The operability of each automatic isolation va3ve in the gaseous radwaste discharge line shall be demonstrated quarterly.

e; If no air ejector off-gas monitor is operating, shutdown shall be initiated so that the reactor will be in the hot shutdown condition within 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br />.

f. If the release rate from the site of noble gases from the main condenser vacuum system is:

OR 4 ~iq El SQ's

+ 3 '

Qis + 14g O Qivj > 1-

f. Ei~ L'21.0 0is + 30 ~ 0 0s

+ 142.0 0iv]pl for a period of greater than 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />, the licensee shall notify the Coranission in writing within 10 days, identifying the causes of

.activity..

The,report should~elude the flow rate of the off-gas from the main condenser vacuum system, and the activity measured downstream of the main condenser vacuum system prior to holdup, and at a point upstream of the point of release.

g.

The drywell shall be purged through the standby Gas Treatment System until Specification 2.1.3 a(l) and 2.1.3 a(2) can be met using normal containment purge systems.

h.

A hydrogen monitor in the off-gas line downstream of the recombiners shall be operable during power operation.

If the hydrogen concentration reaches an alarm set point of four percent by volume, recombiner section of the Off-Gas System shall be isolated.

Whenever the hydrogen monitor is inoperable during power operation, grab samples shall be taken and analyzed for hydrogen concentration each shift.

Calibration of the monitoring system shall be performed weekly.

Amendment No.

51 T5

2.1.4 SPECIFICATIONS FOR GASEOUS WASTE SAMPLING ANO MONITORING a.

Plant records shall be maintained and reports of the sampling and analysis results shall be submitted in accordance with Section 4.6.1 of these Specifications.

'Estimates of the sampling and analytical error associated with each reported value should be included.

b.

The flow rate of Gaseous releases to the environment shall.be measured and recorded.

Gross radioactivity shall be continuously monitored.

Whenever these monitors are inoperable, grab samples shall be taken and analyzed daily for gross radioactivity.

If these monitors are inoperable for more than seven

days, these releases shall be terminated.

c.

An isotopic analysis shall be made of a representative sample of

'aseous activity downstream of the steam jet air'jectors and at the stack sample point:

(1) at least monthly (2) following each refueling outage within one week of attaining steady state power (3) if the offgas monitors indicate an increase of greater than 5(C in the steady state-fission gas release after factoring out increases due to power changes.

d.

All waste gas effluent monitors shall be calibrated at least quarterly by means of a known radioactive source which has been calibrated to a National 8ureau of Standards source.

Each monitor shall have an instrument channel test at least weekly and a sensor check at least daily.

e.

Sampling and analysis of radioactive material in gaseous.waste, particulate form, and radioiodine shall be performed in accordance with Table 2.1-4.

16 Amendment No.

51

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TABLE 2.1-4 RADIOACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS Gaseous Source A.

Drywell Atmosphere Sampling Fre uenc Each Purge Type of Activit Anal sis Princi al Garana Emitters H-3 Detectab e

CnncentratI~~s uCi/ml 3

-4 10

-6 10 l

I Cl.

I Ib O

Environmental Release Monthly Points (Gas Samples)

(2)

Weekly (Charcoal Sam le 4

Princi al Garmna Erhitters H-3 I-131 4

10

-6 10

-12 10 Weekly (Particulates)

(4) Principal Gemara Emitters at least for.Ba-La-140 I-131

-11 10 Honthly (Charcoal Sam le I-133 Monthly Composite (5)

(Parti cul ates)

Sr-89 Sr-90 Honthl Gross al ha

-ll 10

-11 10

~

4 8

~

I

NOTES FOR TABLE 2.1-4 I

1.

The detectability limits for act'ivity analysis are based on technical feasibility and on the potential significance in the environment of the quantities released.

For some nuclides, lower detection limits may be readily achievable and when nucli des are measured below the stated limits, they should also be reported.

2.

Gaana analysis shall also be performed following each refueling, startup, or similar operational occurrence which could alter the mixture of radionuclides.

j 3.

for certain mixtures of gamna emitters, it may not be possible to measure radionuclides at levels near their sensitivity limits when other nuclides are present in the sample at much higher levels.

Under these circumstances it will be more appropriate to calculate the levels of such radionuclides using observed ratios with those radionuclides which are measurable.

4.

Nhen the average daily gross radioactivity release pate exceeds that given in 2.1.3.c(1) or when the release rate is in excess of 1000 uCi/sec and steady state gross release rate increases by 50K over previous corresponding power level steady state release

rate, the iodine and particulate collection device shall be removed and analyzed to determine the change in iodine-131 and particulate release rate.

The analysis shall be done daily following such change until it is shown that a pattern exists which can be used to predict the release rate; after which it may revert to weekly sampling frequency.

5.

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

y

~

l

BASES FOR GASEOUS WASTE SPECIFICATIONS The release of radioactive materials in gaseous waste effluents to unrestricted areas shall not exceed the concentration limits specified in 10 CFR Part 20, and should be as low as reasonably achievable in accordance with the requirements of 10 CFR Part 50.36.

These Specifications provide reasonable assurance that the resulting annual air dose from the site due to gamma radiation will not exceed 10 mrad, and an annual air dose from the site due to beta radiation will not

. exceed 20 mrad from noble gases, and that the'nnual dose to any organ of an individual from iodines and particulates will not 'exceed 15 mrem per site.

At the same time these Specifications permit the flexibi1.ity of operation, compatible with considerations of health and safety, to assure that the public is provided with a dependable source of power under unusual operating conditions which may temporarily result in releases higher than the design objective levels but still within the concentration limits specified in 10 CFR Part 20.

It is expected that using this operational flexibilityunder unusual operating conditions, and by exerting every effort to keep levels of radioactive material in gaseous waste effluents as low as reasonably achiev'able, the annual releases will not exceed a small fraction of the concentration limits specified in 10 CFR Part 20.

These efforts should include consideration of meteorological conditions during releases.

There is a reduction factor of 243 by which ':he maximum permissible concentration of radioactive iodhre-in air should be reduced to allow for the grass-cow-milk pathway.

This factor has..been derived for radioactive iodine, taking into account the milk pathway.

It has been applied to radionuclides of iodine and to all radionuclides in particulate form with a half-life greater than eight days.

The factor is not appropriate for iodine where milk is not a pathway of exposure, or for the other radionuclides.

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

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

The Specification

2. 1.3.a(1) dose calculations have been made for the critical sector.

These calculations consider site meteorology, buoyancy characteristics, and radionuclide content of the effluent from Nine Mile Point Unit 1

and from the FitzPatrick Plant, Meteorological calculations for offsite locations were performed, and 'the most critical one was selected to set the release rate.

The controlling distance is 1900 meters to the east of Nine Mile Point Unit l.

Amendment No.

51 19

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BASES FOR GASEOUS WASTE SPECIFICATIONS (Cont'd)

The gamma dose contribution was determined using the equation 7.63 in Section 7-5.2.5 of Meteorolo and Atomic Ener

- 1968.

The releases from vents are cons>

ere to be groun eve re eases which could result in a beta dose from cloud submersion.

The beta dose contribution was determined using Equation 7.21, as described in Section.7-4.1 of Meteorolo and Atomic Energy

- 1968.

The beta dose contribution was determined on the basis of an infinite cloud passage with semi-infinite geometry for a ground level release (submersion dose).

The beta and gamma components of the gross radioactivity in gaseous effluents were combined to determine the allowable continuous release rate.

Based on these calculations, a continuous release rate of gross radioactivity from the site in the amount specified in 2.1.3.a(1) will not result in offsite annual doses above background in excess of the limits specified in 10 CFR Part 20.

l The average gamma and beta energy per disintegration used in the equation of Specification 2.1.3.a(l) will be based on the average composition of gases determined from. the plant stack and ventilation e'xhausts.

The average energy per beta or gamma disintegration for those radioisotopes determined to be present from the isotopic analyses are given in Table 2.1-3.

Where isotopes are identified that are not listed in Table 2.1-3, the ganma energies are determined from Table of Isoto es, C.

M. Lederer, J.

M. Hollander, and I. Perlman, Sixth

dition, 1967 and the beta energ~hall be as given in USNROL-TR-802, II.

S ectra of Individual Ne atron Emitters (Beta S ectra),

0.

Hogan, P. E.

sgman and

. L. Mack in.

For Specification 2.1.3.a(2),

dose calculations have been made for the critical sectors and critical pathways for all radioiodines and radioactive material in particulate form with half-lives greater than eight days.

The calculations consider site meteorology for these releases.

For radioiodines and radioactive materials in particulate form with half-lives greater than eight days, the critical location for ground releases is the east sector at a distance of 990 meters from the FitzPatrick Plant vent where the X/g is 1.6 x 10"6 sec/m3 for the

dose, due to inhalation.

The critical location for elevated releases is the east sector at a distance of '1900 meters from the Nine Mile Point Unit 1 stack where the X/g is 1.9 x 10-8 sec/m3 for the dose, due to inhalation.

The nearest milk cow is located in the Nine Mile Point Unit 1

SW sector at a distance of 1250 meters where the X/g is 4

x 10-7 sec/m3 for ground releases (FitzPatrick vent),

and 1.2 x'0-8 sec/m3 for Nine Mile Point Unit 1 elevated releases.

The 9rass-cow-milk-child thyroid chain is controlling.

Amendment flo.

51 20

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BASES FOR GASEOUS WASTE SPECIFICATIONS (Cont'd)

The assumptions used for these calculations are:

(1) onsite meteorological data for the most critical 22.5 degree sector; (2) credit for building wake; and (3) a reconcentration factor of 243 and a

grazing factor of 0.41 were applied for possible ecological chain effects from radioactive iodine and particulate releases where applicable.

Specification 2.1.3.b establishes upper site levels for the releases of noble gases, iodines and particulates with half-lives greater than eight days, and iodine-131 at twice the design objective annual quantity during any calendar quarter, or four times the design objective annual quantity during any period of 12 consecutive months.

The intent of this 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 higher releases than the objectives.

In addition to the limiting conditions for operation of Specifications 2.1.3.a and 2.1.3.b, the reportin'g requirements of 2.1.3.c delineate that the cause be identified whenever the release of gaseous effluents exceeds one-half the design objective annual quantity during any calendar quarter, and describe the proposed program of action to reduce such release rates to the design objectives.

Specification 2.1.3.d and 2.1.3.e are in accordance with Oesign Criterion 64.

Specification 2.1.3.f is to monitor the performance of the core.

A sudden increase in the activity levels of gaseous releases may be the result of defective fuel.

Since core performance is of utmost importance in the resulting doses from accidents, a report must be filed within 10 days following the specified increase in gaseous radioactive releases.

Specification 2.1. 3.g requires that the primary containment atmosphere receive treatment for the removal of gaseous iodine and particulates prior to its release.

Specification 2.1.3.h requires that hydrogen concentration in the system shall be monitored at all times.

Amendment No.

51 21

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BASES FOR GASEOUS WASTE SPECIFICATIONS (Cont'd)

The sampling and monitoring requirements given under Specification 2.1.4 provide assurance that radioactive materials released in gaseous waste effluents are properly controlled and monitored in conformance with the requirements of Oesign Criteria 60 and 64.

These requirements provide the data for the licensee and the Commission to evaluate the'lant's performance relative to radioactive wastes released to the environment.

Reports on the quantities of radioactive materials released in gaseous effluents are furnished to the Commission in conformance with 10 CFR 50.36a(a)(2) on a semi -annual basis.

Oata is summarized on a quarterly basis in the Semi-annual'Radioactive Effluent Release Report and in conformance with Regulatory Guide 1.21.

On the basis of such reports and any additional information the Conmission may obtain from the licensee or others, the Comnission may from time to time require the licensee to take such action as the. Commission deems appropriate.

22 Amendment No.

51

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2.1.5 SPECIFICATIONS FOR SOLID WASTE HANDLING'AND'DISPOSAL a.

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

b.

Solid wastes in storage and preparatory to shipment shall be monitored and packaged to assure compliance with 10 CFR Part 20, 10 CFR Part 71, and 49 CFR Parts 171-1.78.

c.

Reports of the radioactive solid waste shipments,

volumes, principal radionuclides, and total curie quantity, shal 1

be submitted in accordance with Section 4.6. l.

BASES The requirements for solid radioactive waste handling and disposal given under Specification 2.1.5 provide assurance that solid radioactive materials stored at the plant and shipped offsite ar' properly controlled, monitored, and packaged in conformance with 10 CFR Part 20, 10 CFR Part 71, and 49 CFR Parts 171-178.

These requirements provide the data for the licensee and the Commission to evaluate the handling and storage facilities for solid radwaste, and to evaluate the environmental impact of offsite shipment and storage.

Reports on the quantities and amounts of the radionuclides, and volumes of the shipments, shall be furnished to the Commission according to Section 4.6.1 of these Technical Specifications.

On the basis of such reports

'and any additional information the Commission may obtain from the licensee or others, the Commission may from time to time require the licensee to take such action as the Coranission deems appropriate.

Amendment No.

51 23

I It N

3. 0 ENVIRONMENTAL SURVEILLANCE

3. 1 METEOROLOGICAL MONITORING OBJECTIVE The objective of meteorological monitoring is to adequately measure and document meteor'ological conditions at,.the site.

S PECIF ICATION The meteorological monitoring system shall measure parameters as prescribed by Table 3.1-1 to provide data that is representative of atmospheric conditions that exist at all gaseous effluent release points.

REPORTING RE UIREMENTS Meteorological data shall be compiled for quarterly periods in a format consistent with Table 3.1-2.

Summaries of data and observations'shall be available to the Nuclear Regulatory Commission upon request.

Oata shall be reported in conjunction with the Semi -Annual Radioactive Effluent Release Report as specified in Section 4.6..l.b.

If the outage.

time of any of the required meteorological instruments exceeds seven consecutive

days, the total outage time and dates of outage, the cause of.the outage, and the instrumen~) -involved shall be reported within 30 days of the initial time of the outage to the -Nuclear Regulatory Commission, Office of Nuclear Reactor Regulation.

Modifications to the meteorological monitoring program as described above shall have the written approval of the Nuclear Regulatory Commission, Office of Nuclear Reactor Regulation, prior to initiation of the modification.

BASES The collection of meteorological data at the plant site will provide information which may be used to develop atmospheric diffusion parameters to estimate potential radiation doses to the public resulting from actual routine or accidental releases of radioactive materials to the atmosphere.

A meteorological data collection program as described above is necessary to meet the requirements of sub-paragraph 50.36 a (a) (2) of 10 CFR Part 50, Appendix L of 10 CFR Part 50, and 10 CFR Part 51.

Amendment fio.

51

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g P

I

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TABLE.3.1-1 Meteorological Measurement Parameter Wind Oirection Instrument Accurac

+5o

( Instantaneous Value)

Nominal Tower Elevation 30',

200'ind Speed

+0.5 mph (2.5-10 mph, time average)

+1.0 mph (10-50 mph, time average)

/

+2.5 mph (Starting Speed) 200'0.5 mph (Time Average) 1.0 mph (Starting Speed) 30'emperature

+1.0oF (Time Average).

27'emperature Oifference

+0.2oF (Time Average)

(200'-27')

25 Amendment iso.

51

I

TABLE 3.1-2 Meteorological Oata Format (a)

PERI00 OF RECORO:

STABILITY OF CLASS:

ELEVATION:

W>nd peed mph at iOm Level Wind Oirection 1-3 4-7 8-1 2 TOTAL NNE NE ENE ESE SSE SSW SW WSW WNW NNW VARIABLE Total'eriods of calm (hours):

Hours of missing data:

I In the table, record the total number of hours of each category of wind direction for each calendar quarter.

Provide similar tables separately for each atmospheric stability class and elevation.

26 Amendment No.

51

r

3. 2 RAOIOLOGICAL ENVIRONMENTAL MONITORING OBJECTIVE P

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 radioactive materials sources.

SPECIFICATION

.An environmental. radiological monitoring program shall be conducted as follows:

a.

The environmental radiation monitoring program specified in Table 3.2-1 shall be conducted.

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

b.

Reporting requirements for the environmental radiological monitoring program are outlined in Section 4.6.

c.

Ouring the seasons that animals producing milk for human consumption are on pasture at locations that may be significantly affected~

by emissions from Nine Mile Point-l, samples of fresh milk shall be obtained monthly.

For those animals on'asture for

~ which the milk chain dose has-been calculated to exceed 15 mrem/year, sampling shall be done weekly.

Samples shall be 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 (two sigma confidence level) of the analysis shall be within + 50 percent.

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

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

the family farm.

I d.

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

"For the purposes of this requirement, "Significantly affected" means that calculations, using standard NRC staff assumptions, predict that a two year old child drinking milk produced by animals at that location may receive a

thyroid does of 1 mrem/year. or greater.

27 Amendment No.

51

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TABLE 3.2-1 SAMPLE COLLECTION AND ANALYSIS SITE RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM A.

LAKE PROGRAM HEDIA 1.

Fish 2.

Cladophora 3.

Lake Water.

4.

Sediment N/A N/A N/A GSA GSA 3H~ 89Sr 90Sr GSA SENSITIVITY ANALYSIS 80 pCi/Kg, dry

GSA, 8 Sr E 9OSr

~FRE UENCY 2/yr in season 2 onsite 2 onsite LOCATIONS(1) 1 offsite 1 offsite 3(2) 1 offsite H Comp.

Qtr.

Comp.

Semi-Annual Dam Shoreline NOTES (1) Onsite samples collected in the vicinity of discharges, o)Ffsite samples collected at a distance of at least five miles from site.

I I

(2) The three lake water samples to include Nine Mile Point Unit 1 intake water, James A. FitzPatrick intake

water, and Oswego city raw water.

Abbrev iati ons:

H Comp. - Monthly composite of weekly or bi-weekly samples GB - Gross beta analysis GSA - Garrma spectral analysis on a NaI or GeLi system (quanitative)

A - Annually W - Weekly H Monthly Qtr. - Quarterly C - Continuous

.SA - Semiannually

I I

I

~ ~

e

TABLE 3.2-1 (Cont'd)

SAMPLE COLLECTION AND ANALYSIS SITE RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM 4

~

B.

LAND PROGRAM MEDIA 1.

Air Particulates ANALYSIS GB GSA FRE(RUENCY W

M Co p(>>

NO.

OF LOCATIONS At least 10 7 onsite LOCATIONS 6 offsite 2.

Soil 3.

TLD 4.

Radiation Moni-tors Gamna Dose Ganma Dose 20 At least 7

GSA, gOSr Every 3 years 13 7 onsite 14 onsite 7 onsite 6 offsite 6 offsite 1 offsite 5.

Airborne - I131 6.

Milk GSA I

GSA, gOSr M(4)

At least 10 4(4)

I 7 onsite (5) 6 offsite 7.

Human Food Crops GSA, 131I 3

I (5) 8.

Heat, Poultry, Eggs GSA Edible Portions SA NOTES (Cont'd)'

(3) Onsite samples counted as two composites:

offsite samples counted as two composites; any high gross beta count samples counted separately (not included in composite).

(4) Frequency applied only during grazing season.

(5) Samples to be collected from farms within a 10-mile radius having the highest potential concentrations of radionuclides.

I f

3. 2 RAOIOLOG ICAL ENVIRONMENTAL MONITORING (Cont 'd)

If it is learned from this census that animals producing milk for human consumption are present at a location which yields a 'calculated infant thyroid dose greater than from previously sampled

animals, the new location shall be added to the surveillance program as soon as practicable.

The sampling location having the lowest calculated dose may then be dropped from the surveillance program at the end of the grazing season during which the census.was conducted.

BASES The number and distribution of sampling locations and the various types of measurements-described in Table 3.2-1 together with the preoperational background data, will provide verification of the effectiveness of Station effluent control and indication of measurable changes in the activity of the environment.

The concentration of I-131 in milk of 2.4 picocuries per. li.ter will result 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 radioiodine concentration in the milk to the sensitivity given above, 0.5 pCi/liter.

Ground water sampling is not reqrrred because ground water in the vicinity of the station flows north to the lake, away from any nearby wells.

30 Amendment No.

51

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4. 0 AOMINISTRATIVE CONTROLS OBJECTIVE Administrative controls for implementation of the Environmental 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 implemented.

4. 1 RES PONS IBILITY 4.1.1 The responsibilities of the General Superintendent-Nuclear Generation as prescribed in paragraph 6.1.1 Appendix A shall include the continuing protection of the environment.

4.1. 2 4.1. 3

'Operation of the Station in compliance with the Environmental Technical Specifications is the responsibility of the Station Superintendent with the assistance of the Station staff organization.

II The structure of corporate responsibility is shown in Figure 6.2;1 of Appendix A.

4.2 ORGANIZATION

4. 2.1 4.2.2 The Station organization and its relationship to the site organization is shown in Figure 6.2-2 of Appendix A to Facility Operating Licensing No.

DPR-63.

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

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

4.3 REVIEW AND AUDIT

4. 3.1 Units for review and audit of environmental matters shall be as described in section 6.5 of Appendix A to Facility Operating License No.

DPR-63.

. Amendment No.

51 31

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4.0 4.3 AOMINISTRATIVE CONTROLS (Cont'd)

RE VIEM ANO AUOIT ( Cont '

)

1 4.3.2 The responsibilities and authorities of the environmental review and audit units are as detailed in section 6.5 of Appendix A.

4.4 ACTION TO BE TAKEN IF A LIMITING CONOITION FOR OPERATION IS EXCEEOED 4.4.1 Remedial action as permitted by the Technical Specification shall be taken until the condition can be met.

4.4.2 4.4.3 Exceeding a limiting condition for operation shall be investigated by the Site. Operations Review Committee.

A report for each occurrence shall be prepared in accordance with one of the schedules specified in Section 4.6.2 or as required by the particular specification involved.

4. 5 PROCEOURES 4.5.1 Oetailed written procedures, including applicable checkoff lists and instructions, shall be prepared, approved as specified in. Section 4.5. 2 and adhered to for operation of all systems and components involved in carrying out the environmental monitoring program.

Procedures shall inc'lude

sampling, instrument calibration, analysis, and actions to be taken when specified limits or report levels are approached or exceeded.

Calibration frequencies for instruments used in performing the measurements required by the environmental Technical Specifications shall'be included.

Testing frequency of any alarms shall be included.

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

4.5. 2 Prior to implementation, all procedures described in 4.5.1

above, and changes

hereto, shall be reviewed as provided in Section 4.3 and approved by the Station Superintendent.

Temporary changes to procedures which do not change the intent of the original procedure may be made, provided such changes are approved by the Station Superinte'ndent and Superintendent Chemistry and Radiation Management.

Such changes shall be documented, subsequently reviewed as provided in Section 4.3 and approved on a timely basis.

Amendment No.

51 32

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4 ~ 6 PLANT REPORTING REOUIREMENTS'.6.1 Routine Re orts a.

b.

4.6. 2 Annual Radiological Environmental Operating Report A report on the radiological environmental surveillance

'rograms for'the previous 12 months of operation shall be submitted to the Director of. the NRC Regional Office (with a copy to the Director, Office of Nuclear Reactor Regulation) as a separate document within 4 months after January 1 of each year.

The reports shall include summa'ries of the'adiological environmental surveillance activities for the report period.

The reports shal 1 al so include the results of land use censuses required by the specifications.

If harmful effects or evidence of irreversible damage. are detected by the monitoring, the licensee shall provide an analysis of the

'problem and a proposed course of action to alleviate the problem.

Results of all radiological environmental samples taken shall be summarized and tabulated on an annual basis in the format of Table 4.6-1.

In the event that some results are not available within the 6 months period, the report shall be submitted noting and explaining the reasons for the missing results.

The missing data-shall be submitted as soon as possible in a supplementary report.

Radioactive Effluent Release Report A report on the radioactive discharges released from the site during the previous 6 months of operation shall be submitted to the Director of the NRC Regional Office (with a copy to the Director, Office of Nuclear Reactor Regulation) within 60 days after January 1

and July 1 of each year.

The report shall include a summary of the quantities of radioactive liquid and gaseous effluents and solid waste released from the plant.

The report shall include a summary of the meteorological conditions concurrent with the release of gaseous effluent during each quarter as prescribed in Section

3. 1.

Nonroutine Re orts a.

Nonroutine Environmental Operating Reports A report shall be submitted in the event that Section 2,

"Limiting Conditions for Operation" or a report level or specification is reached (as specified in Section 3,

"Environmental Surveillance" ).

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

Amendment No.

51 33

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TABLE 4.6-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM REPORT

. N Facility Nine Mile Point Unit 1 Docket Ro. 50-220 O

Average quarterly Results2 (specify radionuclide or entity).

Medium/Sample Location quarter 1

quarter 2

quarter 3

quarter 4

AIRBORNE Particulate DIRECT 1) 2)

Iodine 1) 2)

Soil

, 1) 2)

1) 2)

~

WATERBORNE

, 'Surf ace 1) 2)

Ground Drinking 1) 2)

()

f 1

TABLE 4.6-1 (Cont'd)

~AUATIC Al CL

~

lD 4

Sediment 1) 2)

Benthic Organisms 1) 2)

Plants 1) 2)

d I

INGESTION Hilk 1) 2)

Fish and Shellfish 1) 2)

Heat and Poultry 1) 2)

OTHER

~

B.

Evaluation (Include a suanary evaluation of the results from the monitoring program.)

~,>

NOTES FOR TABLE 4.6-1 1)

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

2)

Use the following units: direct radiation, mrem/quarter; particulate and iodine, pCi/m3; water and milk, pCi/1; sediment, pCi/gn dry; vegetation, pCi/gm wet.

I

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4.6 PLANT REPORTING RE UIREMENTS (Cont'd) 4.6. 2 Nonroutine Re orts (Cont'd)

(1)

Prom t Re ort.

>Those events requiring prompt reports shal be reported within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> by telephone, telegraph or fascimile transmission to the Oirector of the NRC Regional Office and within 10 days by a written report to the Oirector of the NRC Regional Office (with a co'y to the Oirector, Office of Nuclear Reactor Regulation).

(2) 30-Oa Re ort.

Those events not requiring prompt reports shal e reporte within 30 days by a written report to the Oirector of the NRC Regional Office (with a copy to the Oirector, Office of Nuclear Reactor Regulation).

Reports concerning unusual or important events shall be reported on the prompt schedule.

Mritten 10-day and 30-day reports and, to the extent

possible, the preliminary telephone, telegraph, or fascimi le reports shall (a) describe,

analyze, and evaluate the occurrence, including extent and magnitude of the impact, (b) describe the cause of the occurrence, and (c) indicate the corrective action (including any signficant changes made in procedures) taken to preclude repetition of the occurrence and to prevent similar occurrences inva1ving similar components or systems.

Nonroutine'adiological Environmental Operating Reports If a confirmed measured level of radioactivity in any environmental medium exceeds ten times the control value, a

written report shall be submitted to the Oirector of the NRC Regional Office (with a copy to the Oirector, Office of Nuclear Reactor Regulation) within 10 days after confirmation.*

This report shall include an evaluation of any release conditions, environmental factors, or other aspects necessary to explain the anomalous result.

con >rmatory reana ysis o

the original, a duplicate, or a new sample may be desirable, as appropriate.

The results of the confirmatory analysis shall be completed at the earliest time consi'stent with the analysis, but,in any case within 30 days.

Amendment No.

51 37

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4.6 PLANT REPORTIIIE UIREHENTS (Cont'd)

~

4.6.2 Ci 4.6.3 Nonroutine.Re orts (Cont'd)

Nonroutine Radioactive Effluent Reports If the quantity, of radioactive material released in effluents to unrestricted areas during any calendar quarter is such that the resulting radiation exposure or cumulative activity release exceeds one-half the design objective annual exposure derived pursuant to Appendix I 10 CFR Part 50, as stated in the Objective of Section 2, the licensee shall make an investigation to identify the causes of such releases an'd define and initiate a program of action to reduce such releases to the design objective levels.

A written report of these actions shall be submitted to the Director of the NRC Regional Office (with a copy to the Director, Office of Nuclear Reactor Regulation) withi~n 30 days from the end of the quarter during which the release occurred.

The release levels at which such a report is required are given in Specification 2.1.1.h and 2.1.3.c for liquid and gaseous

releases, respectively.

In addition, Specification 2.1.3.f gives conditions under which a report is required within 10 days.

Chan es in Environmental Technical S ecifications A report shall be made to the NRC prior to implementation of a change in plant design, in pla'nt operation, or in procedures described in Section 4.5 if the change would have a significant effect on the environment or involves an environmental matter or question not previously reviewed and evaluated by the NRC.

The report, shall include a description and evaluation of the change and a supporting benefit-cost analysis.

A

4. 7

'ECORDS RETENTION 4.7.1 Records and logs relative to the following areas shall be made and retained for the life of the plant:

a.

b.

Records and. drawings detailing plant design changes..and modifications made to systems and equipment as described in Section 4.6.3.

Records of all data from environmental monitoring'nd surveillance required by these Environmental Technical Specifications.

4.7.2 All other records and logs relating to the Environmental Technical Specifications shall be retained for five years

'ollowing logging or recording.

Amendment No.

51 38 1

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3