ML17319B329

Amends 54 & 40 to Licenses DPR-58 & DPR-74,respectively, Relocating Radiological ETS & Replacing Nonradiological ETS W/Nonradiological Environ Protection Plan

ML17319B329
Person / Time
Site:	Cook
Issue date:	05/06/1982
From:	Varga S Office of Nuclear Reactor Regulation
To:
Shared Package
ML17319B330	List: ML17319B329 ML17319B331 ML20052G873
References
NUDOCS 8205190098
Download: ML17319B329 (70)

Text

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Po UNITED STATES NUMIEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555

';" 8205190098 820506 "PDR *DOCK 05000315

,P',,

PDR'NDIANA AND MICHIGAN ELECTRIC COMPANY DOCKET NO. 50-315 DONALD C.

COOK NUCLEAR'LANT UNIT NO..l AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.. 54 License No.

DPR-58 1.

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

A.

B.

C.

D.

E.

The application for amendment by Indiana and Michigan Electric Company (the licensee) dated November 4, 1981, 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; The facility will operate in conformity with the application, and provisions of the Act, and the rules and regulations of the Commission; There is reasonable assurance (i) that the activities authorized by this amendment can be conducted in without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; 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 The issuance of this amendment is in accordance with 10 CFR Part 51 of the Comission's. regulations and all applicable requirements have been satisfied.

2 2.

Accordingly, the license is amended by changes to the Technical

~

Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No.

DPR-58 is hereby amended to read as follows:

(2)

Technical Soecificati'ons The Technical Specifications contained in Appendices A and B, as revised through Amendment No.

54

, are hereby incorporated in the license.

The licensee shall operate the faci lity in accordance with the Technical Specifications.

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3.

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

0 THE NUCLEAR REGULATORY COMMISSION eve W. v r

, Chic

Attachment:

Changes to the Technical Specifications V

Date of Issuance:

May 6, 1,982 Operating Reactors Bran "1

Division of Licensing

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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, O. C. 20555 INDIANA AND MIC8IGAN'LECTRIC COMPANY DOCKET NO. 50-316 DONALD C.

COOK NUCLEAR PLANT UNIT NO.. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.

40 License No.

DPR-74 l.

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

A.

B.

C.

D.

The application for amendment by Indiana and Michigan Electric Company (the licensee) dated November.4, 1981, 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; The facility will operate in conformity with the application, and provisions of the Act, and the rules and regulations of the Commission; There is reasonable assurance (i) that the activities authorized by this amendment can be conducted in without endangering the health and safety of the 'public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; 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

~

I E.

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

2.

Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No.

DPR-74 is hereby amended to read as follows:

(2)

Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No-4O

, are hereby incorporated in the license.

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

3.

This'license amendment is effectiv as of the date of its issuance.

F THE NUCLEAR REGULATORY COMMISSION ven r a,

.Operating Reactors B'ch 41 Division of Licensin

Attachment:

Changes to the Technical Specifications Date of Issuance: 'ay 6, 1982

ATTACHMENT TO LICENSE AMENDMENTS AMENDMENT NO. 54 TO FACILITY OPERATING LICENSE NO. DPR-58 AMENDMENT NO. 40 TO FACILITY OPERATING LICENSE NO.

DPR-74 DOCKET NOS.

50-315 AND 50-316 Revise Appendix B as follows:

J Remove, rom A enNx B

Insert A

endix B

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H Part

'1 Radiological Part II Hon-Radiological Environmental Protection Plan Part III Non-Radiological Non pater equality cover page 2.1-1 through 2.2-2 2.4-1 through 2.4-19 4.1-1 through 4.1-6 4.1-9 4.1-11 through 4.1-39 4.2-1 through 4.2-10 5.4-1 through 5.5-1 cover page 2.1-1 2.4-1 4.1-1 4.1-9 4.1-11 4.2-1 5,4-1

~ ~

4

, APPENDIX B ENVZRONMENTAL TECHNICAL SPECIFICATIONS FOR DONALD C.

COOK NUCLEAR PLANT UNITS 1 AND 2 BERRZEN COUNTY, i<ZCHZGAN DCCKET NUHBERS 50-315 AND 50-316 PART I - RADIOLCGZCAL Issued:

May 6, 1982

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1 Table of Contents 1

DEFINITIONS~ ~ o ~ ~ ~ ~

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. 1-.1 2.

LIMITING CONDITIONS POR OPERATION 2.1 Radioactive Effluents...............................

2-1

'.1.1'.1.2 2.1.3 2.1.'4 2.1.5 Specifications Specifications and Monitoring.

Specifications Specifications and Monitoring.

Specifications and Disposal...

for Liquid Waste Effluents.........

for Liquid Waste Sampling and

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for Gaseous Waste Effluents.......

for Gaseous Waste Sampling

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for Solid Waste Handling

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2-1 2-2 2-5 2-7 2-'ll 3.

ENVIRONMENTAL SURVEZLLANC....................... ~...........

3>>1 3.1 Radiological Environmental Monitoring...................

3>>1 4 ~

SPECIAL SURVEILLANCE AND STUDY ACTIVITIES....................

4-1 5.

ADMINISTRATIVE CONTROLSo ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ o ~ ~ ~ ~

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5-3.

5.1 Organization, Review and Audit..........................

5-1 5.2 Action to be Taken if a Limiting Condition Operation is Exceeded......................

for o.3 Procedures..............................................

5-1 5.4 Plant Reporting Requirements............................

5-2 5.5 Records Retention.......................................

5-7 Amendment Nos.

54 5 40

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\\

C List of Tables No.

Pacae 2.1-1 Radioactive Liquid Sampling and Analysis.

2-12 2.1-2 Radioactive Gaseous Waste Sampling and Analysis..........

2-14

2. 1-3 PWR-Liquid Wa'ste System.

Location of Process and Effluent Monitors and Samplers Reaui ed by Technical Specifications.................................

2-16 2.1-4 PWR-Gaseous Waste System.

Location of Process and Effluent Monitors and Samplers Required by Technical Specifications.................................

2-17 2.1-5 Average Energy Per Disintegration........................

2-18 Amendment Nos.

54

& 40

e leo DEFINITIONS Abnormal Environmental Occurrence (AEO) is one that:

a.

Results in noncompliance with, or is in violation of, the specifi-cations section of a limiting condition for operation (Section 2).

b.

C ~

Results in uncontrolled oz unplanned release of radioactive dis-charges from the Donald C. Cook Nuclear Plant in excess of the applicable regulations of governing agencies, or

'I Results in a significant adverse Radiological environmental impact.

~Accurse:

Refers to the deviation of a result obtained by a paz'ticulaz method from the value accepted as true.

A~nnuall:, Annually is once per calendar year at intezvals of twelve calendar months.

Batch.Release:

A batch release is the discharge of fluid wastes of a discrete volume.

Calibration:

An instrument or device calibration shall be the adjust-

ment, as necessary, of the output such that it responds with the necessary range and accuracy to known values of the parameter(s) which the inst~ent sensor or device monitors.

The calibration shall encompass the entire circuit including the sensor, indicatory control

feature, alarm and/or trip function(s),

and shall include the functional test.

The calibration may be performed by any series of sequential overlapping or total circuit steps such that the entire, circuit is calibrated as specified.

Composite Sample:

A composite sample is one in which the cuantity of liquid sample is prooortional to the quantity of liquid waste discharged.

Continuous Monitors:

As applied to in place monitors and flow indicators does not prevent the devices from being periodically taken out of service for calibration or maintenance.

Continuous Release:

A continuous zelease is the discharge of luid waste of a non-discrete volume, e.g.,

from a volume or system that has an input flow during the continuous release.

Functional=Check:

A functional check shall be the qualitative assessment of channel behavior during operation by observation.

This determination shall 'include, where oossible, comoarisons and/or status de ived from

independent instrument channels measuring the same parameter.

Amendment

)los.

54 5 40

Functional Test:

A functional test shall be the injection of a simulated signal into the channel as close to the primary sensor as practicable to verify OPERABILITY including alarm and/or trip functions.

or flow.

Minimum Detectable Level:

Refers to that level which a specific detector, instrument or analysis is unable to detect the presence of a'iven con-stitutent.

~Monthl:

Monthly is once evezy 30 days.

Normal 0 eration:

Operation of the station at greater than 5% of rated

'hezmal power in other than an emergency situation.

Precision:

Relates to the reproducibility of measurements within a set, that is, to the scatter or dispersion of a set about its central value.

~uaztezl:

Quarterly is once duzing each successive three south period of the calendar year, counting from January 1, at intervals of 13 weeks.

by the sensor.

Spectral Band:

A width, generally expressed in wavelength or frequency of a particular portion of the electromagnetic spectrum.

~

A given sensor (e.g., radiometer detector or camera film) is designed to measure or be sensitive to energy received from that part of.the spectrum.

Plant and Unit:

Plant refers to D. C. Cook Nuclear Plant, Unit Nos.

1 and 2.

Unit refers only to Unit.No.

1 or Unit No. 2.

~Weekl i Weekly is once during each calendar week at intervals of 7 days.

1-2 Amendment Nos.

54 Im 40

2.0 2.1 LIMITING CONDITIONS FOR OPERATION a

Radioactive Effluents

~Oh'ective:

To define the limits and conditions dor the control'led release of radioactive materials in liquid and gaseous effluents to the environs to ensure that these releases are as low as practicable.

These releases should not result in radiation exposures in unrestricted areas greater than a few percent of natural background exposures.

The release rate for all effluent discharges shall be within the 1'mits specified in 10 CFR Part 20.

To assure that the releases of radioactive material above background to unrestricted areas to be as low as practicable 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 plant 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 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.

e.

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

2.1.3.

S eci ications for Liquid ifaste Effluents a e The concentration of radioactive materials xeleased in liquid waste ef luents from all reactors at the site shall not exceed the values specified in~0"CFR Part 20, Apoendix B, Table ZI, Column 2, for-unrestricted areas.

2-1 Amendment Nos.

54,& 40

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.

During release of radioactive wastes, the effluent contiol monitor shall be set to alarm and to initiate the automatic closure of each waste isolation valve prior to exceeding the limits specified in 2.1.1.a above.

e.

The operability of the automatic isolation valves in the liquid radwaste discharge lines shall be demonstrated quarterly.

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 cumu-lative release rate could exceed 1.25 Ci/reactor/calendar

quarter, excluding tritium and dissolved gases.

go 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 t"itium and dissolved gases.

h.

lf 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'n inves-tigation to identify the causes for such releases, define and initiate a program of action to reduce such release rates 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.

2.1.2 S ecifications for Liouid Haste Sam lin and Monitorin a 0 b.

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

Sample analysis results and other reports

- shall be submitted in accordance with Section 5.4 of these specifications.

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

Prior to release of each batch of liquid waste, a representative sample shall be taken from that batch and analyzed for the con-centration of each significant gamma 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'aste is discharged during the period of discharge.

2-2 Amendment Nos.

54 II 40

Ce s

Sampling and analysis of liquid radioactive waste shall be performed in accordance withTable 2.1-1.

Prior to taking samples from a monitoring tank, at least two 'tank volumes shall be recirculated.

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

Whenever these monitors are inoperable for a period not to exceed 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, two independent samples of each tank to be discharged shall be analyzed and two plant personnel shall independently check valving prior to the discharge.

If'these monitors are inoperable for a period exceeding 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, no liquid waste tank shall be released and any release 'in progress shall be terminated.

e.

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

s All liquid effluent radiation monitors shall be calibrated at least quarterly by means of a radioactive source which has been calibrated to a National Bureau of Standards source.

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

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

Whenever these monitors aze inoperable, the blowdown flow shall be diverted to the waste management system and the dizect release to the environment terminated.

Bases:

The release od radioactive materials in licgxid waste effluents'o unrestricted areas shall not exceed the concentration limits specidied in 10~CFR Part 20 and should be as low as practicable in accordance with the requizements of 10 CFR Part 50.36a.

These speci ications 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 using this operational flexibilityunder unusual operation conditions, and exerting every effort to keep levels of radioactive materials in liquid wastes as low as practicable, the annual releases will not exceed a small fraction of the concentzation limits specified in 10 CFR Part 20.

The design objectives have been developed based on operating experience taking into accourit a combination of variables including defective fuel, primary system leakage, orimary to secondary system leakage and the per-formance of the various waste treatment

systems, and are cons'stent witn Appendix I to 10 CFR Part 50.

2-3 Amendment Nos.

54 5 40

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

This specification provides assurance that.no member of the general public will be exposed to liquid containing radio-active materials in excess of limits considered permissible under the Commission's Rules and Regulations.

Specifications 2.1.1.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 zesult in concentrations of radioactive material.in

'iquid wastes at small percentages of the limits specified in 10 CFR Part 20.

r Specifications 2.1.1.d and 2.1.1.e require that suitable equipment to control and monitor the releases of radioactive materials in liquid wastes are operating during any period these releases are taking place consistent with the requirements of 10 CFR Part 50, Appendix A, Design Criterion 64.

Specification 2.1.1.f requires that the licensee maintain and operate the equipment installed in the liquid waste systems to reduce the release of radioactive materials in liquid effluents to as low as practicable consistent with.the requirements of 10 CFR 50.36a.

Normal use and maintenance of installed equipment in the liquid waste system provides reasonable assurance that the quantity released will not exceed the design objective.

In order to keep zeleases of radioactive materials as low as practicable, the specification requires operation of equip-ment whenevez it appears that the'rojected cumulative discharge rate will exceed one-fourth of this design objective annual quantity during any calendar quarter.

Specification 2.1.l.g limits the amount of radioactive material that may 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 2.1.1.b and 2.1.1.c the reporting requirements of Specification 2.1.1.h delineate that the licensee shall identify the cause whenever the release zate of radioactive materials in liquid waste effluents exceeds one-half the design objective annual quantity during any calendar quarter and describe the proposed program of action to reduce such releases to design objective lev'els on a timely basis.

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

2-4 Amendment Hos.

54 8 40

The sampling and monitoring requirements given under Specification 2.1.2.

a through g provide assurance that radioactive materials in liquid wastes are properly controlled and monitored in-conformance with the requirements of Design Criteria 60 and 64.

These zeauirements pzovide the data for the licensee and the Commission to evaluate the plant's performance relatives to radioactive liquid wastes released to the environment.

Reports on the auantities of radioactive materials released in liquid waste effluents are furnished to the Commission according to Section 5.4 of these Technical Specifications in conformance with Regulatory Guide 1.21.

On the basis of such reports and any additional information the Commission may. from time to time require the licensee to ta3ce such action as the Commission deems appropriate.

The points of release to be monitored in Section 2.1.2 include all the monitored release points as provided for in Table 2.1-3.

2.1.3 S ecifications for Gaseous Haste Effluents a..

(1)

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

4Q.

(37E.

+112E.

)

+ 1 LV Lf where Qv release rate (sum of the unit vents and the turbine condenser steam air ejector exhaust for Unit 1 and Unit 2)

Qiv release rate from vents in Ci/sec (ground release) for the ith individual nuclide.

the ith individual nuclide E.ig the average gamma energy per disintegration for nuclide i E.

~

the average beta energy per disintegration ig for nuclide i Refer to Table 2.1-5 for E Gamma and E Beta values to be used.

a.

(2)

The release rate limit of all radioiodines and radioactive materials in particulate form with half-lives greater than eight days, released to the environs as oart of the gaseous waste from the site shall be:

1.5 x 10 Q

< 1 5

where Q

is defined above.

v 2-5 II

)

Amendment Nos.

54

& 40

b.

(1)

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

gK.

(350 Q.") < 1 iv

and, gE.

(120 Qi

) ~

1 ip iv b.

(2)

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

'gE.

(700 Q.

) ~ 1 C

and 3

$ E.

(230 Q.

) ~ 1 t'.

b.

(3)

The average release rate of all iodines and radioactive materials in particulate form per site with half-lives greater than eight days during any calendar auarter shall be:

18x10 Q ~1 v

b.

(4)

The average release rate of all iodines and radioactive materials per site in particulate form with half-lives greater than 'eight days during any period of 12 conse-cutive months shall be:

3.6 x 10 Qv b.

(5)

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

b.

(6)

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

2-6 Amendment Nos.

54 5 40

Co Should the conditions of 2.1.3.c (1), (2), or (3) listed below exist,, the licensee shall make an investigation to identify the causes of the release

rates, define and initiate a program of action to reduce the release rates to design objective levels, listed in Section 2.1, and report these actions to the Commission within 30 days from the end of the quarter during which the releases occurred.,

c ~

(1)

Zf the average release rate of noble gases during any calendar quarter is:

gE. p (1400 Q.

) P 1 4

org gE.

(47o g.

> ) a ca (2) If the average release rate of all iodines and radioactive materials in particulate form per site with half-lives greater than 8 days during any calendar quarter is:

7.3 x 10 Q

Q 1 c.

(3)

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

d.

During the release of gaseous wastes from the primary system waste'as holdup system the effluent monitors listed in Table 2.1-4 shall be operating and set to alarm and to initiate the automatic closure of the waste gas discharge valve prior to exceeding the

~ limits speci ied in 2.1.3.a, above'.

The operability of each auto-matic isolation valve shall be demonstrated quarterly.

e.

The maximum activity to be contained in one waste gas storage tank

.shall not exceed 43,800 curies (considered as Ze-133).

2.1:4 S ecifications for Gaseous Waste Sam lin and Monitorin Plant records shall be maintained and reports of the sampling and analysis results shall be submitted 'in accordance with Section 5.4 of these Speci ications.

Estimates of the sampling and analytical errorassociated with each reported value should be included.

2~7 Amendment Nos.

54 II 40

I J'

b.

Gaseous releases to the environment, except from the turbine build-ing ventilation exhaust and as noted in Specification 2.1.4.c, shall be continuously monitored for gross radioactivity and the flow continuously measured and recorded.

Whenever the gross radio-activity monitors are inoperable, grab samples shall be taken and analyzed daily for gross radioactivity.

Whenever the flow rate measu"ement recording instruments are inoperable the flow shall be estimated daily whenever activity is indicated.

ce During the release of gaseous wastes from the primary system waste gas holdup system, the gross activity monitor, 'the iodine collection

device, and the particulate collection device shall be operating.

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

Each monitor shall have a

functional test at least monthly and instrument check at least daily.

e.

Sampling and analysis of radioactive material in gaseous

waste, particulate form, and radioiodine shall be performed in accordance with Table 2.1-2.

Bases:

The release of radioactive materials in gaseous waste effluents to unrestricted areas shall not exceed the concentration limits specified in 10 CFR Part 20, and in accordance with the requirements of 10 CFR Part 50.36a.

These specifications provide reasonable assurance that the resulting annual air dose due to gamma radiation will not exceed 10 mrad, and an annual air dose due to beta radiation will not exceed 20 mrad from noble

gases, and that the annual 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 flexibilityof operation, compatible with considerations of health and safety, to assure that the public is provided with a dependable source of power under unusual oper-ating 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.

Zt is expected that using this operational flexibilityunder unusual operating conditions, and by exerting every effort to keep levels of radioactive material in gaseous wastes as low as practicable, 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 the maximum permissible concentration of radioactive iodine in air should be reduced to allow for tne grass-cow-milk pathway.

(The factor is 1220. for the grass-goat-milk pathway.)

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

Zt has been applied to radio-.

nuclides 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 exposu e or for the other radionuclides.

2-8 Amendment Nos.

54 8 40

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

For Specification 2.1.3.a(l) dose calculations have been made for the critical sector.

These calculations consider site meteorology, buoyancy characteristics, and radionuclide content of the effluent of each unit.

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

The controlling distance is 610 meters to the nozth.

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

- 1968.

The releases from vents are considered to be ground level releases 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 Ener

- 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.

Bsa'ed on these calculations, a continuous release rate 'of gross radioactxvity 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.

The average gamma and beta energy per distintegration used in the equation of Specification 2.1.3.a(1) will be based on the average composition of gases-determined from the plant vent and ventilation exhausts.

The average energy per beta or gamma disintegrat'ion for those radioisotopes determined to be present from the isotopic analysis aze given in Table 2.1-5.

Where isotopes. are identified that are not listed in-Table 2.1-5, the ave age ganuaa and beta energies are determined f om ORNL/KJREG-70 (NUREG/CR-1413),

A Radionuclide Deca Data Base - Index and Summa

Table, D. C. Kocher, May 1980.

. For Specification 2.1;3.a(2),

dose calculations have been made for the critical sectors and critical pathways for all radioiodines and radio-active 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 fom, the controlling sector for unit vent releases is the N sector at a distance of 610 meters (X/Q ~ 7.7 x 10 sec/m

) for the dose due to inhalation.

The nearest milk cow is located in the ENE sector at a distance of 2900 peters.

The applicable X/Q at the nearest milk cow is 1.5 x 10 sec/m The grass-cow-milk-child thyroid chain is controlling.

2-9 1t ~

Amendment

Nos, 54 5 40

The assumption used for these calculations are:

(1) onsite meteoro-logical data for the most critical 22.5 degree sector, (2) credit for building wake, and (2) a'econcentration

.factor 243 and a grazing factor of 0.4 was applied for possible ecological chain effects from radioactive iodine and particulate releases.

Specification 2.1.3.b establishes upper limits 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 a~uaL 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 reporting 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 requires that suitable equipment to monitor and control the radioactive gaseous releases are operating during any period these eLeases are taking place.

Spec'fication 2.1.3.e limits the maximum offsite dose above background to below the limits of 10 CFR Part 20, postulating that the rupture of a waste gas storage tank holding the maximum activity releases all of the contents to the atmosphere.

The sampling and monitoring recuizements given under Specification 2.1.4.

a through e provide assurance that radioactive materials released in gaseous waste effluents'are properly controlled and aenitored in con-formance with the requirements of Design Criteria 60 and 64.

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

Reports on the quantities of radioactive materiaLs released in gaseous effluents are furnished to the Commission on the basis of Section 5.4 of these Technical Specifications and 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 equize the licensee to take such action as the Commission deems aooropriate.

The points of release to the environment to be montiored in Section 2.1.4 'nclude all the monitored release points as provided for in the Table 2.1-4.

p ~ g 2-10 Amendment Nos.

54 5 40

Specification 2.1.4.b excludes monitoring the lation exhaust since this release is expected point.

Many PWR reactors do not have turbine be consistent in this requirement for all PWR of gaseous releases from turbine buildings is turbine building venti-to be a negligible release building enclosures.

To

reactors, the monitoring not required.

2.1.5 S ecifications for Solid Waste Handlin and Disnosal a.

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

b.

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 171-178.

c.

Reports of the radioactive solid waste shipments,

volumes, principle radionuclides, and total curie quantity, shall. be sumbitted in accordance with Section 5.4.

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 are 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 sol'd radwaste, and to evaluate the environmental impact of offsite shipment and storage.

Reports on the quantities, principle isotopes and volumes of the shipments, are furnished to the Commission according to Section 5.4 of these Technical Specifications.

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

V 2-11 Amendment Nos.

54

& 40

TAOLE 2 1-1 AAOIOACT VE GASEOUS WASTE SAHPL NG AND ANALYS S LIQUI 0 SOURCE SAHPLINC FREqUENCY TYPE OI'CTIVITYANALYSIS OETECTASLE CONCENTRAT)OQS UCI A~

NoNITOR TANK AELEAsEs EACN BATCII PRINCIPAL GAMMA EHI TTERS OtE BAT

< M 10 W

K C

P S T B A-10

-1 1

10 10-'ONTIILY CONPOS I TE 10 ARTE Y COMPOS E

GRoss SR- 0 10 x 10 8 ~

PRINARY COOt ANT w

I-1 1

-1 10 C

STEAIt GENERATOR BLOMDOMN (11)

WEEKLY ONE SAMP NON I

(4)

NONTHLY COFIPOSITE PR NC PA GANJA E TT Rs BA-LA-1IIO

-1 1

Osso vsoG ss SR-8 1 -6 1 -5 1 -8 10 GRoss (4)

A T

R CON S

Sn- 0 1 -7 10

Table 2.L-L (cont'd.)

NOTES:

(1)

For certain mixtures of gamma emittezs, it may not be possible to measure radionuclides in concentzat'ions near their sensitivity limits when other nuclides aze present in the sample in much greater concentrations.

Under these circumstances, it wi.ll be more appropriate to calculate the concentrations of such radio-nuclides using measured ratios wi.th those radionuclides which are routinely identified and measured.

(2)

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

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

(3)

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

(4)

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

Prior to analyses, all samples taken for the composite should be throughly mixed in order for the composite sample to be represen-tative of the average 'effluent release.

Amendment ttos.

54 Im, 40

TADLF 2a 1 2

~

RADIOACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS GASEOUS SOURCE A ~

WASTE GAS DECAY TAtIK RELEASES B

COtITAItttIENT PURGE RELEASES SAMPLING FREQUENCY EACH TANK EACH PURGE TYPE OF ACTIVITY ANALYSIS P

NC PA G

MA E TTERS P

NC PA GA A

E TT RS DETECTABLE CONCENTRATIONS Uci 10-4 (>)

10 6 10-4 (2) 1 -6 C

CONDENSER AIR EJECTOR I

MONTHLY PR C

PA G

E TTCR 10-4 (2) (3) 1 -6 O

Vl C)

DE ENVIRONtIENTAL RELEASE POINTS MONTHLY (GAS SAHPLES)

WEEKLY CHA COA SA P

E MOt THL CIIARCOA SAHPL WEEKLY (PART I CULATCS)

(4)

MONTHLY CotIPOSITE (PARTICULATES)

QUARTERLY CotIPOSITC (4)

P T

CU AT S

PR NC PA GA E

T R

I-1 1

I-1 I-1 PR I tIC I PAL GAIINA ENI TTCRS T LEAST F R BA LA-140 I-1 1

SR-8 GROSS CI SR-90.

4 (2) (>)

1 -6 10 12 10 10 io 11 1 Q 1 1 10 11 1 Q 1 1

Table 2.1-2 (cont'd.)

r NOTES:

(1)

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

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

(2)

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

(3)

Por certain mixtures of gamma 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 calcu-late the levels of such radionuclides using observed ratios with those radionuclides which are measurable.

(4)

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

Amendment Nos.

54

& 40

Y TAsl.c 2.1-j LOCAT IXI OF PIIOCESS AttO EIFLUfttf TctttlTOIIS AIIO SAtlti.IS AE ulttEU OT TECtltllchL SPECIFICATlottS

~Pct

~

Il

~sr P

Cl CAH ~ STATION OAAINACC ASTI: IIOLD UP I AIIK A

X AUTO CONTROL TO 150ISA ION V~g CONT lltUOUS GtnAO SAIIPLC S~AT~OI Gnoss OlssoLvco looTorlc I

~G

~A IL'~~

X X

X X

CHCNICAL UnAIH TANK LAUHonv/IIOT Snoucn TANK' AIIIAAYCOOLAHI'YSTKN A

X A

X X

X LIOUlo OADVASTC OIDCHAAOC I IPC I

STEAII GENCNATOR IILOVOOQN SYS'TCII

. Scnvlcc MAYcn OlscHAnac I'lpc X>

II X

OUTDOOR STORACC TAtIKS ttUCLCAn Cl.osco COOLINC STSTKN TUAOltlC OUILOIHO SUHPS (FLOOR OAAINS)

A X

A LIUUIO LEVCL HIOH ID CL ID c+

I' UI

-5 4

VHCN ACTIVITY IN THC ConrotICNT CDDLltlo MATCA SYsTctl (CLOS) cxcccos 10 tllcRDCUAICs/tlL AtlD A LCAK IH THC CCSIS IS OOSCAVKU ~

CROSS AC'Tl V ITY IH THC SEAVICC VATCR 0 I SCHAROC VILL DC DCTEAHINCO (OY OHAO SAIIPLC AHALYSSS) 'OAII Y ~

fADLc 2. 1-11 LOCATIOII OF PAOCESS ANO EfFLOENf mNI fOIlS ANO SAfIILES llE UIIIEI) DY TECNNICAL SPEC lf ICAfIONS Pt10 ftf~S~A~itf fl~Ag PO ~N

~An AUYo CoHTROL Yo

~OA ~Ott V~g ColtT ltluous GRAD SANPLC NG II A Un HCN I

~PA n

~ll-MA&YE ItAs STonAoc TAIIKS X

Conocnscn AIR Euccton VcNY llc*ocn SYSYCtt'UILD IHO VCNTILA'TIoil SY&'YCIIS Ilc*OTOR CotlTA INtlcnT BUILolna (MIICttCVC.I YIICtlC IS FLOM)

AUXILIARYBUILDIN&

X

~tt Xt Foci. l4HDLIno & SYonAoc BUILD Itto X

X X

lIADUARYC BUILDIHO X

X YCAH GctlCR Ton BLoltDOMN TANK VcttT Oll Cottocnscll VctlY funolnc GLANo ScAI. Conocnscn MASYE EYAponAYon Conocnscn vcttT X

IF AHY on ALL ol Tnc rnoccss

&YncAtls on OUILoINO VEttTILATIDH &Yslct1s Anc RouTCO To A s IN&LE RCLFASE poIHTt 'Itic Hcco Fon A cott Ylnuouf I'toHI TOR AT Tttc INDI VI lluAL D I SCIIAROC POINT To TIIC ttAIN CXHAUST DUCT I S CL ININAYCD~

ONE COH Y INUOUS 110HI Ton AT YltE F INAL RELCA E POINT IS Surf ICIENY~

0Vl Itt sottc PIIll 6 YNE STCAtl OEHERAYOR OLOMDO'MN TANK VENT Is ROUTED To TNL HAIN TURDINC COHOEHSEII AHO YIIE NEED FOR A CONTINUOUS t1ONI'YOR AT AY Tilts RCI.CASE I'0 tH'Y IS CL IIIIHAYCO~

fttc Aux ILI ART BUILD Inc vcNT ILAT ION IlusY oh MILL I ODLAYc TltE MA&'IE GAO STonAoc fARK&

TABLE 2.1-5 AVERAGE ENERGY PER DISTINTEGRATION (1)

ISOTOPE EG ma Mev/dis I

EBeta Mev/dis (2) l Kr-83m Kr-85 Kr-85m Kr-87 Kr-88 Kr-89 Kr-90 Xe-131m Xe-133 Xe-133m Xe-135 Xe-135m Xe-137 Xe-138 Ar-41 0.0026 0.0022 0.1577 0.7931 1.9545 1.8344 1.2715 0.0201 0.0453 0.0415 0.2479 0.4307 0.1877 1.1258 0.4640 0.0382 0.2505 0.2553 1.3235 0.3648 1.3620 1.3151 0.1422 0.1355 0.1902 0.3182

0. 0958 1.7687 0.6315 1.2836 (1)

ORNL/NVREG-70 (NVREG/CR-1413 ),

A Radionuclide Decay Data Base Index and Summary Table, D. C. Kocherr Mayl 1980, (2)

The average Beta energy is taken from the "all electrons" column of the reference indicated in (1) above.

2-18 knendment Nos.

54 8 40

3.0 3.1 ENVIRONMENTAL SURVEILLANCE RADIOLOGICAL ENVIRONMENTAL MONITORING

~ct 'ctive 1.

To establish a sampling schedule which will assure recognition of changes in radioactivity in the environment surrounding the plant.

2.

To verify that offsite concentrations of radioactive materials and doses due to plant operation are within allowable limits.

S ecification 1.

Samples shall be collected and analyzed according to the schedule established by Table 3.1-1.

2.

This program shall be continued until four years after licensing of Unit 2*, at which time the licensee will evaluate the extent to which the program has met its objectives, and may request from the NRC permission to implement changes in the program.

3.

Suitable analytical procedures shall be used to determine the radioiodine content of milk to. a sensitivity of 0.5 picocuries per liter of milk at the time of sampling.

Overall error (one sigma confidence level) of this analytical procedure will be within 2 25%.

4.

5.

Milk samples shall be obtained from those milk-producing cows actually in the area of highest dose potential.

An annual survey shall be made during the grazing season to confirm that no milk producing cows are closer than the closest cow now sampled.

V Deviations are permitte$ from the required sampling schedule if biological specimens are not obtained or if due to the malfunction of an automatic samplere Zf the latter, corrective actions shall be completed prior to the end-of the next sampling period.

All deviations from the sampling schedule shall be described in the annual reports.

Re ortin Reauir ements A.

Rcutine Reports 1'.

The annual report, specified Section 5, shall contain:

a.

A narrative summary of the results of offsite airborne environmental surveys performed during the report period.

• Unjt 2 Low Power License dated December 23, 1977.

Amendment Nos: 54 5 40 3-1

I For each medium sampled during the year, a list of the sampling locations, the total number of samples, and the highest,. lowest, and the yverage concentrations for the highest location.

co Figures showing locations of offsite and onsite sampling locations.

2.

In the event that some results are not available within the 60 day period, the report should 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.

3.

If statistically significant variations of offsite environ>>

mental radionuclide concentrations.with time aze observed, a comparison of these results with'ffluent releases shall be provided.

~

4.

Individual samples which show higher than normal levels (25%

above background for external dose, or twice background for radionuclide content) will be noted in the report.

B.

Non-Routine Reports (See Non-Routine Reports, Section 5.4.2)

Prompt Report If a measured level of radioactivity in critical pathway environmental media samples indicates that the resultant annual dose to an individual from these levels could equal or exceed 4 times the design objective, a determination will be made as to whether or not such levels of radio-activity are attributable to plant operation.

If attribu-able to plant operation a zeport will be made to the Region IIIOffice of Inspection and Fnforcement within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> and a plan will be submitted within 10 days advising the NRC of the proposed action to ensure the plant related annual doses will be within the design objective. If not attributable to plant operation, the zationale for this conclusion shall be included in the annual report.

2.

30-Day Report If samples of critical pathway environmental media collected over a calendar quarter show total levels of radioactivity that could esult in accumulated olant related doses. to an individual for that quarter of 4 the annual design objective or for any 2 consecutive quarters of 3/4 the annual design objective a determination will be made as to whether or not such levels or radioactivity are attributable to plant 3-2 Amendment Nos.

54 II 40

operation.

Xf attributable to plant operation, the results shall be reported within 30 days and a plan submitted and implemented within 30 days to limit conditions so that the annual dose to an individual will not exceed the design objective. lf not attributable to plant operation, the rationale for this conclusion shall be included in the annual report.

Basis:

The survey program is designed to allow the licensee. to:

l.

Assure compliance with Technical Specifications and Federal Regulations by measurement of radiation levels in samples of selected media.

2.

Differentiate releases of plant origin from natural or other sources of radiation in the environment.

- This is accomplished by using a

~

reference (background) ring of sampling stations and an indicator (site vicinity) ring of sampling stations.

Calculations are then made. which show whether or not a statistical difference exists between the levels of radioactivity detected in the site vicinity and those detected remotely from the site.

Also, analysis for specific radionuc'ides are made in the sample media which can be related to,known plant releases of the same radionuclide.

3.

Hake dose estimates if significant increase in radiation levels are detected by the survey.

This is accomplished by samp'ing signi i-cant media and using sufficient sensitivity in sample analysis to detect concentrations far below maximum permissible concentrations.

The reporting re<pxirements assure that the NRC will be informed of the results of the survey on a regular bas's, and will be informed promptly of any results that indicate that annual design objectives may be exceeded.

They,r~uire the licensee to take steps to assure that annual doses will be within design objectives, and to inform the NRC of such steps, should monitoring indicate that the annual

'design objective may be exceeded.

3-3 Amendment Nos.

54 5 40

TABLE P 1-1 i<AD I OLOG IGAL ENV IBONMENTAL f%N ITOI< ING PIIOGAAM OONALO C.

COOI( NOCLLtAA PLANT SPMr L-T No ~

STATIONS lttn. BKC.

COLLECTION FRE UENCY ArtALYsls F~ss s N s TYPE

~Asscvs s

REMARKS AIR PARTICULATE 6

ll WEEKLY WEEKLY MONTHLY OUAttTERLY GRoss.BETA GAMMA SPECTRAL.

COMPOSITE OF WEEKLY SAMPLES SR 89, SR-90 (COMPOSITE)

BY IND I GATOR AND BACKCROUND SAMPLES AJROORrtE I-1/1 WEEKLY WEEKLY GAMt'IA SPECTRAL BY INDICATOR AND BACKGROUND SAMPLES PRE C JP I TAT I Ott MONTHLY MoNTIILY CHEMI-ANNUALLY GAMMA SPECTRAL COMPOSITE

SR9, SR-90 (COMPOSITE)

BY INDICATOR AND OACKCROUND SAMPI ES O

Vl LAKE WATER MONTHLY DR 2JJ HoURs AFTER A OATCH RELEASE QUARTERLY MONTHLY TR JT.IUMt SR9>90

('CottPOS I TE OF COLLECTED SAMPLES)

GAMMA SPECTRAL (COMPOSITE OF COLLECTED SAMPLES)

BY INDI GATOR AND SACKCROUNO SAMPLES TMO INDICATOR STATJ

MJLI, INCLUDE THE NEA EST PUIILJC MATER JN-

'TAKES ON THE LAKE NORTH ANO SOUTH OF THE PLAIIT WELL WATER CD EVERY 18 WKS ~

EVERY 18 WKS TR I TI UM GAMMA SPECTRAJ PlsH 2/YEAR 2/YFAR GAMI1A SPECTRAL SR-89, 90.

~D IOLE PORTION ONLY WEATttER FERMI TT INC

TAOLf $.1-1 (CoNTIHUKD)

RADIOLOG ICAL fNVIRONMfNTALMONITORING PROGRAM OONALO C.

COOK Nl/CLfAR PLANT.

No ~

STATIONS IND. OKG.

COLLECTION FRE UENC ANALYSI S

~R E IREE IIC TYPE

~ANKL E

R RENKRKE AQUATIC OAGANISI15'R VEGETATION (AS AVAILABLE) 2/YKAn 2/YEan GAI1t1A SPECTRAL S4-S7, SR-90 MILK MONTHLY MOtlTHLY MoNTIILY I-1>1 Gatltla SPECTRAL SR-89, SR-90 SKO Jt1EtlT 2/YEAR 2/YEAn GAI1tIA SPECTRAL SR-89, SR-90 4'LO I

Ilut1AN Fooo Cnol s QUARTERLY ANNUALLY QUARTERLY ANNUALLY ToTaL DosK GAHtIA SPECTRAL

~

~ ~

THRFK ItlD I GATOR STATIONS SHALL BE WITHIN 5 t1ILES OF THE PLANT.

IF FEWER THAN FOUR LOCATIONS 11EET INC TH IS REQUIREt1ENT ARE AVAILABLE'HENUHOEA OF IND I GATOR STATIONS t1AY BE REDUCED~

0M HE TWO BACKGROUND STAT I ONS SHALL BE BETWEEN 5 AND 20'lILES OF TJIE PLANT IF FEWER THAN THREE LOCATIONS t1EET ING THI S AEQUI AEI1EtlT AAC AVAILABLE THE NUMBER OF BACKGAOUNO STATIONS t1AY BE REDUCED ~

AT LKAST OtlE OACKCROUND STAI'ION SHALL BE ESTABL I SIIEO W I TH IN 50 t1I LES OF THE PLAtlTy IF AVAILABLE~

4.0 SPECIAL SURVEILLANCE AND STUDY ACTIVITIES None 4-a Amendment Nos 54 II 40

5.0 ADMINISTRATIVE CONTROLS 5.1 ORGANXZATXONt REVL.W AND AUDIT-Organization, review and audit shall be in accordance with Section 6, Appendix A.

5.2 ACTXON TO BE TAKEN IF A LIMITINGCONDITION FOR OPERATION IS EXCEEDED Remedial action permitted by the Environmental Technical Specifications will be performed until the condition can be met.

The occurrence of exceeding a limiting condition will be inves-tigated by the Plant staff as directed by the Plant Manager.

2.

A separate report for each occurrence will be prepared as specified in Section 5.4.2.1.

This report shall include an evaluation of the cause of the occurrence, and recommendations for appropriate action to prevent or reduce the probability of recurrence.

5.3 PROCEDURES Detailed written procedures, including applicable check lists and instructions, shall be prepared and adhered to for all act'ivities involved in carrying out the recpxirements of the Part I, Appendix B Technical Spec'ications.

Procedures shall include sampling, instrument calibration, analysis, and actions to be taken when limits are approached or exceeded.

Testing frecpxency of any alarms shall be included.

These fre~encies will be determined from experience with similar instruments in similar environments and from manufacturer's technical manuals.

2.

In addition to the procedures specified above, the Plant operating procedures shall include provisions to ensure that the Plant's systems and components

.are ooerated in compliance with the limit-ing conditions for operations established as part of the Fnviron-mental Technical Specifications.

3.

The Plant procedures described

above, and all changes thereto, will be reviewed and approved prior to implementation.

Temporary changes to Plant procedures which do not change the intent or capability of the original procedure may be made, provided such changes are approved in writing by two members of the Plant management staff.

S'uch,changes will be documented and reported 'to the Regulatory staff.

Any such changes which affect data required in the annual Operating Report shall be described. in those reports.

5-1 Amendment Nos.

54 Im 40

I

.)

5 4

0-PLANT REPORTING RE UZREMENTS 5.4.1 Routine Re orts A.

Radioactive Effluent Release Re ort 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 effluents released as outlined in Regulatory Guide 1.21 with data summarized on a quarterly basis following the fozmat of Appendix B thereof.

The report shall include a summary of the meteorological conditions concurrent with the release of gaseous effluents during each quarter as outlined in.Regulatory Guide 1.21, with data summarized on a quarterly basis following the fozmat of Appendix B thereof.

Calculated offsite dose to humans resulting from the release of effluents and their subse-quent dispersion in the atmosphere shall be reported in accordance with Regulatory Guide 1.21.

a ~

Gases Quarterly sums of total curies of fission and activation gases released.

2 ~

Average release zates (uCi/sec) of fission and activation gases for the auarterly periods covered by. the report.

3.

Percent of technical speci ication limit for release of fission and activation gases.

This should be calculated in accordance with technical specificatton limits.

4.

Quarterly sums of total curies for each of the radio-nuclides determined to be released based on analyses of fission and activation gases.

The data should be categozed by (1) elevated

releases, batch and continuous

modes, and.(2) gzound level releases, batch and contin-uous modes.

.b.

Todines 1.

Quarterly sums of total curies of iodine-131 released.

2.

Average release rate (uCi/sec) of iodine-131.

3. 'ercent of technical specification limit for iodine-131.

4.

Quarterly sums of total curies of each of the isotopes, iodine-131, iodine-133, and iodine-135 determined to be released.

5-2 Amendment Nos.

54 5 40

Cg c.

Particulates 1.

Q'uarterly sums of total curies of radioactive material in particulate form with half-lives greater than 8 days determined to be released.

2.

Average release rate (uCi/sec) of radioactive material in

" particulate form with half-lives greater than 8 days.

3.

Percent of technical specification limit for radioactive material in particulate-form with half-lives greater than 8 days.

4.

Quarterly sums of total curies for each of the radio-nuclides in particulate form determined to be released based on analysis performed.

5.

Quarterly sums of total curies of gross alpha radio-activity determined to be released.

d.

Tritium 1.

Quarterly sums of total curies of tritium determined to be released in gaseous effluents.

2..Average release rate (uCi/sec) of tritium.

3.

Percent of appropriate technical specification or MPC limits for tritj.um.

e.

Mixed Fission and Activation Products.

1.

Quarterly sums of total curies of radioactive material determined to be released in liquid effluents (not including tritium, dissolved and entrained

gases, and alpha-emitting material).

2.

Average concentrations (uCi/ml) of mixed fission and activation products released to unrestricted

areas, averaged over the quarterly periods covered by the report.

3.

Percent of applicable limit of average concentrations released to unrestricted areas.

Xnclude the limit used and the bases in the supplemental report information.

E

4. 'uarterly sums of total curies for each of the radio-nuclides determined to be released in liquid effluents, based on analysis performed.

Data should be separated by type of release mode, i.e., continuous or batch.

5 3

Amendment Nos.

54

& 40

O f.

Tritium 1.

Quarterly sums of total cuzies of tritium determined to be released in liquid effluents.

2.

Average concentrations (uCi/ml) of tritium released in liquid effluents to unrestricted

areas, averaged over the quarterly periods covered by the report.

3.

Percent of applicable limit of average concentrations

'eleaseg to unrestricted areas, i.e., percent of 3 x 10 uCi/ml.

Include the limit and the bases in the supplemental report information.

g.

. Dissolved and Entrained Gases Quarterly sums of total curies of gaseous radioactive material determined to be released in liquid effluents.

2.

Average concentrations (uCi/ml) of dissolved and entrained gaseous radioactive material released to unrestricted

areas, averaged over the quarterly periods covered by the report.

3.

Percent of technical specification limit of average concentrations released to unrestricted areas.

Include the limit used and the bases in the supplemental report information.

4.

Quarterly sums of total curies for each of the zadio-nuclides determined to be released as dissolved and entrained gases in liauid effluents.

h.

Al ha Radioactivit Quarterly sums of total curies of gross alpha-emitting material determined to be zeleased in liquid effluents.

Volumes 1.

Quarterly sums, in liters, of total measured

volume, prior.to dilution, of liauid effluent zeleased.

2.

Quarterly sums of total determined 'volume, in liters, of dilution water used during the period of the report.

Solid Waste The following information should be reported for shipments of solid waste and irradiated fuel tzansported from the site duping the report period:

5-4 Amendment Hos.

S4 R 40

The semiannual total cpxantity in cubic meters and the semiannual total radioactivity in curies for the cate-gories or types of waste.-

a)

Spent resins, filter sludges, evaporator bottoms; b)

Dry compressible

waste, contaminated epxipment, etc.;

c)

Irradiated components, control rods, etc.;

d)

Other (furnish description).

2.

3.

An estimate of the major nuclide composition in the categories of waste above.

The disposition of solid waste shipments.

(Identify the number of shipments, the mode of transport, and the destination.)

4.

The disposition of irradiated fuel shipments.

(Identify the number of shipments, the mode of transport, and the destination.)

Radiolo ical I act, on Man Potential doses to individuals and populations should be calculated using measured ef luent and meteorological'ata.

A semiannual summary report should be submitted containing the following information:

Total body and significant organ doses to individuals in unrestricted areas from receiving-water-related exposure pathways.

2.

Total body and skin doses to individuals exposed at the point of maximum offsite ground-level concentrations of radioactive materials in gaseous effluents.

3.'rgan doses to individuals in unrestricted area f om radioactive iodine and radioactive material in parti-culate form from all pathways of exposure.

4 ~'otal body doses to individuals and populations in unrestricted areas from direct radiation from the facility.

5.

Total body doses to the population. and average doses to individuals in the population from all receiving-water-related pathways.

6.

Total body doses to the population and average doses to individuals in the population gaseous ef luents to a distance of 50 miles. from the site. If a signi i-cantly large population area is located just beyond 50 miles from the site, the dose to this population group should be considered.

Amendment Nos.

54 a 4()

Aeteorolo ical Data The report should include the cumulative joint frequency dist ibution of wind speed, wind direction, and atmospheric stability for the stabili y for the quarterly periods.

Similar data should be reportred separately for the meteorological conditions during batch releases.

5.4.2 Nonroutine Re orts 5.4.2.1 Abnormal Environmental Occurrence

{AEO)

Zn the event of an AZO, as defined in Section 1.0, a report shall be submitted under one of the report schedules described below.

1.

Promot Reuort.

Those events requiring prompt reports shall be reported within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> by telephone, t'elegraph, or facsimile transmission to the Director of the NRC Regional Office and within 10 days by a written report to the Director of the Regional NRC Office (with a copy to the Director, Office of Nuclear Reactor Regulation.

be reported within 30 days by a written report to the Director of the NRC Regional Office (with a copy to the Director, Office of Nuclear Reactor Regulat'on).

The reporting schedule for reports concerning limiting conditions for operation and report levels aze specified in the technical specifications.

Reports concerning unusual or important AEO's shall be reported on the prompt schedule.

The significance of an unusual or apparently important event with regard. to environ-mental impact may not be obvious or fully appreciated at the time of occurrence.

Zn such cases, the NRC shall be informed promptly of.changes in the licensee's

'assessment of the signifi-cance of the event and a corrected report shall be submitted as expeditiously as possible.

The written report,,

and to the extent, possible the preliminary telephone and telegraph report, shall:

(a) describe, analyze and evaluate the AEO, including extent and magnitude of the impact, (b) describe the cause of the AEO, and. (c) indicate the corrective action (including any significant changes made in procedures) taken to preclude repeti-tion o2 the AEO and to prevent similar AEO's involving similar components or systems.

5.4.2.2

~Chan es When a change to the Plant design, to the Plant operation, or to the procedures described in Section 5.3 is planned which involves an environ-mental matter.oz cuestion not previously reviewed and evaluated by the

NRC, a report on the change shall be made to the Office of Nuclear Reaator Regulation prior to implementation.

The report shall include a" description and evaluation of the change.

5-6 Amendment Hos.

54 8 40

~ I Changes or additions to permits and certificates required by Federal,

state, local and'regional authorities for the orotection of the eriviron-ment shall be reported.

When the requir d changes are submitted to the concerned agency for approval, they shall also be submitted to the Director, Office of Nuclear Reactor Regulation, USNRC, for information..

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

Request for changes in environmental technical specifications shall be submitted to the Director, Office of Nuclear Reactor Regulation,

USNRC, for prior review and authorization.

The request shall include an evalu-ation of the impact of the change,'ncluding a supporting benefit-cost analysis.

5.4.2.3, Radioactive Discha es The reporting requirements for radioactive discharges are specified in Section 2.1 of the Environmental Technical Specifications.

5; 4.2. 4 Radiolo ical Environmental Monitorin Reporting involving radi.ological environmental monitoring is discussed in Section 3.1 of the Environmental Technical Specifications.

5.5 5.5.1 RECORDS RETENTION Records Retained for Life of Plant Records and logs relative to the following areas will be retained for the life of the Plant:

a ~

b.

Records and drawing changes reflecting Plant design modifications made to systems and eauipment as described in Section 5.4.2.2.

V Records of radiologica3, environmental surveillance data.

c.

Records to demonstrate compliance with the limiting conditions

'or operation in Section 2.

5.5.2 Records Retained for Five Years All other.records and logs relating to the Environmental Technical Speci ications Part 1 shall be retained for five years.

5-7 Amendment Nos.

54

& 40

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APPENDIX B ENVlRONMENTAL TECHNICAL SPECIFICATIONS FOR DONALD C.

COOR NUCLEAR PLANT UNITS 1 and 2

BERRIEN COUNTY, MICHIGAN D~T NUMBERS 50-315 and 50-316 PART IZ - NONRADZOLOGZCAL EWTIRONMENTAL PROTECTION PLAN

DONALD C.

COOK NUCLEAR PLANT UNITS 1 and 2

ENVIRONMENTAL PROTECTION PLAN (NON-RADIOLOGICAL)

TABLE OF CONTENTS Section Pacae 1.0 Objectives of the Environmental Protection Plan..

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1 1 2.0 Environmental Protection Issues..................

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2 1 2.1 Aquatic Issues..........

2-1 2.2 Terrestrial 1ssues.....

2-1 3.0 Consistency Requirements...................................

3.1 Plant Design and Operation................,...........

3 11 3.2 Reporting Related to the NPDES, Permits and State Certification...............

3-2.

3.3 Changes Required for Compliance with Other Environmental Regulations............................

3-2 4.0 Environmental Conditions..

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4. 2.

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

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4>>1 5.0 0

Adminxstrative Procedures....

5-1 5.1 eview and Audit o ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~

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R 5-1 5.2 Records Retention..............

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5.3 Changes in Environmental Protection Plan.............

5-1 5.4 Plant Reporting Requi ements....=.....

5-1 Amendment Nos.

54 5 40

1.0 OBJECTIVES OF THE ENVIRONMENTAL PROTECTION PLAN The Fnvi onmental Protection Plan (EPP) is to provide for protection of environmental values during construction and operation of the nuclear facility.

The principal objectives of the EPP are as follows:

(1)

Verify that the station is operated in an envixonmentally acceptable

manner, as established by the FES* and other NRC environmental impact assessments.

(2)

Coordinate NRC repxirements and maintain. consistency with other Federal, State and local repxirements for environmen-tal protection.

(3)

.Keep NRC informed of the environmental effects of facility'onstruction and operation and of actions taken to control those effects.

Environmental concerns identified in the FES which relate to water cpxality matters are regulated, by way of the licensee's NPDES permit.

~Final Environmental Statement Amendment Has.

54

& 40

2.0 ENVIRONMENTAL PROTECTION ISSUES Zn the FES-OL dated August 1973, the staff considered the environmental impacts associated with the operation of the Donald C. Cook Nuclear Plant.

Certain environmental issues were identified which required study or license conditions to resolve and to assure adequate protection of the environment.

The Appendix B Environmental Technical Specifications

- accompanying the license included monitoring programs and other require-ments to permit resolution of the issues.

Prior to issuance of this EPP, the requirements remaining in the ETS were:

2.1 Aquatic Issues 1.

Protection of the aquatic environment by limiting the thermal

- stress to which aquatic organisms will be sub)ected during transit through the plant.

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2.

The avoidance of possible adverse effects on lake biota due to deicing operations.

I'.

Protection of aquatic life by limiting the release of chlorine from plant operation.'.

Monitoring of the movement of chemicals introduced into the groundwater f om the onsite absorption field.

5.

Limit the plant discharge of corrosion and deposit inhibitors used in the plant systems.

6.

The need for aquatic monitoring to confirm that effects on phytoplankton, periphyton, zooplankton, benthic invertebratesf and fish due to plant operation are no greater than predicted.

7.

The need for special studies to document levels of intake ent ainment and impingement in relation to the densities of important species in the plant vicinity.

S.

The need for visual underwater observations in the intake and discharge area to observe the physical and ecological conditions.

hese Aquatic Issues are addressed by the effluent limitations, monitoring requirements and the Section 316(b) demonstration requirement contained in the effective NPDES permit issued by the state of. Michigan, Department of

'atural Resources.,

The HRC will rely on this agency or regulation of matters involving water cuality and aquatic biota.

Z.2 Terrestrial Issues The remaining terrestrial issue is the need for controlled use of herbicides if such are'used for maintenance of transmission rights-of-way.

NRC require-ments with regard to this ter estrial issue are specified in Subsection 4.2.

2-1 Amendment thos.

54 8 '40

3.0 CONSISTENCY REQUIREMENTS 3.1 Plant Design and Operation The licensee may make changes in station design or operation or perform tests or experiments affecting the environment provided such changes, tests or experiments do not involve an unreviewed environmental question, and do not involve a change in the Environmental Protection Plan.*

Changes in plant design or operation or performance of tests or experi-

'ents which do not affect the environment are not subject to the require-ments of this EPP.

Activities governed by Section 3.3 are not subject to the requirements of this section.

Before engaging in'unauthorized construction or operational activities which may affect the environment, the licensee shall prepare and 'record an environmental evaluation of such activity..

When the evaluation indicates that such activity involves an unreviewed environmental

question, the licensee shall provide a written evaluation of such activities and obtain prior approval from.the NRC.

When such activity involves a change in the Environmental Protection, Plan, such activity and change to the Environmental Protection Plan may be implemented only in accordance with an appropriate license amendment as set forth i' Section, 5.3.

A proposed

change, test or experiment shall be deemed to involve an unreviewed environmental auestion if it concerns (1) a matter which may result in a significant increase in any adverse environmental impact previously evaluated in the final environmental statement (FES) as modified by staff's testimony to the Atomic Safety and Licensing Board, supplements to the FES, environmental impact appraisals, or in any decisions of the Atomic Safety and Licensing Board> or (2) a significant change in ef luents or power level [in accordance with 10.CFR.Part. 51.5 (b)(2)] or (3) a matter not previously reviewed and. evaluated in the documents specified in (1) of this Subsection, which may have a signifi-cant adverse environmental impact.

The licensee shall maintain records of changes in facility design or operation and of tests and experiments carried out pursuant to this Subsection.

These records shall include a written evaluation which provide bases for the determination that the change, test, or experiment does not involve an unreviewed environmental auestion nor constitute a

decrease in the effectiveness of this EPP to meet the objectives specified in Section 1.0.

The licensee shall include as part of his Annual Envir'onmental Operating Report (per Subsection 5.4.1) brief description,

analysis, interpretations, and evaluations of such 'changes,, tests and experiments.

• This prov'sion does not relieve the licensee of the reauirements of 10 CFR 50.59-3-1 Amendment.Hos.

54 5 40

3.2 Reporting Related to the NPDES Permits and State Certifications Violations 'of the NPDES Pezmit or the State certification (pursuant to Section 401 of the Clean Water Act) shall be reported to the NRC by sub-mittal of copies of the reports required by the NPDES Permit or 'certifi-.

cation.

Changes and additions to the NPDES Permit or the State certification shall be reported to the NRC within 30 days following the date the change is approved.

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

Zhe NRC shall be notified of changes to the effective NPDES Pezmit pro-posed by.the licensee by providing NRC with a copy of the proposed change at the same time it is submitted to the permitting agency.

The licensee shall provide the. NRC a copy of the application for renewal of the NPDES permit at the same time the application is submitted to the permitting agency.

3.3 Changes Required for Compliance with Other Environmental Regulations Changes in plant design or operation and performance of tests or experiments which are required to achieve compliance with other Federal,

State, or local 'environmental regulation are not subject to the requirements of Section 3.1.

3-2 Amendment Nos.

54 5 40

4.0 4.1 ENVIRONMENTAL CONDITIONS Unusual or Important Environmental Events Any occurrence of an unusual or important event that indicates or could result in significant environmental impact related to plant operation shall be recorded and promptly reported to the NRC within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> by telephone, telegraph, or facsimile tzansmissions followed by a written report per Subsection 5 ' '.

No routine monitoring programs are repxired to implement this condition.

4.2 Environmental Monitoring 4.2 '

Herbicide Application The use of herbicides within rights-of-way within the Plant site shall conform to the approved use of selected herbicides as registered by the Environmental Protection Agency and approved by State authorities and applied as directed by said authorities.

4 1 Amendment Hos.

54

& 40

5.0 5.1 ADMXNISTRATZVE PROCEDURES Review, and Audit The licensee shall provide for review and audit of compliance with the Environmental Protection Plan.

The audits shall be conducted indepen-dently of the'ndividual oz groups responsible for performing the specific activity.

A description of the organization structure utilized to.

achieve the independent review and audit function and results, of the audit activities shall be maintained and made available for inspection.

5.2 Records Retention Records and logs relative to the environmental aspects of plant operation shall be made and retained in a manner convenient for review and inspec-tion.'hese records and logs shall be made available to NRC on request..

r Records of modifications to plant structures, systems and components determined to potentially affect the continued protection of the environ>>

ment shall be retained for the life of the plant All other records, data and logs relating to this EPP shall be retained for five yeazs or, where applicable, in accoidance with the requirements of other agencies.

5.3 Changes in Envizonmental Protection Plan Recuest for change in the Environmental Protection Plan shall include an assessment of the environmental impact of the proposed change and a support-ing justification.

Lmplementation of such changes in the EPP shall not commence prior to NRC approval of the proposed, changes in the form of a license amendment incorporating the appropriate revision to the Environ-mental Protection Plan.

5.4 Plant Reporting Requirements V

5.4.1 Routine Reports An Annual Environmental Operating Report describing implementation of this EPP for the previous year shall be submitted to the NRC prior to May 1 of each year.

The initial report shall be submitted prior to May 1 of the pear following issuance of the EPP.

The report shall include summaries and analyses. of the results of the environmental protection activities required by Subsection 4.2 of this Environmental Protection Plan for the report period, including a com-parison with preoperational

studies, operational controls (as, aporo-pziate'),

and previous nonradiological environmental monitoring reports, and an assessment of the observed impacts of the plant operation on the environment.

Zf harmful effects or evidence of trends towards irrever-sible damage to the environment are observed, the licensee shall pro-vide a detailed analysis of the data and a proposed course of action to alleviate the problem.

Amendment Nos.

54 8 40

The Annual Environmental Operating Report shall also include:

(a)

A list of EPP noncompliances and the corrective actions taken to remedy them.

(b)

A list of all changes in station design or operation,

tests, and experiments made in accordance with Subsection 3.1 which involved a potentially significant unreviewed environmental issue.

(c)

A list of nonroutine reports submitted in accordance with Subsection 5.4.2.

In the event that.some results are not available by the report due date, the report shall be submitted noting and explaining the missing results.

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

5.4.2 Nonroutine Reports A written report shall be submitted to the NRC within 30 days of occurrence of nonroutine event.

The report shall (a) describe, analyze and evaluate the event, including extent and magnitude of the impact and plant oper-ating characteristics, (b) describe the probable cause of the event, (c) indicate the action taken to correct the reported event, (d) indicate the corrective action taken to preclude repetition of the event and to prevent, similar occurrences involving similar components o" systems, and (e) indicate the agencies notified and their preliminary responses.

Events reportable under this subsection which also reguire reports to other Pederal, State or local agencies shall be reported in accordance with those reporting recplirements in lieu of the repxirements of this subsection.

The NRC shall be provided a copy of such report at the same time it is submitted to the other agency.

5>>2 Amendment Hos.

54 IE 40

1'

APPENDIX B ENVIRONMENTAL TECHNICAL SPECIFICATIONS PART III NON PATER UALITY-NON-RADIOLOGICAL FOR DONALD C. 'COOK NUCLEAR PLANT UNITS 1 AND 2 BERRIEN COUNTY MICHIGAN DOCKET NUMBERS 50-315 AND 50-316 V'NITED STATES ATOMIC ENERGY COMMISSION DIRECTORATE OF LICENSING Issued:

~ay 6, 1 982

PAGES 2.1-1, 2.1-2, 2.1-3,',1-4, 2.1-5, 2.2-1 2.2-2, DELETED Amendment Hos.

54

& 40 2.1-1

PAGES 2.4-1, 2.4-2, 2.4-3, 2.4-4, 2.4-5, 2.4-6, 2.4-7, 2.4-8, 2.4-9, 2.4-10, 2.4-11, 2.4-12, 2.4-13, 2.4-14, 2.4-15, 2.4-16, 2.4-17, 2.4-18, 2.4-19, DELETED.

2,4-1 Amendment Hos.

54 E 40

PAGES 4.1-1, 4.1-2, 4.1-3, 4.1-4, 4.1-5, 4.1-6, DELETED 4.1-1 " Amendment Nos.

54 Im40

bed on any movement, or displacement, of material moved by alongshore currents in the vicinity and to the south and north of the scour beds.

Results of all monitorina or special studies necessary for model verification and demonstration of the effect of scour beds on along shore transport of sediment shall be reported in the annual Operating

'eports.

if bottom scouring or erosion resulting from th". high velocity di.scharoe, and/or implacement of the protective scour bed.."curs, and if judged to be. significant by the staff, 1) the licensee shall submit plans for corrective action to the staff for approval and 2) implementation'f any approved ac'tion shal.l be met by the time schedule specified'hould the 'scour study indicate loss of function of the scour bed, the licensee would initiate an Engineering investigation to repair the bottom protection in an appropriate fashion.

The licensee shall submit plans for corrective action to the Of ice of Nuclear Reactor Regulation for review and approval.

S. schematic view of the scour study area is shown in Figure 4.1.1.4-1.

Reocrtina Requirements Cs speci fi ed above and in Sect i on 5.4.

Basis ffter extensive

study, a jet diffuser system was'developed, with a jet velocity of 13-ft/sec selec.ed on the basis of experimen.ation with a i.ycraulic model, to r'educe the temperatures in the thermal-affected zone and to minimize the exposure of entrained organisms to heated

'i ke water.

Because of the re1atively high velocity of the cooling

~ ater at the exit ports of the discharge structure, an extensive scour protective bed has been installed.,The subject scour studies are to verify that there are no scour problems resulting from Plant discharges or irplacement of the riprap scour bed in the lake.

ETS 4,1 9

Amendment Nos.

54 5 40

PAGES 4.1.1.5, 4.1-9, 4.1-11, 4.1-12, 4;1-13, 4.1-14, 4,1-15, 4.1-16, 4;1-17, 4,1-18 to 4.1-39 DELETED 4.1-11 Amendment Nos.

54

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PAGES 4.2-1, 4,2-2, 4.2-3,'.2-10 DELETED 4,2-1 Amendment Nos.

54 IK 40

PAGES 5.4<<1, 5.4-2 to 5.4 7

DELETED Amendment Nos.

54 8 40

7590-01 The Commission has determined that the issuance of these amendments will not result in any significant environmental impact and that pursuant to 10 CFR 551.5(d)(4) an environmental impact statement or negative 'declaration and environmental impact appraisal need not be prepared in connection with issuance of these amendments.

For further details with respect to this action, see (1) the application for amendments dated November 4, 1981, (2) Amendment Nos.

54 and 40 to License Nos.

DPR-58 and DPR-74, and (3) the Commission's related Safety Evaluation.

All of these items are available for pub'lic inspection at the Commission's Public Document

Room, 1717 H Street, N.W., Washington, D.C.

and at the Maude Reston Memorial Library, 500 Market Street, St. Joseph, Michigan 49085.

A copy of items (2) and (3) may be obtained upon request addressed to the U. S. Nuclear Regulatory Commission, Washington, D.C.

20555, Attention:

Director, Division of Licensing.

Dated at Bethesda, Maryland this 6th day of May, 1982.

R THE NUCLEA 8

GULATORY COMMISSION n

. 'a, Chi Operating Reactors B an h

81 Division of Licensing

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1 UNITED STATES NUCLEAR REGULATORY COMMISSION 7590<<01 DOCKET NOS. 50-315 ANIL 50-316 INDIANA AND MICHIGAN ELECTRIC COMPANY NOTICE OF ISSUANCE OF AMENDMENT TO FACILITY OPERATING LICENSE The U. S. Nuclear Regulatory Commission (the Commission) has issued Amendment No.

54 to Facility Operating License No.

DPR-58, and Amendment

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No.

40 to Fanlsty Operating License No.

DPR-74 issued to Ind)ana and Michigan Electric Company (the licensee),

which revised Technical Specifications for operation. of Donald C.

Cook Nuclear Plant, Unit Nos.

1 and 2 (the facilities) located in Berrien County, Michigan.

The amendments are effective as of the date of issuance.

These 'amendments r elocate the radiological environmental Technical Specifications into a separate section Appdndix B Part I - Radiological and replace the non-radiological environmental Technical Speci.fications with Appendix B Part II - non-radiological, Environmental Protection Plan.

Remaining requirements of Appendix B are now called Part III non Mater

'I V'uality

- Non Radiological.

The application for the amendments complies with the standards and requirements of the Atomic. Energy Act of 1954, as amended (the Act), and the Commission s rules and regulations.

The Commission has=made appropriate findings as required by the Act and the Commission's rules and regulations in 10 CFR Chapter I, which are set forth in the license amendments.

Prior public notice of these amendments was not required since the amendments do not involve a significant hazards consideration.

4

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1 E nvi ronmenta 1

C ons iderati on We have determined that the amendments do not authorize a change in effluent types or total amounts nor an increase in'power level and will not result in any significant environmental impact.

Having made this determination, we have further concluded that the amendments involve an action which is insignificant. from the standpoint of environmental impact and, pursuant'o 10 CFR

$51.5(d)(4), that an environmental impact statement or negative declaration and environ-mental impact appraisal need not be prepared in connection with the issuance o'f these amendments.

C oncl us i on We have concluded, based on the considerations discussed above, that:

(1) because the amendments do not involve a significant increase in the probability or consequences of accidents previously considered and do not involve a significant decrease in a safety margin, the amendments do not involve a significant hazards consideration, (2)

-here is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed

manner, and (3) such activities will be conducted in compliance with the Commission's regulations and the issuance of these amendments will not be inimical to the common defense and security or to the health and safety of the public.

Oate:

May 6, 1982 The NRETS contain certatn w'ater quality related conditions.

In a memorandum dated December 7, 1979, from Howard K. Shapar to Harold R. Denton, it was stated that:

"The NRC's role in the water qua1tty area is 'limited to the weighing of aquatic impacts as part of its NEPA cost-bene'fit balance in its

'icensing decision.

That role does. not extend to including any conditions of its own in the license for the protectton of the aquatic environment.

Rather, EPA or those states to whom permitting authority

= has been delegated have been given exclusive responsibility for water quality protection and the regulation of water quality lies in the NPDES permit system."

"...ope'rating conditions on non-radiological aquatic matters and other non-radiological aquatic monitoring requirements are now the exclusive concern of EPA and permitting states and are not the responsibility of the NRC."

This memorandum also recommended that':

"...for those existing licenses where the facility holds an ef,ective NPDES permit, existing limiting conditions of operation or other non-radio 1 o gical aquatic moni tor in g requirements be deleted as*a matter of law, Since the deletion of these conditions would be a ministerial action required as a matter of law, no environmental impact assessment need be prepared as a condition precedent to taking the actions

h The Plant has an NPDES permit (No. 8I 0005827) and therefore the non-radiological aquatic monitoring. requirements ar e now the exclusive concern of EPA.

The NRC does have responsibility of 6eing aware of power plant performance as it effects environmental matters.

Consequently, the non-radiological water quality matters, while not controlled by the NRC, are monitored.

This is accomplished by. the'PP; The EPP has certain requirements which enable the NRC 'to perform its required environmental assessments.

These are strictly reporting of information as contrasted to the.limiting conditions of operation which have been deleted.

We'ave reviewed the proposed EPP submitted by the licensee and find that it satisfies the requirement of keeping the NRC.

informed of appropriate environmental matters concerning the plant.