ML18018B288

Submittal of Radioactive Effluent Release Report for the Period July 1, 1976 Through December 31, 1976, Including Meteorological Data in Accordance with Reg. Guide 1.23

ML18018B288
Person / Time
Site:	Nine Mile Point
Issue date:	02/23/1977
From:	Schneider R Niagara Mohawk Power Corp
To:	O'Reilly J Office of Nuclear Reactor Regulation, NRC Region 1
References
Download: ML18018B288 (202)

Text

DXSTRXBUTXON POR ANNUAL h SEMX-'ANNUAL ENVXRONMHI'ITALOPERATXNG REPORTS (OL STAGE).

U.S. NUCLEAR REGULATORi'MMISSION DOCKET NUMBER NpC F o RM'195 I2.78) Sa-Zz-e FILE NUMBER NRC DISTR I BUTION FoR PART 50 DOCKET MATERIAL ip ENVIRONMENTAL To: FROM: DATE OF DOCUMENT'/23/77 rh Niagara Mohawk Power Corp Mr. James P ~ O'Reilly Syracuse, New York DATE RECEIVED Ro Re Schneider 6/8/77 GALETTE R NOTORIZED PROP INPUT FORM NUMBER OF COPIES RECEIVED 0 ORIGINAL NC LASS IF I E D lBCOP Y DESCRIPTION ENCLOSURE Radioactive Effluent Release Report for the period July 1, 1976 through December 31, 1976 including meterological data in accordance with Regs Guide 1 ~ 23 ~ ~ ~

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PLANT NAME:

Nine Mile Point Unit No. 1 pP$ %I)

R JL 6/8/77 (1-P) =

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RATE FOR ACTION/INFORMATION LM. ASST.

~FOR DXSTRXBUTXON AS FOLLOWS:

1 EACH TO: EPA H A REGXON NOAA F8'c FM).

INTERNAL D ISTRI BUTION 2

BALLARD LL EXTERNAL DISTRIBUTION CONTROL NUMBER TXC 7 61003i =

NRC FORM 195 (2-78)

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NIAGARA MOHAWKIPOWER CORPORATION NIAGARA I~

I>II~m MOHAWK 300 ERIE BOULEVARD. WEST %egut2aory SYRACUSE. N. Y. 13202 Feb'3, 1977 h4,. James P. OIReiLLy NAe&oh, United S~es hluclem Reguku."oey Comm@sion Regin I (IIl ~I 631 Parck Avenue Kmg o$ P~s~, PA. 19406 IO RE: Nne NLe Pet Unit IIl Sock& No. 50-220 GeaII, h4.. O'Reilly:

In conformance Io&h PcvmgMph 5.6.2 o$ Che EnvMonmmtaL TechnicaL Speci.pcations tIoe hline hKEe Pef: Nucl~ S~on Unit <1, uIe arse enclosing She Radioactive E$ Quent Release RepoM $ oa She paused July 1, 1976 Chrcough OeceInbm 31, 1976. ALso included Lb mMeoM-Logical data m accordance uIith Regula'os Guide 1.23.

The, $ o~at used Joe She effluent data m as o~ed ~n ReguLatacy Guide 1.21. Om~b~on ask n accordance uIith Regulatory Guide 10.1.

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Vice PceskdeJLt-ELe~c Production MAS/mtm Enc. (2 copies.)

cc: Nrcmtox, Ofhce o$ Inspection and En)oacemeet (25)

Bmectoa, Management In(own~on and Paogtuun Co~ol (2)

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NRC FOAM 195 U.S. NUCLEAR REGULATORY COI'"<ISSION DOCKET NUMBEA I2-NI /41O FILE NUMBEA

~ NRC DISTRIBUTION FQR PART 50 DOCKET MATERIAL TO: FROM: DATE OF DOCUMENT Mr. J. M. Toennies New York State. Dept of Enviro 2-23-77 Conserration DATE RECEIVED Division of Pure Waters 3-2-77 LETTER Q Y~'I R IGINAL OP DESCRIPTION-NOTOR 12 E D jSUN C LASS I F I E 0 PROP INPUT FORM NUMBER OF COPIES AECEIVED 1 CC Consists of response to 2<<24-76 Ltr. Trans. The Followigg; request concerning denial of 401 Water Quality Certification.....

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'O NOT REMQVg NILE MILE POINT UNITS 1 ACKNOWrZDGZD SAFETY FOR ACTION/INFORMATION ASSIGNED AD:

MAK ~a-'47 BEGAN PROJECT MANAGER'IC L C ASST ASST INTERNAL DIST RI BUTION REG F LE SYSTEMS SAFETY PLANT SYSTEMS S TE SAFE NK HEINEMAN TEDESCO X & E SCHROEDER 0 A OELD GOSSICK & STAFF ENGINEERING XPPOLXTO MIPC MACARRY ERNST CASE BOSNAK BALLARD SIHWEXL OPERATING REACTORS SPANGLER HARLESS PAWL CK STELLO SXTE TECH PROJECT MANAGEMENT REACTOR SAFE OPERATING TECH GAMIIILL BOYD ROSS EISENHUT ~

STEPP P COLLINS NOVAK HULMAN HOUSTON ROSZTOCZY PETERSON CHECK SITE ANALYSIS MELTZ VOLLMER HELTEMES AT& I BUNCH SKOVHOLT SALTZMAN J ~ COLLINS

'UTBERG 'KREGER EXTERNAL DISTRIBUTION CONTROL NUMBER LPDR NAT LAB 0 TIC: REG V IE ~ULR KSON OR NSIC: LA PDR ASLB: CONSULTANTS:

ACRS CYS HOLDING/

NAC FOAM 195 (2.76)

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//@gal()~ ro Director, Envir onmenta't Affairs 4/cy /N Niagara (%hawk Power Corporation 300 Erie Boulevard Most Syracuse> flew York 13202 Re: 401 Water guality Certification Nine Nile Point I'nuclear SQhtion Unit 81

Dear Rr. Toennies:

Your request of. February 24, 1976 for recertification pursuant to Section 401 of the Fedora) Mater Control Act Amendments of 'l972 to supersede a previous certification issued April 9, 1974 is denied. The current certification sha'll remain in force and effect.

This denial is without pre)udice to t<iagara Mohawk's rights to 'make r'eapplication for certification, and,is done in 'consideration .

that the issues upon which recertification would depend are not now resolved.

The National Pollution Discharge Elimination System

,Permit issued by the U. S Environmental Protection Agency has boon disputed by Niagara Mohawk and is cunently the subject of a pending adgudicatory hearing before the Agency. The maintenance of, a balanded indigenous pursuant to Section 316a of the Act, and the design, location. fish'opulation construction and capacity of the intake to minimize adverse environmental impact pursuant to 316b of the Act, as well as similar State requirements of the Thermal Criteria pursuant to Sections 704.1(~), and 704.6 respectively.

stil't require resolution.

According to the agudicatory hearing procedure's. the Environmental Conservation Department, as a party to the heaving, will be afforded recertification rights based upon the determinations of the Environmental Protection Agency when a decision is proposed on the referenced matters, and on any of the other permit requirements which form the subgect of the adjudicatory heaving. If certificatjon were prpcessed now, it could be construed as a pre3udgement of ghe ad3udicatory proceedings 2169

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and in any event <could have to be redone at the time the Environmental Protection Agency proposed to modify the permit, Should you have any questions please contact Nr.'homas E. gu$ nn at (610) 467-6939.

Very truly yours, H)llfata t.. Garvey Director, Bureau of Standards and Compliance cc> U. S. KPA - Region Il ter. Garvey TEg;sam

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NeW York State Department of Environmental Conservation Division of Pure Waters Peter A. A. Berle, Commissioner February 23, 1977 Mr. J. M. Toennies, Director Environmental Affairs Niagara Mohawk Power Corporation 300 Erie Boulevard West Syracuse, New York 13202 Re: 401 Water Qualmy Certification Nine Mile Point Nuclear Station Unit PE2

Dear Mr,

. Toennies:

ln response to your request of February 24, 1976 for recert-ification pursuant to Section 401 of t: he Federal Water Pollution Control Act Amendments of 1972 to the original certification issued for this facility dated October 12, 1973, the New York'tate De-partment of Environmental Conservation hereby supercedes the existing certification as follows:

Public notice was duly given pursuant to Part 608.16 of the Official Compilation of Codes, Rules and Regulations of the State of New York. The Department of Environmental Conservation hereby issues the certification in accordance with'ection 401 of the Act and in accordance with applicable effluent limitations or other limitatio'ns in Sections 301, 302, 306 and 307 of the Act for construction of the Nine Mile Point Unit N2 Nuclear Generat-ing facility on Lake Ontario in the Town of Scriba, Oswego County, New York. ~

This certification is f>>

intended to apply to proceedings before the U. S. Nuclear Regulatory Commission and the U. S. Environmental

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Mr. J. M..Toennies, Director February 23, 1977 Protection Agency. This certification is issued due to funda-mental changes in the circulating cooling water system from open cycle once through cooling to closed cycle cooling utilizing a natural draft evaporative cooling tower. Based upon the the Department of Environmental Co'nservation hereby cert-fore-'oing, ifies that Niagara Mohawk will. comply with all applicable pro-visions of 301, 302, 306 and 307 of the Act for its Nine Mile Point Nuclear, Generating Station Unit N2 provided that:

I. There are no future changes in any of the following that would result. in non-compliance with Sections 301, 302, 306 and 307 of the Act.

A. The proposed construction and operation of the facility; B. The characteristics of the waters into which dis-charges are made; C. The water quality criteria applicable to such waters; or D. Applicable effluent limitations or other requirements.

II. The applicable provisions. of State laws and regulations are complied with; and III. The following effluent .limitations and monitoring requirements which shall be conditions of any U.'. Nuclear Reg-ulatory Commission license or U. S. Environmental Protection Agency NPDES permit for Nine Mile'oint Unit N'2 pursuant to Sec-tion 401d of the Act are complied with.

1. Pursuant to Part 704 Criteria Governing Thermal Discharges Section 704.1(a),all thermal discharges to .the waters of the State shall assure the protection and propagation of a balanced indigenous population of shellfish, fish and wildlife in and on the body of water

Mr. J. M. Toennies, Director February 23., 1977

. 2. Pursuant,to Part 704 Criteria Governing Thermal Discharges Section 704e5 the location, design, construction and capacity, of cooling water intake structures in connection'with point source thermal discharges shall reflect the best technology available for minimizing adverse environmental impact.

3. Pursuant to Part .701 Classifications and Standards of Quality and Purity Part 701,'4 the following classes and stan-dards for fresh surface waters shall be attained in Lake Ontario outside the zone of active mixing induced by the tuibulence of the discharge.

Suspended, colloidal or None from sewage, industrial wastes or settleable solids other wastes which will cause 'deposi-tion or be deleterious for, any best usage determined for the specific waters which are assigned'tg each class.

t Oil and floating sub- No residue attributable to sewage, stances industrial wastes or other wastes nor visible oil film nor globules of grease.

Taste and odor-producing None e

in amounts that will be injurious substances, toxic wastes to fishlife or which in any manner shall and deleterious substances adversely effect the flavor, color or odor thereof, or impair the waters for any best usage as determined for the

.speci,fic waters which are assigned to each class.

Radioactivity

a. Gross Beta Shall uct ezceed 1,000 pic~curiae per

.liter in,the absence of Sr and alpha emitters.

b. Radium 226 Shall not exceed 3 picocuries per liter.

c. Strontium 90 Shall not exceed 10 picocuries per liter.

I Mr. J. M. Toennies, Director February 23, 1977

4. Pursuant. to Part 702 Special Classifications and S'tandards Section 702.1 Quality Standards for Class A Special Wa<ers the following additional requirements shall be achieved in Lake Ontario. outside the zone, of active mixing induced by the turbulence of the discharge.

Total Dissolved Solids Should not exceed 200 milligrams per liter pH Should not be outside the range of 6.7 to 8.5 Radioactivity Should be kept at the lowest practicable levels and in any event should be con-trolled to the extent necessary to pre-vent harmful effects on health,

5. No discharge from this facility shall cause 'violation of the New York State Department of Health regulations contained in 10 NYCRR Part 170 at the source of intake of any water supply used for drinking culinary or food processing purposes.

6. Pursuant to Part 704 Criteria Governing Thermal Dis-charges Section 704.3 Mixing Zone Criteria, upon the presentation of a final design for the discharge the Department shall specify definable numerical limits for the mixing zone, including linear distances from the point of discharge, surface area 'involvement, of volume of receiving water entrained in the thermal plume, as appropriate.

7. Not less than 180 'days prior to the initiation of discharge from t'e Nine Mile Point Nuclear Generating Unit g2 Niagara Mohawk shall submit to the Department of Environmental Conservation, for approval, 'a plan of study for evaluating the environmental effects of such discharges on Lake Ontario, which shall include, but not be limited to the following:

A. Assessment of the effects of the intake on organisms entrained in the intake water'low.

B. Assessment of the effects of the intake on fishes impinged on any intake structure screens

P Mr. J. M. Toennies, Director February 23, 1977 C. The extent of the thermal plume in the receiv-ing waters, to be verified by thermal survey in alternate months except for, December through March during the first two years of operation.

D. Prior to operation of Nine Mile Point Unit N2 existing biological studies in Lake Ontario as required by regu-latory agencies shall continue; subsequent to Unit N'2 operation such study programs shall be adjusted as required by regulatory agencies to assess the operating impact of Unit N2. Requirements to submit reports, frequency of submission, and content shall be established at the time of approval of the study programs

7. Starting one month subsequent to plant operation Niagara Mohawk shall submit to the Department a monthly report of daily operating data by the 30th of the month following for:

A'. Daily minimum, maximum and average station electrical output in megawatts; B. Daily minimum, maximum and average intake water volume; G. Temperature in degress farenheit of the intake and discharge 'shall be monitored continuously and daily minimum, maximum and average intake and discharge temperatures shall be reported.

8. There shall be no discharge of heat from the main condensors except heat may be discharges in blowdown from recir-culated cooling water systems provided the temperature at which the blowdown is discharges does not exceed at any time the lowest temperature of recirculated'ooling water prior to the addition of make-up water.

9. Neither free available chlorine or total residual chlorine may be discharged from any unit for more than two hours in any one day.

10. The discharge of free 'a'vailable chlorine shall not exceed a maximum concentration of 0.5 mg/1 nor an average concentration of 0.2 mg/1, with the furter restriction that the concentration of total residual chlorine in the receiving waters outside the zone of active mixing induced by the turbulence of the discharge shall not exceed 0.05 mg/1.

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Mr.,J. M. Toennies, Director February 23, 1977

11. Niagara Mohawk shall notify the Department within one week from the time of submission to the Nuclear Regulatory Commissio~ of any requested change in'he environmental technical specifications requirements which could in any way affect the requirements of this certification.

12. Niagara Mohawk shall also submit concurrently to the Department any report on the environment it submits to any Federal, State or local agency.

13. Niagara Mohawk shall provide access to the Nine Mile-Point, Site at any time to representatives of th'e Department subject to site security regulations to assess the environmental

. impact of the 'operation of 'the Nine Mile Point Nuclear Unit N'2, and to review any sampling program, methodology, and the gather-ing and reporting of any data, pursuant to the conditions of this certification.

This certification is i'ssued solely for the purpose of Section 401 of the Act. If. any condition of this certification

-is subsequently declared invalid, the Department shall reconsider the entire certification and make appropriate .amendments and mod-ifications as a result of such considerations..

A copy of this certification is being forwarded to the, Director of Regulation, United States Nuclear Regulatory Commission and 'the Regio'nal Administrator of the U. S. Environmental Protection Agency, Region II.

Very truly yours, William L. Garvey Director Bureau of Standards 6 Compliance cc: U.S. NRC cc: U.S. EPA

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NRC FoRM 195 U.S. NUCLFAR REGULATORY C~'-"hlSSION DOCKET NUMBER (2 76)

. r$ FILE NUMBER

'I -.imp,", 'NR< DiSTRIBUTiON FoR pART SS Dp CKET MATERIAL En uJ vo~ me~4 DATE OF OPCQIEIII)

Mr B PRusche 'LEBBEUF,LAIfB, LEIBY &

DC MACRAE'ashington, DATE RECEIVED Addressees BLETTER .l2KNOTORIZED PROP INPUT FORM NUMBER OF COPIES RECEIVED IBORIGINAL BUN C LASS I F I E D QCOPY 3 signed DESCRIPTION ENCLOSURE Ltr on behalf of Niagara Mohawk Pwr Corp.'... Amdt to OL/Change to Appendix B Tech Specs:

notarized 1-24-77....trans the following: Revising Appendix .B in it's entirety. by the submittal of attacIiment A & B which cover the following areas:

1. Changes to instrumentation sensitivities which permit xeasonable deviations..........

2. Change's to account for si.te specific rather than generic industry donditions.....

3. Changes to the en')ironmental analysis &

r sampling program......

PLANT NAME: Nine Mjle Point It:1 4. Editorial changes for clarification.....

1 DO NOT REMOVE (40 cys encl rec'd)

ACKNOWLEDGED SAFETY FOR ACTION/INFORIvlATION 1-26-77 ehf ASSIGNED AD:

N CKCHL RO .CT MANA c cu)c.lC PROJECT MANAGER OuI tS LTC ASST I V)$ LIC ASST INTERNAL 0 1ST RI BUTION REG SYSTEMS SAFETY PLANT SYSTEMS S TE SAFE NRC PDR HEINEMAN TEDESCO I & E SCHROEDER OELD ~I GOSSICK & STAFF 6+v ENGINEERING IPPOL TO ENV MIPC IfACARRY ERNST CASE KNIGHT BALLARD HANAUER SIHWEIL OPERATING REACTORS SPANGLER HARLESS PAWL CK STELLO SITE TECH PROJECT MANAGEMENT BOYD P COLLINS REACTOR SAFE ROSS NOVAK EISENHUT ~

OPERATING TECH GAKfILL STEPP HULMAN HOUSTON ROSZTOCZY PETERSON CHECK B F, SITE ANALYSIS MELTZ VOLLMER C+v-HEI TEMES AT&I BUNCH SKOVHOLT SALTZMAN J COLLINS RUTBERG KREGER EXTERNAL DISTRIBUTION CONTROL NUMBER LPDR Me. AJ NAT LAB HWMUauu TIC: REG V,IE ULRIKSON OR NS IC: LA PDR ASLB: CONSULTANTS:

ACRS CYS  %%RRRC/ Et T 5. C NRC FORM 195 {2 76)

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LEON A. ALLEN,JR. CAMERON F. MAcRAC 8 RAHDALL J. LEBOEUF, JR. I929 1925 JOSCPH E.GACHCLDER,TK QAMCRON F MOOR*K 3IE 8 LEBWIH~WASHIHOTOH~0, C ERNEST S. GALLARO,JR. GCRARO A.MAHER 440274 ASSIAH C. LEISY 1952 ~ IBFB G. S. PCTKR GERGCN 4 SHEILA H. MARSHALL TELEX:

GCOFFRY D. C. GCST DAVID P. DICKS JAMES G. MOELROY JAMCS P. McGRANCRY. JR 8i OF COVHBEL TAYLOR R. GRIGGS PHILIP PALMER MOGUIGAN CHARLES N.BURGER L. MANNING MUNTZINGi8 WILLIAM O. DOUG EUGENE R. FIDCLLia JAMcs 0 MALLcY JR.E J. MICHAEL PARISH January 24, 1 9 77 ARVIN C. UPTON

.JACOG FRIEDLANDCR JOHN A.RVDY DONALD J. GREENE PAVL G. RUSSCLL HAROLD M. SCIDEL I%0 BROADWAY JAMES A GRCCRs TE 8 CHARLES P. SIFTON JOHN L.GROSC 4 HALCYON G. SKINNER NEW YORK, H.Y. I0008-DOUGLAS W. HAWES JOSEPH S.STRAUSS CARL D. HOGCLMAN SAMUCL M.SUGDCN TELEPHOHE 2I2 259 II00 MICHAEL IOVENKO JAMCS F. JOHNSON, 4~<

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+ RESIDENT PARTNERS WASHINGTON OFFICE 8 ADMITTED TO THC DISTRICT OF COLUMBIA GAR C

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~gTLSQ Mr. Ben C. Rusche Q2 +

l Director 0 'O TSIG iSSCS Office of Nuclear Reactor Regulation TSPSI U. S. Nuclear Regulatory Commission Washington, D. C. 20555 Re: Niagara Mohawk Power Corporation Nine Mile Point Nuclear Station Unit No. 1

'ock'et'o. 50'-'220'ear Mr. Rusche:

As counsel for Niagara Mohawk Power Corporation, we hereby transmit three (3) signed originals and nineteen (19) copies of a document entitled "Application for Amendment to Operating License." This Application seeks to amend in its entirety Appendix B to Facility Operating License No. DPR-63. 1I 1

In summary, the proposed Technical Specifications enclosed with this letter cover the following four areas: f (1) ,Instrumentation sensitivities changes, proposed to allow for reasonable deviations inherent to current "state of the artH measurement devices; (2). Changes, proposed to account for site speci-fic rather than generic industry conditions;

(.3) Changes, proposed to the environmental sampling and analysis. program; and

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(4) Changes of an editorial nature, proposed for clarification.

Forty (40) copies each of the proposed changes and of the accompanying technical data (Attachments A and B, respect'ively) are also transmitted.

Very truly yours, LeBoeuf, Lamb, Leiby 6 MacRae Attorneys for Niagara Mohawk Power Corporation Enclosures

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ji UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION In the Matter of )

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NIAGARA MOHAWK POWER CORPORATION ) Docket No. 50-220 (Nine Mile Point Nuclear Station )

Unit No. 1) )

APPLICATION FOR AMENDMENT TO OPERATING LICENSE Pursuant to Section 50.90 of the regulations of the Nuclear Regulatory Commission, Niagara Mohawk Power Corporation, holder of Facility Operating License No. DPR-63, hereby requests that the Environ-mental Technical Specifications set forth in Appendix 8 to that License be amended. These proposed changes have been accepted by the Site Operations Review Committee and Safety Review and Audit Hoard.

P The proposed Environmental Technical Specifications are set forth in Attachment A to this'application. Supporting information, Q which demonstrates that the proposed specifications do not involve a ll significant hazards consideration, is set f'orth in Attachment B. The proposed specifications would not authorize any change in the types or any increase in the amounts of effluents or any change in the authorized power level of the facility.

4 WHEREFORE, Applicant respectfully requests that Appendix B to Facility Operating License No. DPR-63 be amended in the form attached hereto as Attachment A.

NIAGARA MOHAWK POWER, CORPORATION By G. K. Rhode Vice Pre ident-Engineering Subscribed and sworn to before me on this HK day of January,, 1977.

N ary Public HAZEL J. CARittCK Notary Public in tho Sta(o of Now YorL Qualified in Onon. Co. No. 4524460 MY Commission Expires March 30, IQ;7W

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Attachment A Niagara 'Mohan>k Pov(er Corporation License No. DPR-63 Docl"et No. 50-220 Pro osed Chan es to Facilit 0 eratin License The attached is a revision to Appendix B of DPR-63.

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ENVIRONYiEHTAL TECH lNICAL SPECIFICATIONS APPENDIX 8 TO FACILITY OPERATING LICENSE NO. DPR-63 FOR HIHE NILE POINT NUCLEAR STATION UNIT' NIAGARA NOHAWK POWER CORPORATION DOCKET NO. 50-220

1 TABLE OF CONTENTS

~Pa e Table of Contents List of Figures iv List of .Tables

1. 0 DEF IN ITIONS 2.0 LIMITING CONDITIONS FOR OPERATION 2.1 Thermal

2. 1.1 t5aximum aT Between Condenser Inlet and Discharge Tunnel 2.1. 2 Maximum Discharge Temperature - Not Applicable 2..1.3 t1aximum Btu/hr - Not Applicable 2.1. 4 Rate of Change of Discharge Temperature 2.1. 5 Heat Treatment of Circulating Water System 2.2 Hydraulic - Not Applicable 2.3 Chemical 2 '.1 Biocides 9

2. 3. 2 Corrosion Inhibitors 10 2,3,3 Suspended and Dissolved Solids 13 2.3.4 pH and Conductivity 14 2.4 Radioactive Discharges Objective 15 2.4.1 Specifications for Liquid Waste Effluents 16 2.4.2 Specifications for Liquid Waste Sampling and tlonitoring 17 Bases for Liquid Waste Specifications 19 2.4.3 Specifications for Gaseous Waste Effluents 21 2.4.4 Specifications for Gaseous Waste Sampling and t1onitoring 26 Bases for Gaseous Waste Specifications 29 2.4.5 Specifications for Solid Waste Handling and Disposal 33

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TABLF. OF CONTENTS (Continued)

~Pa e 3.0 ENVIRONMENTAL SURVEILLANCE 34 3.1 Nonradiological Surveillance 34 3.1 ~ 1 Abiotic 35 a ~ Aquatic 35 (1) Chemical Discharges 35

'(2) Dissolved Gases 36 (3) Thermal Measurements 36

b. Terrestrial 37 (1) Soil Chemistry - Not Applicable 37 (2) Groundwater - Not Applicable 37 (3) Meteorological Monitoring 38 3.1.2 Biotic 41

a. Aquatic 41 (1) General Ecological Survey 41 (2) Impingement of Organisms 43 (3) Entrainment of Plankton, Fish Eggs and Larvae - Not Applicable 43

b. Terrestrial - Not Applicable 44 3.2 Radiological Environmental Monitoring 47 4.0 SPECIAL SURVEILLANCE AND STUDY ACTIVITIES - Not Applicable 5.0 ADMINISTRATIVE CONTROLS 5.1 Responsibility 52 5.2 Organization 52 5 3

~ Review and Audit 52 5.4 Action to be Taken if a Limiting Condition for Operation is Exceeded 54 Operating Procedures 54

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TABLE OF CONTENTS (Continued)

Page Station Reporting 'Requirements 58

5. 6.1 Annual Reports 58 5.6.2 t<on-Routine Reports 59 5.6.3 Changes in Environmental Technical Specifications 65 Records Retention 66 Special Requirements 67 (Land Management)

'l LIST OF FIGURES Title Pa<ac Sampling Locations Environmental Technical Specifications Nine Nile Point Site 46 Safety Organization: 'ine Mile Point and James A.

FitzPatrick Site

LIST OF TABLES Table Ti tl e ~Pa e

2. 3-1 Limiting Values for Chemicals in Liquid Effluents 2~ 3 2 Chemical Liquid Haste Analysis 12

2. 4-1 Radioactive Liquid Sampling and Analysis 18

2. 4-2. Average Energy Per Disintegration 22

2. 4-3 Radioactive Gaseous Haste Sampling and Analysis 27 3.1-1 Frequency of Sampling for Ecological Studies in the Nine Nile Point Area of Lake Ontario 45 3.1-2 Meteorological Measurements 39 3.1-3 Meteorological Data Format 40

3. 2.1 Sampling Collection and Analysis Site Radiological Environmental Monitoring Program 48 5.3 Responsibilities and Authority for Environmental Review Organi zation 5.6 Environmental Radiological Monitoring Program Summary 61

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1.0 Reactor 0 eratin Conditions a ~ Power 0 eratin Condition (1) Reactor mode switch is in startup or run position.

(2) Reactor is critical or criticality is possible due to contro't rod withdrawl.

b. Normal Station 0 era'tion 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) The reactor mode switch is in the shutdown position.

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

(3) Reactor coolant temperature is greater .than 212 F.

1.2 R f l~iQ 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 unti 1 the next regularly scheduled outage.

1.3 0 er atin C cle An operating cycle is that portion of Station operation between reactor startups following 'each major refueling outage as defined above.

'l.4 E ui ment Status

a. ~0erab le A system or component shall be considered operable when it is capable of performing its intended function in its required manner.

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

1 Instrument Test Procedure Instrument Channel Calibration Instrument channel calibration means adjustment of channel output such that it responds, 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~ Sensor Check A sensor check is qualitative determination of acceptable

.operability by observation of sensor behavior during operation.

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

Circulatin lJater Heat Treatments

a. ~Tem erin During tempering, a gate in the screenwell is partially opened to recirculate part of the heated circulating water in the screenwell discharge bay to the intake bay. The procedure is used to control condenser inlet temperature at times of low lake temperature.

b. Normal Flow In the normal flow configuration, circulating water is drawn from the lake into the screenwell intake bay through the intake tunnel.

Heated water in the discharge bay is discharged to the discharge tunnel.

C. Reverse Flow In the reverse flow configuration, circulating water is drawn from the lake into the screenwell intake bay through the discharge tunnel. Heated water in the discharge bay is discharged to the intake tunnel. This procedure is used to correct intake structure icing.

~ .

.I

(Cont'. )

The term "reverse flow operations" designates the period from the time reverse flow is initiated until two hours after normal flow is restored.

The reverse flow configuration includes a tempering arrangement similar to that described in 1.6.a above except using a different gate.

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

The temperature of incoming lake water, as measured in the screenhouse, before tempering.

6 E.O, ~LII ITIHG CITIORS FOR OFERIITION 2.1 Thermal 2.1.1 Maximum hT Between Condenser Inlet and Discharge Tunnel r

OBJECTIYE The purpose of this Specification is to limit the thermal stress to the aquatic ecosystem by limiting the maximum hT between the condenser inlet and discharge tunnel.

SPEC I'F I CAT ION MIaximum IRT between condenser inlet and discharge tunnel during normal Station operation'hall'e limited to 32 F. If during normal Station operation the aT exceeds 32 F for a period of eight hours in any given 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> period the cause of this deviation shall be inves-tigated and positive action shall be taken to reduce the aT to within the Specification. Positive action also shall be taken to prevent any.

such deviations in the future. In addition, a report shall be submitted in accordance with Section 6.6.2a(l).

I MON ITOR IHG RE U REMENT The aT shall be recorded once per hour.

The temperatures at the main condenser inlet and in the screenwell discharge bay (upstream from the discharge tunnel) shall be measured by two Resistance Temperature Detec)ors (RTD's) in each location.

The RTD's shall be accurate to +2.0 F. The difference of these tem-peratures, aT, shall be computed.

BASES Nine Mile Point Unit 1 holds a National Pollutant Discharge Elimina-tion System (NPDES) permit from the United States Environmental Protec-tion Agency (USEPA) to discharge cooling water to Lake'ntario when operating with a maximum aT of 32 F, Lake studies and operating experience indicate that mortality 'of plankton, fish, eggs, and larvae entrained in the condenser will not have a significant effect on the populations of the species involved.

Maximum Discharge Temperature NOT APPLICABLE 2.1.3 Maximum BTU Per Hour NOT APPLICABLE

2. 1.4 Rate of Change of Discharge Temperature OBJECTIVE The purpose of this Specification is to limit the temperature changes to which aquatic organisms in the discharge plume may be, subjected during normal station startups, shutdowns, and power level changes.

SPECIFICATION The d'ischarge temperature shall not be changed by more than 18 F in .

any hour. This Specification shall nof. apply to temperature changes occurring during forced shutdowns, or to the temperature increase at the intake resulting from flow reversal.

I OFITQ FG ~FIGIEI T Discharge temperature shall be measured and recorded hourly as provided in the Monitoring Requirement of Section 2.1.1 BASES The cooling water discharge is diluted by a'factor of at least 2,5 as it rises from the submerged discharge ports, outside of a conical volume of 100 foot maximum radius extending from the discharge structure to the lake surface. Therefore, outside of this volume, an 18 F per hour discharge temperature change would result in a maximum lake water temperature change of 7 F per hour. Moreover, while the specified rate of change may be reached in the first hour of a shutdown or power change, the rate will be less than 10 F per hour in subsequent hours. This would produce a 4 F per hour change in the lake, as described above, Fish in Lake Ontario experience natural lake water temperature changes of 6 to 9 F.per hour with a frequency greater than the expected frequency of changes induced by the Station. In 1974; for example, temperature drops of 9.5, 8.5, and 6.5 F per hour were recorded in the Station logs on July 29, September 3, and August 15, respectively.

Neat Treatment of Circulating Water System OBJECTIVE To limit the thermal stress to the aquatic ecosystem by limiting the circulating water temperature increase over lake inlet temper-ature resulting from tempering and reverse flow procedures.

SPECIFICATION When the lake inlet temperature is between 32 F and 50 F, the dis-charge temperature shall not exceed the 'lake inlet temperature by 50 F, except during reverse flow operations. At no time during tem-pering,'xcept during reverse flow operations, shall the discharge temperature exceed 82 F.

Following a flow reversal, the discharge temperature shall not exceed the lake inlet temperature by more than the following values:

70 F for the first hour following flow 'reversal 60 F for the second hour following flow reversal 50 F two hours following flow reversal and thereafter HONITORING RE UIREHENT The discharge temperature shall be measured and recorded hourly as provided in the Honitoring Requirement, of Section 2,1,1.

BASES When lake temperature is less than 50 F, part of the discharge flow in the screenwell maybe recirculated to the intake to maintain condenser inlet temperature between 40 F and 50 F. This procedure is known as "tempering". The iaaximum circulating water temperature rise due to tempering is. 18 F, and occurs when the lake temperature is 32 F. When this is added to the 32 F maximum d,T, the maximum rise is 50 F over lake inlet temperature. Haintaining the condenser inlet temperature at no more than 50 F during tempering ensures that the discharge .tem-perature will not exceed 82 F during tempering.

The amount of tempering is controlled by moving a gate in the screen-well, and is normally adjusted to maintain the optimal condenser inlet temperature of approximately 45 F. The gate can be adjusted to'chieve this temperature within an error of approximately 5 F.

2.1.5 (Cont'd.)

Flow reversal is required to correct intake icing at low intake temperatures.. Flow reversal is also required to return to normal flow operations from reverse flow operations.

Prior to flow reveral, Station power is reduced to approximately 75 percent power or less. Reversal is achieved by moving gates in the screenwell. Immediately after flow reversal, heated water in the discharge tunnel at essentially the condenser outlet temperature is drawn through the condenser. The reverse flow configuration also requires that some tempering be continued. Accordingly, the 70 F maximum difference between discharge temperature and lake inlet temperature was determined taking into account the elevated intake water temperature, a temperature rise due to tempering, and the condenser rise.

All of the heated water contained in the discharge tunnel at the time of flow reversal passes through the condenser within approxi-mately 6 minutes.. Operating experience has shown that dilution of the heated lake wate~ near the discharge structure, sufficient to achieve a discharge temperature no more than 60 F higher than the lake inlet temperature, occurs within one hour after flow reversal.

Within two hours the lake temperature near the discharge structure is essentially the ambient lake temperature. Therefore, the dis-

. charge, temperature can be maintained within 50 F above the lake inlet temperature subsequent to this two hour interval.

Operating experience has shown that reverse flow is required less than five times each winter.

2.2 Hydraulic NOT APPLICABLE

(

2'. 3 Chemical

2. 3.1 Biocides OBJECTIVE The purpose of this Specification is to protect the quality and purity of Lake Ontario waters.

SPECIFICATION No biocides "hall be used in the main condenser cooling water or service water systems.

t~iON ITORI NG RENDU I REHENT No monitoring is required because no biocides shall be used in the main condenser cooling water or service water systems.

BASES The Specification will ensure that the lake water quality is not jeopardized by the introduction of biocides from the main condenser cooling water or service water systems.

! I t A

2.3.2 Corrosion Inhibitors OBJECTIVE The purpose of this Specification is to protect the quality and purity of Lake Ontario waters.

SPECIFICATION

/

The Station shall not normally discharge corrosion inhibitors to the lake, If inplant system leakage occurs and chromate corrosion inhibitor must be discharged to the lalie, the discharge shall not exceed the 'iimits shown in Table 2.3-1, and shall be made to the circulating water systems.

MONITORING RE UIREHENTS Waste tanks shall be analyzed for chromium as shown in Table 2.3-2.

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

.Chromate corrosion inhibitor is used in the diesel generator closed loop cooling system. No discharges from this system are made to the lake. If leakage from this system should occur, the chromate would be collected in floor drains and routed to the waste tanks. It could ultimately be discharged in the cooling water under controlled conditions. Prompt action will be taken to correct any such 1eakage.

10

4 I

TABLE 2.3-1 LIMITING YALUES FOR CHEMICALS IN LI UID EFFLUENTS Maximum Increase Over Maximum Annual Discharge Lake Ambient Concentration From Plant Sources Parameter. (mg/1 Prior to Dilution) (lbs/year)

Total Suspended Solids 100.0 Total Dissolved Solids 50.0 Calcium (as Ca) - 5 ' 4,900 Sodium (as Na) 1.5 27,000 Sulfate (as S04 ) 3.0 49,000 Total Phosphorus (as P04 ) 1.0 10 Chromium (as Cr) (1) 0.05 (1)

NOTES

l. Annual discharge of chromium shall normally be zero. Small amounts of chromium may be di scharged if chromate leak'age from the diesel generator closed loop cooling system should occur. Such leakage would be handled as discussed in the Bases of Section 2.3.2.

Small amounts of chromium occur in Station waste water as cor-rosion products.

TABLE 2.3-2

. CHEMICAL LI UID HASTE ANALYSIS Sample Type of Sensi ti vi ty of

~Sam le Fee~vane Anal sis 3 ~ll Cooling water Monthly {1)

Discharge Composite Total Dissolved Solids + 10.0 mg/liter Total Suspended Solids 5.0 mg/liter Cooling water Monthly (1)

Intake Composite Total Dissolved Solids + 10.0 .mg/liter Total Suspended Solids 5.0 mg/liter t<aste Tanks Each Batch pH + 0;5 pH units 1

Conducti vi ty + 1.0 umho/cm (4 Monthly Proportional Composite (2) Total Dissolved Solids + 10.0 mg/liter Total Suspended Solids + 5.0 mg/liter Ca 5.0 mg/liter Na 2.

+ 5.0 mg/liter SO 5.0 mg/liter P04 3 + 5. 0 mg/1 i ter Cr 1. 0 mg/1 i ter

{1) The cooling water intake and discharge are sampled continuously, for each week. The monthly composite includes an aliquot from each'week's collection.

If the continuous sampler is unavailable, grab samples shall be taken at a maximum interval of 96 hours0.00111 days <br />0.0267 hours <br />1.587302e-4 weeks <br />3.6528e-5 months <br />.

(2) The monthly proportional composite shall be composited from a representative aliquot of each waste tank batch discharge.

(3) Standard techniques such as ASTM or equivalent methods shall be used for analyses.

(4) This sensitivity applies only to measurements below 10 pmho/cm.

12

1 I

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

SPECIFICATION For suspended solids, total dissolved solids, and individual solutes in the cooling water discharge, the increase in concentration over lake %let shall not exceed the limits shown in Table 2.3-1. Total annual discharge of individual solutes shall not exceed the limits shown in Table 2.3-1.

If these limits are exceeded, corrective action shall be taken to decrease concentrations to within the Specification and a report shall be submitted in accordance with Section 5.6.2 a(l).

MONITORING RE UIREtiENT Liquid wastes discharged to Lake Ontario shall be monitored and analyzed as shown in Table 2.3-2.

BASES Adherence to the Specification will ensure that the water quality of Lake Ontario is not jeopardized by suspended and dissolved solids in Station discharges.

The data obtained from waste tank monthly proportional composite samples will be used with known flow rates to determine the increase in cooling water chemical concentrations over lake inlet concentra-tions resulting from waste .tank releases. Analyses of-the cooling water intake and discharge will provide a check against gross errors in the proportional composite sample analysis.

Records of waste tank analyses will provide sufficient information to ensure that the annual discharge limits will not be exceeded.

13

I 2 ~ 3.4 pH and Conductivity OBJECTIVE The purpose of this Specification is to limit the liquid effluent pH to a range of values consistent with the classifications and standards governing the quality and purity of Lake Ontario waters.

SPECIFICATION The pH'of treated water in the waste tanks prior to heing discharged into the discharge tunnel shall be betwe'en 6.0 and 9.0. When the conductivity of a waste tank is below 10 vmho/cm, the pH shall be between.4.0 and 9.0: If water with a pH value outside these limits is discharged, corrective action shall be taken and a report shall be filed in accordance with Section 5.6.2a (1).

MONITORING REOUIREtlENT Sampling and analysis for pH and conductivi ty shall be performed in accordance with Table 2.3-2, BASES Lake Ontario is designated Class A-Special (International Boundary Water). This classification specifies a lake water pH range of 6.7 to 8 5~ ~ However, pH observations performed during site monitoring programs have fallen predominantly in the range from 8.0 to 9.0 and have frequently exceeded 8.5.

Waste tank releases are diluted by a factor of more than 2,000 in the circulating water prior to discharge. After such dilution the discharge is at essentially the same pH as the incoming lake water. Therefore, waste tank releases will have insignificant impact on the frequency with which Class A Special limits are exceeded when maintained within the Specification.

With increased usage of the waste concentrator, pure water inventory increases' To allow for discharge of water with only C02 as con-tatninate, a lower pH is allowed for low conductivity tanks.

14

2.4 Radioactive Discharges OBJECTIVE To define the limits and conditions for the controlled release of radioactive materials in liquid and gaseous effluents to the environs to ensure that these releases are as low as reasonably achievable. The release rate for all effluent discharges shall be within the limits specified in 10 CFR Part 20.

To ensure that the releases of radioactive material above background to unrestricted areas will be as low as reasonably achievable as defined in Appendix I to 10 CFR Part 50, the following design objec-tives 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

'aterial in particulate forms above background from all reactors at a site should'ot 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.

15

I l SPECIFICATIONS FOR LI UID HASTE EFFLUENTS a ~ The concentration of radioactive materials released in liquid wastes from each reactor 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 calendar year.

d. The radiation monitor on the discharge line from the waste disposal tanks to the discharge tunnel shall. continuously monitor released acti vity and shall be set to alarm prior to exceeding Specification 2.4.1.a.

e. If Specification 2.4.1.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 discharge.

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

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

h. If the cumulative release of radioactive materials in liquid efflu-ents, 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'.4, and report these actions to the Commission within 30 days from the end of the quarter during which the release occurred.

16

I SPECIFICATIONS FOR LI UID WASTE SAt1PLING AND tlONITORING

a. Plant records shall be maintained of the radioactive concentra-tion 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 othe~ reports shall be submitted in accordance with Sec-tion 5.6. 1 of these specifications. Estimates of the sam-pling and analytical error associated wit)i 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 gamma energy peak in accordance with Table 2.4-1 to demonstrate compliance with Specification 2.4.1 using the flow rate of the stream into which the waste is discharged during the period of discharge.

C. Sampling and analysis of liquid radioactive waste shall be per-formed in accordance with Table 2.4-1. Prior to taking samples, at least two tank volumes of entrained fluid shall be recircu-lated through the mixing nozzles.

d. The radioactivity in liquid wastes shall be continuously moni-tored during release. Whenever the monitor is 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 tank to be discharged shall be analyzed and two plant of'ach personnel shall independently check valving prior to the dis-charge. 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 terriiinated.

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

The liquid effluent radiation monitor'hall 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 instrument channel test monthly and a sensor check prior to making a release.

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

17

TABLE 2.4-1 RADIOACTIVE LI UID SANPLING AND ANALYSIS Detectable Liquid Sampling Type of ConcentratI~~s Source Fre uenc Acti vi t Anal si s 'Ci/ml A. Haste Tank Releases Each Batch Principal Gamma Emitters (Ba-La-140, I-131 One Batch/Month Dissolved Gases Sr-89, 90 5X108 Quarterly Composite (1) H-3 1O-'.

Gross a 10 7 Primar Cool.ant Heekl I-131, I-133 1O-6 NOTES FOR TABLE 2.4-1 .

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

2. For certain mixtures of g.amma emitters, it may not be possible to measure radionuc1ides 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 limiits miay be readily achievable and when nuclides 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.

BASES FOR LIQUID HASTE SPECIFICATIONS The release of radioactive materials in liquid waste effluents to unrestricted areas shall not exceed the concentration limits spec-ified 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 flexibility of operation, compatible with considerations of health and safety, to assure that the public is provided a dependable source of power under unusual operating conditions which may temporarily result in releases higher than the design objective levels but still within the concentration limits specified in 10 CFR Part 20. It is expected that by usi ng thi s operational flexibility under unusual operation conditions, and exerting every effort to keep levels of radioactive material in liquid wastes as low as reasonably achievalbe, 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 experi-ence taking into account a combination of variables including defec-tive 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 2.4.1.a requires the licensee to limit the concentration of radioactive materials in liquid waste effluents released from the site to levels speci'fied in 10 CFR Part 20, Appendiy B, Table II, Column 2, for unrestricted areas. Thi"s Specifi,cation provides assur-ance that no member of the general public will be exposed to liquid containing radioactive materials in excess of limits considered permissible under the Commission's Rules and Regulations.

Specifications 2.4.1.b and 2.4'.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 flexibility of operation to assure that the public is provided a dependable source of power under unusual operating conditions which may temporarily result in releases higher than the levels normally achievable when the plant and the liquid waste treatment systems are functioning as designed. Releases of up to these limits will result in concentra-tions of radioactive material in liquid waste effluents at small percentages of the limits specified in 10 CFR Part 20.

Specifications 2.4.l.d and 2.4.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, Design Criterion 64. C 19

l BASES FOR LI UID HASTE SPECIFICATIONS (Cont'd.)

Specification 2.4.1. 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 reasonably achievable consistent with the requirements of 10 CFR Part 50.36a. Normal use and maintenance of installed equipment in the liquid waste system provides reasonable assurance that the quantity released will not exceed the design object'ive. In order to keep releases of radioacti ve material s 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 2.4.l.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 Spec-ification 2.4.l.b and 2.4.l.c, the reporting requirements of Spec-ification 2.4. 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 quarter and describe the proposed program of ac-tion to reduce such releases to design objective .levels on a timely basis. This report must be filed within 30 days following the calen-dar quarter in which the release occurred.

The sampling and monitoring requirements given 'unde'r Specification 2.4.2 provide assurance that radioactive materials in liquid wastes are properly controlled and monitored in conformance with the require-ments of Design Criteria 60 and 64. These requi rements provide the data for the licensee and the Commission to evaluate the plant's performance relative to radioactive liquid wastes released to the environment. Reports on the quantities of radioactive materials released in liquid waste effluents are furnished to the Commission according to Section 5.6.1 of these Technical Specifications in con-formance 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.

20

2.4. 3 SPECIFICATIONS FOR GASEOUS l(ASTE EFFLUENTS

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

~ " is Ll 6 EiY + 0 3 Eig j + ~isL2.7 EiY + 0.5 Eig] "'iv[11.0 E + 24.0 E gJ s 1 where g' release rate from Nine Nile Point Unit 1 main stack in Ci/sec (as elevated release)

= release rate from the FitzPatrick main stack in Ci/sec (as elevated release) gv

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

= the individual nuclide E = the average gamma energy per disintegration Y

E = the average beta energy per disintegration 0

Refer to Table 2.4-2 for E Y

and E> values 4o be used.

(2) The release'ate limit of all radionuclides and radioactive materials in particulate form with half-lives greater than eight .days, released to the environs as part of the gaseous wastes from the site shall be:

1.2 X 10 (g' 0 08 9 + 5.5 9 ) < 1 s '

v where g' release rate from Nine Nile Point Unit 1 main stack in Ci/sec (as elevated release) s

= release rate from the FitzPatrick main stack in Ci/sec (as elevated release)

= release rate from the Fi tzPatri.ck vents in Ci/sec'ground. release) 21

P I

TABLE 2.4-2 AVERAGE ENERGY PER DISINTEGRATION Isoto e E , l1ev/dis Ref E, Mev/dis( Ref Kr-83m 0.00248 (1) 0.0371 (1)

Kr-85 0.0022 (1) 0.250 (1)

Kr-85m 0.159 (1) 0.253 (1)

Kr-87. 0. 793 . (1) 1. 32 (1)

Kr-88 1.95 (1) 0.377 (1)

Kr-89 2,22 (2) 1. 37 (2)

Kr-90 2.10 (2) 1. 01 (2)

Xe-131m 0,0201 (1) 0.143 (1)

Xe-133 0.0454 (1) 0.135 (1)

Xe-133m 0,. 042 (1) 0.19 (1)

Xe-135 0. 247 (1) 0. 317 (1)

Xe-135m 0.432 (1) 0.095 (1)

Xe-137 0.194 (1) 1. 64 (1)

Xe-138 1.18 (1) 0.611 (1)

(1) ORNL-4923, Radioactive Atoms Su lement I, H. S. Hartin, November 1973.

(2) NED0-12037, "Summary of Gamma and Beta Emitters and Intensity Data";

M. E. Heck, R. S. Gilbert, January 1970. (The average 8 energy was

~

computed frown the maximum energy using -the ICRP. II equation, not the 1/3 value assumption used in this reference).

(3) 1'he average 8 energy includes conversion electrons.

22

) I a

2.4. 3 (Cont'd.)

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

z E,~ C0.9 Q'.s + '7 Q s

+ 74'Q1vj -'

AND z E. L10'.0 Q'. + 17.'0 Q. + 71.0 Q. ] < 1 1'y 1S 1S 1V (2) The average release rate of noble gases from the site during any 12 consecutive months shall be:

z E. L1.8 Q'. + 3.4 Q . + 149.0 Q. j < 1 AND z E. L21.0 Q'. + 35.0 Q. + 142.0 Q. ]' 1 1"( 1S 1S 1V (3) The average release rate from the site of all iodines and radioactive materials in particulate form with half-

' " l.ives greater than eight days during any calendar quarter "

shall be:

1.5 X 10 (Q',08Q + 5,5 Q ) 1 (4) 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 consecu-tive months shall be:

3 0 X 10 (Q s + 0 08 Qs + 5 5 Qv) 1 I

(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.

23

I 2.4.3 (Cont'd.)

C. Should the conditions of 2.4.3.c(l), (2) or (3') listed below exist, the licensee shall make an investigation to identify the causes of the release rates, define and initiate a program of action to reduce the release rates to design objective levels listed in Section 2.4 and report.'these actions to the Commission within 30 days from the end of the quarter during which the releases occurred.

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

z E.

1~

C3 5 Q'.

1'S

+ 6 8 Q.

1S

+ 282.0 Q.

1V j > 1 1

11's, OR Z E L41.0Q'680 Q 1s

+ 3100Q 1v

] >1 (2) If the average release rate from the site of all iodines and radioactive materials in particulate form with hal f-lives greater than eight days, during any calendar quarter 1S:

5 8 X 10(QS008Qs55Qv)1 (3) If the amount of iodine-131 released during any calendar quar ter is greater than 0.5 Ci/reactor.

24

r l

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 2.4.3.a above. The operability of each automatic isola-tion valve in the gaseous radwaste discharge line shall be demonstrated quarterly.

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 />.

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

Z Eig'1.8 Q'is + 3.4 Qis + 149.0 Qiv] > 1 1

OR

~

1 Eiy L21 0 Q'is + 35 0 Qis + 142 o Qiv~ '

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 />,'he Licensee shall notify the Commission in wri,ting within 10 days, identify-ing the causes of activity. The report should include 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 up-stream of the point of release.

g. The drywe11 shall be purged through the standby Gas Treat-ment System until Specification 2.4.3 a(1) and 2.4.3 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.

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

25

'I I

4

2.4.4 SPECIFICATIONS FOR GASEOUS 'LSASTE SAMPLING AND MONITORING

a. Plant records shall be maintained and reports of the sampling and analysis results shall be submitted in accordance with Section 5.6.1 of these Specifications. Estimates of the sampling and analytical error associated with each reported value should be included.

The flow rate of Gaseous releases to the environment shall be measured and recorded. Gross radioactivity shall be continuously moni tored except as noted in Specification 2.4.4.c below. 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 gaseous activity downstream of the steam jet air ejectors and at the, stack sample point:

(1) at, least monthly (2) following each refuel outage within one week of attaining steady state power (3) if the offgas monitors indicate an increase of greater than 50! 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 Bureau 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 accor-dance with Table 2.4-3.

I

1 sl =

TABLE 2.4-3 RADIOACTIVE GASEOUS PJASTE SAMPLING AND ANALYSIS Detectabl e Gaseous Sampling Type of Concentratjqqs Source Fre uenc Activit Anal sis uCi/ml <'> 3 A. Drywell Atmosphere Each Purge  : Princi al Gamma Emi tters

8. Environmental Release Points Monthly (Gas Samples) (2) Princi al Gamma Emitters H-3 10-6 Weekly (Charcoal Sam le 4 I-131 1O-12 Meekly (Particulates)(4) Principal Gamma Emitters at least for Ba-La-140 I-131 10

(}uarterly Composite (5)

(Particulates) Sr-89 Gross e 1O-11

'I NOTES FOR TABLE 2.4-3

l. 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 nuclides are measured below the stated limits, they should also be reported.

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

3. For 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 calculate the levels of such radionuclid s using observed ratios with those radionuclides which are measurable.

4. When the average daily gross radioactivity release rate exceeds that given in 2.4.3.c(1) or where the steady state gross radioactivity release rate increases by 50K over the previous corresponding power level steady state release rate, the iodine and particulate collection device shall be re-moved 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 par-ticulate form released in gaseous effluents, samples should be collected in proportion to the rate of flow of the effluent stream.

I BASES FOR GASEOUS HASTE SPECIFICATIONS The release of radioactive materials in gaseous waste effluents to unrestricted areas shall not exceed the concentration limits spec-ified in 10 CFR Part 20, and should be a's low as reasonably ach-ievable 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 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 flexibility of operation, compatible with considerations of health and safety, to assure that the public is provided with a dependable source of power under unusual operating condi tions which may temporarily result in releases higher than the design objective levels but still within the 'concentration limits spec-ified in 10 CFR Part 20. It is expected that using this opera-tional flexibility under unusual operating condi tions, and by exert-ing every effort to keep levels of radioactive material in gaseous

~

waste effluents as low as reasonable achievable, 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 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 grea'ter than eight days'he 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 operation experi-ence 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 2.4.3.a(l) dose calculations have been made for the critical sector. These calculations consider site meteorology, buoyancy characteristics, and radionuclide content of the effluent from Nine Nile Point Unit 1 and from the FitzPatrick'lant. tieteo-rological 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'ine t<ile Point Unit l.

29

)

BASES FOR GASEOUS HASTE SPECIFICATIONS (Cont'd.)

The gamma dose contribution was determined using the equation 7.63 in Seciion 7-5.2.5 of ~lieteorolo and Atomic Ener~ - 1968. The releases from vents are considered to be ground level releases wh'ich 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 Iieteorolo and Atoniic ~ner<iy - 1968. The beta dose contribution was determined on the basis of an infinite cloud passage with semi-infinite geometry. for a gound level release (sub-mersion dose). The beta and gamma components of the gross radio-activity in gaseous effluents were combined to determine the allow-able continuous release rate. Based on these calculations, a con-tinuous release rate of gross radioactivity from the si te in the amount specified in 2.4.3.a(l) will not result in offsite annual doses above background'n excess of the limits specified in 10 CFR Part 20.

The average gamma and beta energy per disintegration used in the equation of Specification 2.4.3.a(l) will be based on the average composition of gases determined from the plant stack exhausts.

The average energy per beta or gamma disintegration for those radioisotopes determined to be present from the isotopic analyses are given in Table 2.4-3. Where isotopes, are identified, that are not listed in Table 2.4-3, the gamma energies are determined

.from Table of Isotopes, C. M. Lederer, J. M. Hollander, and I.

Per lman,.Sixth Edition, 1967 and the beta energy shall be as given in USNRDL- TR-802, II. S ectra of Individual Ne atron Emitters (Beta Spectra), 0. Hogan, P. E; Zigman and J. L. Macklin.

For Specification 2.4.3.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/Q 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 Unit 1 stack where the X/Q is 1.9 X 10 sec/m3 for the dose, 'oint due to inhalation. The nearest milk cow is located in the Nine Mile Point Ugit 1 Sl) sector at a distance ot'250 meters where the X/0 is 8 4 X 1 'ec/m for ground releases (FitzPatricl: vent), and 1.2 X 10 sec/m for Nine liile Point Unit 1 elevated releases. The grass-cow-milk-child thyroid chain is controlling.

30

\

MSES FOR GASEOUS MSTE 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 2.4.3.b establishes upper site levels for the releases of noble gases, iodi nes and particulates wi th half-lives greater than eight days, and ~odine-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 consecu-tive months. The intent of this Specification is to permit the licensee the flexibility of operation to assure that the public is provided a dependable source of power under unusual operation con-ditions which may temporarily result in higher releases than the objectives.

In addition'o the limiting conditions for operation of Specifica-tions 2.4.3.a and 2.4.3.b, the reporting requirements of 2.4.3.c delineate that the cause be identified whenever the release of gas-eous 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.

2.4.3.d and 2.4.3.e are in accordance with Design 'pecification Criterion 64.

Specification 2.4.3.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 2.4. 3. g requires that the primary contai nment atmos-phere receive treatment for the removal of gaseous iodine and par-ticulates prior to its release.

Specification 2.4.3.h requires that hydrogen concentration in the system shall be monitored at all times.

31

I E BASES FOR GASEOUS WASTE SPECIFICATIONS (Cont'd.)

The sampling and monitoring requirements'iven under Specification 2,4.4 provide assurance that radioactive materials released in gaseous waste effluents are properly controlled and monitored in conformance wi.th 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 radio-active wastes released to the environment. Reports on'he quanti ties

~

of radioactive materials released in gaseous effluents are furnished to the Commission in conformance wi th 10 CFR 50.36(a)(2) on a semi-annual, basis. Data is summarized on a quarterly basis in the annual Environmental"Operating Report and in conformance with Regulatory Guide 1.21. On the basis of such reports and any additional informa-tion the Commission may obtain from the licensee or others, the Gommission may from time to time require the licensee to take such action as the Commission deems appropriate.

32

1 0

2.4.5 SPECIFICATIONS FOR SOLID WASTE NANDLING AND DISPOSAL tieasurements 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 171-178.

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

BASES The requirements for solid radioactive waste handling and dis-posal given under Specification 2.4.5 provide assurance that solid radioactive materials stored at the plant and shipped off-site are properly controlled, monitored, and packaged in con-formance .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 faci li-ties for solid radwaste, and to evaluate the environmental im-of offsite shipment and storage. Reports on the quantities 'act and amounts of the radionuclides, and volumes of the shipments, shall be furnished to the Commission according to Section 5.6.1 of these Technical Specifications. On the basis of such reports and any additional information the Commission may obtain from .

the licensee or others, the Commission may from time to time require the licensee to take such action as the Commission deems appropriate.

33

3.0 ENVIRONMENTAL SURVEILLANCE 3.1 Nonradiological Surveillance Periodic evaluation of the findings of the surveillance program (Section 5.6.la - Annual Environmental Operating Report) will provide the basis for modification of the program to insure that the surveillance effort is sufficient and justified when compared to current assessment of the effect that plant opera-tion is having on the environment.

Major nonradiological enviro'nmental surveys have been conducted beginning in 1972. In 1975 the data obtained from the surveys was used to demonstrate no harm to the water body from Nine t'ai le Unit 1. The demonstration document,was submitted to the Environ-mental Protection Agency in December 1975 under the provisions of paragraph 316(a) Federal Mater Pollutant Control Act Amendments of 1972. Based on the substantial documentation of no harm to the water body Niagara Mohawk has established a program to provide for monitor-ing of nonradiological environmental parameters in order to,insure early discovery of adverse long range environmental trends.

34

Abiotic

a. Aqua ti c (1) Chemical Discharges OBJECTIVE The objective of these surveys is to measure and docu-ment water quality conditions and chemical character-istics in the vicinity of the site and to provide data on those factors which are related to plant operation.

SPECIFICATION

'i)ater equality samples shall be collected as prescribed by Table 3.1-1 at the location indicated on Figure 3.1-1.

to the extent weather permits. The sample shall be analyzed for:

1. Dissolved Oxygen

2. Temperature

3. pH

4. Total Solids

5. Total Suspended Solids

6. Total Phosphorus

7. Calcium

8. Sodium

9. f Sul ate REPORTING RE UIREYiENTS The results of the year's data as specified above shall be reported in the annual report. (See reporti ng requirements 5.6. la).

HASES (Refer section 2.3) Results of data analysis will indicate overall water quality in the plant vicinity.

35

(2) Dissolved Gases Not required.

BASES Sampling for dissolved oxygen is prescribed in Section 3.1.1a(1) .

(3) Thermal Measurements Not required.

BASES Thermal plume studies performed during 1970 through 1975 have thoroughly characterized the dispersion and extent of the Nine Mile Point Unit 1 thermal plume under varying meteorological conditions. No further thermal plume studies shall be required, 36

l

3. l.l.a (Cont'd. )

b. Terres trial (1) Soil Chemistry NOT APPLICABLE (2) Groundwater HOT APPLICABLE 37

I 3.1.1.b (Cont'd.) (3) Meteorol ogi cal t1oni toring OBJECTIVE The objective of meteorological monitoring is to adequately measure and document meteorological conditions at the site.

SPECIFICATION meterss The meteorological monitoring system shall measure para-as prescribed by Table 3.1-2 to provide data that is representative of atmospheric conditions that exist at all gaseous effluent release points.

REPORTING RE UIREHEHTS Meteorological data shall be compiled for quarterly periods in a format consistent with Table 3.13. Summaries of data and observations shall be available to the Nuclear Regulatory Commission upon request. Data shall be reported in conjuncti(

with the Semi-Annual Radiological Releases Report as specific<

in Section 5.6.1.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 instrument(s) involved shall be reported wi thin 30 days of the initial time of the outage to the Nuclear Regulatory Commission, Directorate of Licensing. Modifications to the meteorological monitoring program as described above shall have the written approval of the Nuclear Regulatory Commission, Directorate of Licensing, prior to initiation of the modification.

BASES The collection of meteorological data at the plant site will provide information which maP 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, Appendi.x.E of 10 CFR Part 50, and 10 CFR Part 51.

38

1 TAI3LE 3.1-2 meteorological t1easurements Instrument Parameter ~hccurac Wind direction +5 '(instaneous values)

Wind speed +0.5 mph (time average values)

Temperature +0.5 C (time average values)

(Two levels) differences

+0.1 C (average temperature

)

39

1 TABLE 3. 1-3 HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD:

STABILITY CLASS:

ELEVATION:

Wind Speed mph at 10m Level Wind Direction 1-3 8-12 13-18 19-24 >24 TOTAL NNE NE ENE ESE SE SSE SSW SW WSW WNW VARIABLE Total Periods of calm (hours):

Hours of missing data:

a 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.

40

I Biotic

a. Aquati c General Ecological, Sur vey OBJECTIVE To monitor effects of plant operation with respect to selected ecological parameters.

SPECIFICATION Field sampling shall be performed as described below to the extent weather permits. Table 3.1-1 summarizes the complete lake monitoring program. Sampling locations and type of sampling shall be in accordance with Figure 3.1-1.

(i) Ph to lankton and Zoo lankton Phytoplankton samples shall be collected as prescribed by Table 3.1-1 from approximately one-half meter below the surface at the four sampling locations shown on Figure 3.1-1. Zooplankton samples shall be collected as prescribed by Table 3.1-1 by oblique tows at the phytoplankton sampling locations. Relative phytoplankton density shall be determined for diatoms, and green and blue-green algae present. The density of total phytoplank-ton and dominant organisms sha.ll be re'ported. Density in numbers per cubic meter shall be determined for major zoo-plankton taxa and dominant species'

~hh Ichthyoplankton sampling (sampling for fish eggs and larvae) shall be conducted at the stations shown on Figure 3.1-1.

Collections will be made at 20 and 40-feet depths at the four transects at surface and bottom. Samples will also be collected at the nearshore location of each transect (approx-imately 10-foot depth). Samples shall be collected as prescribed'y Table 3.1-1 with metered nets.

Fish eggs and larvae samples will be enumerated and speciate'd in so far as possible. Density in numbers per'ubic meter shall be determined for major taxa.

1 I

3.1.2.a(1) (Cont'd.) REPORTING RE UIREf1ENTS At the end of each year of study, the results from the General Ecological Surveys shall be summarized in a report and submitted in accordance with Section 5.6.1.

BASES The information outlined in the Specification will provide data for interpetative analysis of the situation existing in the aquatic ecosystem of Lake Ontario in the Nine Nile Point area. The information collected through 1976 has provided data for determining the impact of the operation of Nine Nile Unit 1 and the FitzPatrick Plant on the aquatic environment. The continuing surveys will provide data to monitor the impact of the combined operations of these Plants on the aquati c environment. Specifications for future General Ecological Surveillance at this site will be based upon evaluations of these data.

(ii) Benthos '

Samples of the macroinvertebrate benthic community, shall be collected as prescribed in Table 3.1-1 at each of the four sampling locations shown in Figure 3.1-1 ~ Results shall be reported in terms of. numbers 'of organisms by major taxon and dominant species per unit area of the substrate sampled.

As prescribed by Table 3.1-1, adult and juvenile fish shall be collected bimonthly by gill nets. Bottom gill nets shall be set at the 40 ft. depth at all 'four transects. Replicate day samples will be taken at all stations as indicated on Figure 3. 1-1. The number of individuals of each species collected shall be recorded.

Secondary analysis of fish by species for each collection will include length, weight and sex. Only a random sample of forty fish per species will be analyzed from collections with more than 40 fish of a species.

l

~ I

3. 1.2.a (Cont'd.) (2) Impingement of Organisms OBJECTIVE To estimate the number and weight and to determine the species of fish impinged on the traveling screens in the intake screenwell during various seasons.

SPECIFICATION The species and numbers of fish removed from the travel-ing screens during a 24-hour period shall be recorded monthly. 0'uring the months of possible higher rates (March through June), 24-hour samples shall be collected once per week.

All fish collected will be separ'ated by species. A ran-dom sample of 40 fish per species will be analyzed for length and weight from collections with more than 40 fish of a species.

Based upon the mean weight of individuals of each species, an estimate of the number of fi sh by. species will be cal-culated. In the event of large collections, subsampling during the 24-hour collection will be satisfactory and es-timates of the number of fish of each species impinged can be based on volume. When the number of fish collected during a 24-hour period exceeds 20,000, sampling shall be continued until the number of fish diminish to less than 20,000 in a 24-hour period.

REPORTING RE UIREMENTS A report of impingement sampling results shall be included in the Annual Environmental Operating Report, submitted to the Director of the NRC Regional Office, in accordance with Section 5.6.1.

If the number of fish collected during a 24-hour period exceeds 20,000, notifications shall be made to the Director of the NRC Regional Office in accordance with Section 5.6.2.a.(1) "Prompt Report". In the event that numbers of fish in excess of 20,000/24 hours are collect'ed for consecutive days, "Prompt Report" notifications will be made when the number first exceeds 20,000/24 hours and

.when the number falls below 20,000/24 hours followed by a single "10 day" report.

BASES The program described in the Specification will monitor the magnitude of fish impingement at the Nine fiile Point si te.

Entrainment of. Plankton, Fish Eggs, and Larvae Not applicable.

T I

TABLE 5.3 RESPONSIBILITIES AND AUTHORITY FOR ENVIRONMENTAL REVIEM ORGANIZATION Vi ce Pres i dent-Engineering Site 0 erations Review Committee Safet Review and Audit Board Vice President-Electric 0 erations RESPONSIBILITIES Review results of environmental The function of the Vice President monitoring programs prior to sub- Engineering and the Vice President mittal in each annual environ- Electric Operations are identical mental operating report.- for environmental matters with those described for safety in the Technical Specifications of Appendix A.

Review proposed changes to the en- Review proposed environmental vironmental techni cal speci fications technical specification changes and the evaluated impact of the change. or license amendments. Submit ana'lysis to the Vice President-Engineering and Vice President-Electric Operations for the sub-mittal to the NRC-Review proposed changes or modifi-cations to the station systems or equipment and the evaluated impact which would require a change in the procedures or which would affect the evaluation of the station's environ-mental impact.

Review the environmental technical specification development with the safety technical specifications to avoid conflicts and for consistency.

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

I TABLE 5.3 Cont'd.)

Vice President-Engineering Site 0 erations Review Cornnittee Safet Review and Audit Board Vice President-Electric 0 eratioss Investigate all reported violations Review violations of environmental of environmental technical specifica- technical specifications and sub-tions. Mhere the investigation mit an analysis to the Vice Pres-indicates, prepare and forward a re- ident-Engineering and the Vice port covering their evaluation and President-Electric Operations.

recommendation to prevent recurrence, to he General Superintendent Nuclear Generation, and the Chairman of the Safety Review and Audit Board.

AUTHORITY

'dvisory to the General Superintendent The Board shall report to and advise Nuclear Generation the Vice President-Engineering and the Vice President-Electric Operations in all matters relating to environmental impact.

Hake tentative determinations as to whether or not proposals submitted to the committee involve a change in the station's environmental impact. This determination subject to review by the Safety Review and Audit. Board.

RECOROS Separate minutes shall be kept of all meetings of the SORC when convened for review of environmental matters. Copies shall be sent to the General Superintendent Nuclear. Generation and to the Chairman of the Safety Review and Audit Board.

TABLE 5.3 Cont'd.

Vice President-Engineering Site 0 erations Review Committee Safet Review and Audit Board Vice President-Electric 0 erations MEt IBERSHIP The membership of the Site Operations Review Committee and the Safety Review and Audit Board shall be as shown in 6.2-2 of Appendix A.

MEETING FREQUENCY, QUORUM The meeting frequency and quorum requirements shall be identical with those listed in Figure 6.1.4 of Appendix A.

5.6

5. 6.1 Routine Re orts a ~ Annual Environmental Operating Report PART A: Nonradiological Report A report on the environmental surveillance programs 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 6 months after January 1 of each year. The report shall include summaries of the nonradiological environmental surveillance activities (Section 3) for the'report period. If harmful effects or evidence of 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.

mittedd PART B: Radiological Report A report on the radiological environmental surveillance pro-grams for the previous 12 months of operation shall be sub-to the Director of the NRC Regional Office (with a copy to the Director, Office of Nuclear Reactor Regulation) as a separate document within 6 months after January 1 of each year. The reports shall include summaries of the radiological environmental surveillance activities for the report period. The reports shall also include the results of land use censuses required by the specifications. If harmful effects or evidence of irreversible damage are de-tected by the monitoring, the licensee shall provide an analysis of the problem and a proposed course of action to alleviate the problem.

58

0 y t

li

b.6.1 (Cant'd.) ~

Results of all radiological environmental samples taken shall be summarized and tabulated on an annual basis in the format of Table 5.6. In the event 'that some results are not available within the 6 months period, the re-port shall be submitted noting and explaining the reasons for the missing results. The missing data shall be sub-mitted as soon as possible in a supplementary report.

b. Radioactive Effluent Release Re ort A report on the radioactive discharges released from the during the previous 6 months of operation shall be 'i.te submitted to the Director of the NRC,Regional Office (with a copy to the Director,.Office of Nuclear Reactor Regula-tion) wi thin 60 days after January 1 and July 1 of each year. The report shall include a summary of the quan-tities 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 effluents during each quarter as prescribed in Section 3.1.1(b)(3).

5.6.2 Nonroutine Re orts a ~ Nonroutine Environmental Operating Reports A report shall be submitted in the event that (a) a limit-ing condition for operation is exceeded (as specified in Section 2, "Limiting Conditions'or Operation" ) or (b) 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:

59

K 0

'5.6.2 (Cont'd.)

(1) ~Prom t ~Re ort. 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, telegraph, or facsimile transmission to the Director of the NRC Re-gional 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).

(2) ~30-Da ~Re ort. Those events not requiring prompt re-ports shall 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 Regulation).

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

l<ritten 10-day and 30-day reports and, to the extent pos-sible, the preliminary telephone, telegraph, or facsimile 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 significant changes made in procedures) taken to preclude repetition of the occurrence and to prevent similar occurrences involving similar components or systems.

b; Nonroutine Radiological 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 submi tted to the Director of the NRC Regional Office (wi th a copy to the Director, 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.

• A confirmatory reanalysis of 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 consistent'ith the analysis,but in any case within 30 days.

60

I TABLE 5.6 Facility Nine Yiile Point Unit 1 Docket No. 50-220

~Ei R Average quarterly Results (specify radionuclide or entity)

Medium/Sample Location quarter 1 quarter 2 quarter 3 quarter 4 AIRBORNE Particulate 1) 2)

Iodine 1) 2)

Soil 1) 2)

DIRECT 1) 2)

l/ATERBORNE Surface 1) 2)

Ground Drinking

I TABLE 5.6 (cont.)

~AUATIC Sediment 1) 2)

Benthic Organisms 1) 2)

Plants 1) 2)

INGESTION Hi 1k 1) 2)

Fish and Shellfish 1) 2)

Heat and Poultry 1) 2)

OTHER B. Evaluation (include a sumMIary evaluation of the results from the monitoring program).

NOTES FOR TABLE 5.6

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. pCi/m , iodine, water and milk, pCi/1, sediment, and vegetation, pCi/gm dry.

I

)

. 5.6.2 (Cont d.)

C. l<onroutine 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 ac-tivity 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 2.4, the licensee shall make an investigation to identify the causes of such releases and define and initiate a program of action to reduce such releases to the design objective levels. A written report of these actions shall be submitted to the Director of the NRC Regional Office- (with a copy to the Director, Office of Nuclear Reactor Regulation) within 30 days from the end of the .quarter during which the re-occurred. The release levels at which such a re- 'ease port is required are given in Specifications 2.4.l..h 2.4.3.c for liquid and gaseous releases, respectively.

'nd In addition, Specification 2.4.3.f gives condition under which a report is required within 10 days...

~ )I Executive Vice President Chief Engineer En ineering, Operations and Employee Relations (NMPC) PASNY I

Vice President Engineering (NMPC)

V'c~Pr sid ~ - E~g~~~g tl<iPC I I

SAFETY REVIEll 5 AUDIT BOARD SITE OPERATIONS REVIEW COMMITTEE Staff Engineer or 'Manager - Chm General Superintendent Nuclear Gen. Chm.

Staff Technical Plant Superintendent-- FitzPatrick Plant Assistance General Superintendent Station Superintendent Nine Mile Point Unit 1 Nuclear Generation Results Supervisor Staff Engineer Nuclear Reactor Analyst Supervisor Staff Engineer Mech. or Electrical Radiochemistry and Radiation Protector Supervisor Other Staff Engineer Environmental Instrument 5 Control Supervisor Consul ta nts Consultant* Maintenance Supervisor As Required PASNY Principal Nuclear Engineer PASNY Resident Manager PASNY Project Engineer

• At least one technical member from outside Niagara Mohawk Power Corporation organization for the first few years of Station Operation FIGURE 5.3 SAFETY ORGANIZATION NINE NILE POINT - JAMES A. FITZPATRICK SITE

I 5.3. 2 The responsibi1 i ties and authori tie of the environmental review and audit units are shown in Table 5.3.

5.4 Action to be Taken if a Limitin Condition for 0 eration is Exceeded 5.4.1 Remedial action as permitted by the technical specification shall be taken until the condition can be met.

5,4. 2 Exceeding a limiting condition for operation shall be inves-tigated by the Site Operation Review ComIiittee.

5 4..3

~ A report for each occurrence shall be prepared in accordance with one of the schedules specified. in Section 5.6.2 or as required by the particular specification involved.

5.5 Procedures Detailed written procedures, including applicable check-lists and instructions, shall be prepared and followed for all activities involved in carrying out the environmental technical specifications. Procedures shall include sam'-

pling, data recording and storage, instrument calibration, measurements and analyses, and actions to be taken when limits are approached or exce'eded. 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.

I

, 3.1.2.b (Cont'd.)

b. Terrestrial NOT APPLICABLE

l' TABLE 3.1-1 FREQUENCY OF SAYiPLING FOR ECOLOGICAL SURVEY IN THE NINE NILE POINT AREA OF LAVAGE ONTARIO Surve equality Grou ~Fee uenc Period A. Mater Bimonthly April through October B. General Ecological Survey (Site)

Phytoplankton and Zooplankton Bimonthly April through October Benthos Bimonthly . April through October Fish Gill Netting Bimonthly April through October Ichthyoplankton Monthly April through August C. Impingement of Organisms Collection of Impinged Fish Monthly Jan., Feb., July through Dec.

Weekly triarch through June NOTE:

Bimonthly means every other month Sampling shall not be required when prevented by inclement weather.

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I 3.2 Radiolo ica1 Environmental Honitorin OBJECTIVE An environmental radiological monitori'ng program shall be conducted to evaluate the effects of Station operation on the environs and to verify the effectiveness of the controls on radioactive material sources.

SPECI F ICATION An environmental radiological monitoring program shall be conducted as follows:

a ~ The environmental radiation monitoring program specified in Table 3.2 shall be conducted. Variations from the frequency availabilityy and location of samples are permitted if due to sample un-or seasonal conditions,

b. Reporting requirements for the environmental radiological monitoring program are outlined in Section 5.6.

c ~ During the seasons that animals producing milk for human con-sumption are on pasture at locations that may be significantly affected~ by emissions from Nine tlile Point-l, samples of fresh milk shall be obtained monthly. For those animals on pasture 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 1.0 picocuries per liter of milk at the time of sampling. For activity levels at or above 1.0 picocuries per liter, counting error (two sigma confidence level) of the analysis shall b'e with-in + 50 percent. Results shall be reported with associated calculated error, as picocuries of I-131 per liter of mi lk at the time of sampling'pecial attention shall be paid to those locations where milk is produced for direct consumption by humans; e,g., the family farm.

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

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

e TABLE 3.2-1 SAMPLE COLLECTION AND ANALYSIS SITE RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM A. LAKE PROGRAM(1)

MEDIA SENSITIVITY ANALYSIS ~FRE UENCY LOCATIONS( )

1. Fish 80. pCi/Kq dry GSA, Sr 5 Sr 2/yr 2 onsite 1 o fsi te

2. Cladophora N/A GSA in season 2 onsite 1 offsi ~

3. Lake Mater N/A GSA N Comp. .,(3) 3H~ 89Sr, 9OSr Qtr. Comp.

NOTES:

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

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

(3) The three lake water samples to include Nine Nile Point Unit 1 intake water, James. A'. FitzPatrick intake water, and Oswego city raw water,

TABLE 3.2-1 Cont'd.

SAMPLE COLLECTION AND ANALYSIS SITE RADIOLOGICAI ENVIRONMENTAL MONITORING PROGRAM B. LAND PROGRAM(

MEDIA ANALYSIS FREQUENCY NO. OF LOCATIONS LOCATIONS

1. Air Particulates- GB At least .10 7 onsite 6 offsite" GSA M Comp(4)

2. Soil GSA, Sr Every 3 years 13 7 on site 6 offsite

3. TLD Gamma Dose Qtr. 20 14 onsite 6 offsite~

4. Radiation Monitors Gamma Dose At least 7 7 onsite 1 offsite

5. Airborne -- I GSA At least 10 7 onsite 6 offsite

6. Milk I 4(5) (6)

GSA, Sr

7. Human Food Crops . GSA, I (6)

8. Heat, Poultry, Eggs GSA Edible Portions (6)

NOTES: (Cont'd.)

(4) Onsite samples counted together, offsite counted together, any high count (greater than three times average of latest four weeks of samples) counted separately.

(5) Frequency applied only during grazing season.

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

Abbreviations:

H Comp. - Monthly composite of weekly or bi-weekly samples A - Annually GB - Gross beta analysis W - Meekly BM - Bi-weekly (alt'ernate wks.)

GSA - Gamma spectral analysis on a NaI or GeLi system ,H - Monthly Qtr. Quarterly (quantitative) C - Continuous SA - Semiannually

V I

0'f 3.2 (Cont'd.)

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 to-gether with the preoperational background data, will pro-vide verification of the effectiveness of Station effluent control and indication of measurable changes in the ac-tivity of the environment.

The concentration of I-131 in milk of 2.4 picocuries per liter 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 a dose of greater than 15 mrem/year'to the thyroid, it is necessary to know the radioiodine concentration in

'eceive the milk to the sensitivity given above, 1.0 pCi/liter.

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

50

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SPECIAL SURYEILLANCE AND STUDY ACTIYITIES NOT APPLICABLE

I I 0

5.0 Administrative Controls OBJECTIVE Administrative controls for implementation of th'e Environmental Technical Specifications are the means by which environmental protection is subject to Station management control and indepen-dent review and audit. These measures ensure that the Environ-mental Technical Specifications will be properly implemented.

5.1 Res onsibilit 5.1.1 The responsibili ties of the General Superintendent-Nuclear

.Generation as prescribed in paragraph 6.1.1 Appendix A shall include the continuing protection of the environment.

5.1. 2 Operation of the Station in compliance with the Environ-mental Technical Specifications is the responsibility of the Station Superintendent with the assistance of the Sta-tion staff organization.

5.1.3 The structure of corporate responsibility is shown in Figure 6.2-1 of Appendix A.

5.2 ~Or anization 5.2.1 The Station organization and its relationship to the site organization is shown in Figure 6.2-2 of Appendix A.

5.2.2 Environmental monitoring will be performed by site technical personnel and when requested by environmental consultant personnel. Engineers from the corporate staff will be avail-ab'le for technical assistance when required.

5.3 Review and Audit

5. 3.1 Units for review and audit of environmental matters shall be organized as shown in Figure 5.3. In addition to the regular members of the Site Operations Review Committee, a responsible supervisor from each consultant organization performing environmental monitoring shall participate in Committee meetings as required.

52

I CflANGES IN ENV IRQNf'1ENTAL TECNNICAL SPECIFICATIONS A report shall be made to the NRC prior to implementation of a change in plant design, in plant operation, or in procedures described in Section 5.5 if the change would have a significant effect on the environment or 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.

b. Request for changes in environmental technical specifica-tions shall be submitted to the Director, Division of Reactor Licensing, for review and authorization. The request shall include an evaluation of the environmental impact of the proposed change and a supporting benefit-cost analysis.

i RECOROS RETENTION 5.7.1 Records and logs relative to the following areas shall be made and retained for the life of the plant:

a. Records and drawings detailing plant design changes and modifications made to systems and equipment as described in Section 5.6.3

b. veillancee, Records of all data from environmental monitoring, sur-and special surveillance and study activi ties required by these environmental technical specifications.

5.7.2 -

All other records and logs relating to the environmental tech-nical specifications shall be retained for five years follow-ing logging or recording.

1 0

LAND t!ANAGEMENT It is Niagara Mohawk's policy to encourage growth of desirable species of trees, shrubs and ground covers which will preserve and enhance the ecological values .of unoccupied land on its generating sites and transmission rights-of-way. lransmission line maintenance is accomplished on a scheduled basis under the supervision of Niagara Mohawk personnel and includes selective use of herbicides, approved for such use by appropriate govern-mental agencies. The guides for the use of herbicides are as follows and apply within the site boundary:

a ~ Selective use of herbicides 'shall be employed to maintain "tight grou'nd cover" which will allow growth of compatible weeds and woody species and tend to encourage wildlife habitat growth.

b. No herbicide shall be used in an application for which it is restricted by the New York State Department of Environ-mental Conservation (DEC) restricted use list.

C. Herbicides such as 2, 4, 5-T or;similar compounds which are approved for use by the U. S. Environmental Protection Agency and DEC for the purpose intended shall be used as prescribed and directed by registered label.

d. No formulation with a dioxin contamination level that exceeds O.l parts per million shall be used.

e. No contamination of portable water suppl.ies shall be per-mi tted.

f. Application of herbicides to potential human foodstuffs including wild berries shall be avoided.

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

h. Treatment shall,.not be more than once ger year i<hen the Administrator of FPA and the DEC issue standards for pesticide applicators,'all spraying shall be done by an individual meeting these standards or under his immediate supervision. . Implementation of this requirements shall con-form to any compliance schedule contained in such standards.

5.8 (Cont'd.)

When it becomes necessary to cut or spray vegetation which in the wilting stage has a potential for physiological harm to grazi ng animals, precautions shall be taken to preclude availability of such material to livestock.

h, Only selective use of herbicides shall be employed on vegeta-tion used for road and stream screening. Such application may be used to eliminate undesirable species which would en-croach on the right-of-way and inhibit the growth of more desirable species. Treatment shall be such that visual im-pact is minimized. Treatment of stream screening vegetation shall be performed such that no herbicide shall be intro-duced into the water body.

l. Aer',al spraying operations shall be performed only when wind speed is less than 5 mph. During such operations a procedure to control drift shall be employed. Two examples of an ac-ceptable procedure are:

(1) A thickening agent may be added to the herbicide mix to permi t "on target" deposition.

(2) A "microfoil" delivery system may be used to control droplet size.

m. Work of contractors performing spray operations shall be inspected for compliance with these specifications.

logs) shall be kept for each inspection.

Records'field Subject to the above restrictions, herbicides may be used in ini-tial clearing operations and in right-of-way maintenance. Follow-ing initial clearing, stumps will be treated with herbicides to prevent "resurge". It is Niagara Mohawk policy to -effectively remove tall-growing species from the right-of-way which'can invade the "wire securi ty zone" through the use of herbicides. This policy allows low-growing compatible species to occupy the grow-ing space. Subsequently, as field observations dictate, various herbicides may .be employed on a selective basis to prevent the growth of those species which could result in interference and potential short circuit of transmission lines.

I Attachment B Niagara Mohawk Power Corporation License Ho. DPR-63 Docket Ho. 50-220 Su ortin Information It is proposed that the Environmental Technical Specifications for Nine Mile Point Unit 1 be revised in four general areas:

l. Instrumentation sensitivities changes are pro-posed to allow for reasonable deviations inherent to current "state of the art",measurement devices.

2. Changes are proposed to account for site specific rather than 'generic industry conditions.

3. Changes are proposed to the environmental sampling .

and analysis program.

4. Changes of an editorial nature are proposed for clarification.

Table 1 lists the sections that have been revised and the justification for revision.

Over the past four years, sampling at the site has been successful

'in establishing the variety, abundance and viability of the total aquatic community. The net revised sampling -and analysis program will meet the goal .of maintaining "no harm" to the receiving water body by mon'itoring changes to the established abundance and variety. of the present aquatic community and providing for corrective action as necessary. By changing the scope and purpose of the program from discovery to 'monitoring the characteristics of the aquatic community, it is estimated that annual pro-gram cost will be reduced significantly. Niagara Mohawk believes these savings can be realized without sacrifice of environmental care or reduction in environmental concern.

I Table 1 Summar of Chan es Environmental Technical Specifications Section Oescri tion Basis for Chan e

=

Table of Contents Changes required by changes in Editorial content List of Figures Changes required by changes in Editorial content C List of Tables Changes required by changes in Edi tori al content 1.8 Definition of "Ambient Lake Elimination of Temperature," retitled, "Lake language ambiguity.

Intake Temperature," establishes correlation between the location of the temperature, as defined, and the location of the temper-ature, as measured.

2.1.1 The hT is established as the Elimination of difference in temperature language ambiguity.

between measured temperatures in the inlet and discharge tunnels. Change correlates measured temperatures with defined temperatures.

2.1.4 Changes in wording. Editorial 2.3.1 Changes in wording. Editorial 2.3.2 Changes in wording. Section Editorial refers to Tables 2.3-1 and

, 2.3-2. Refer to changes in Tables specified below.

Reference to (Cr 04 2) is deleted as inconsistent with Table 2.3-1.

Table 2.3-1 -Suspended solids is changed EPA effluent guidelines from 15.0 mg/1 to 100. mg/1 have been chanoed from prior to dilution. 15 to 100 mg/l.

0 II

Sc:ction Descri tion Basis for Chan e Table 2.3-2 pH measurements of the See basis under monthly composites of the in- Section 2.3.4.

take, discharge, and waste tanks are deleted. Conductivity measurement of waste tanks for each batch js added. Analysis for Cr 0 a is deleted and Cr substi-tute therefor.

2.3.3 Reporting specifications are Clarity of language added for clarity. Nine Mile and conformance to 1 will not use Nine Nile 2 current situation.

water purification facilities; therefore, the contingency specification is deleted.

2.3.4 Conductivity measurements Basis paragraph added. pH excursion as changed provides authorized for low conductivity support for change tanks. to allow for site specific pH ex-cursions. No adverse impact on water quality is predicted'limination 2.4.2 Reporting requirements are of added to the specification. ambiguity.

Table 2.4-1 Sampling and analysis require- Editor ial ments are adjusted for easier understanding. Table 2.4-3 is delet d. See list of tables for new titles.

2.4.3 The equation in 2.4.3 a (1) Edi tori al is corrected.

2.4.4 Table 2.4-4 and reference Elimination of thereto is deleted as no ambiguity.

longer necessary.

Table 2.4-3 Tabl e i s adjusted for eas i er El imina tion of.

understanding and more. ambiguity.

accurate identification of specifications.

3.1 Introductory remarks added. Remards provide gnneral basis for major changes to Section 3.

1 I

Section Descri tion Basis for Chan e 3.1.1a. l<ater quality sampling Reduced scope Figure 3.1-1 specification reduced in supported by Table 3.1-1 'cope and modified in introductory remarks.

language. Specification rewritten for clarity of under-standing.

3.l.lb Atomic Energy Coomission Editorial changed to Nuclear Regulatory ,

Commission.

Table 3.1-2 Table establishes concise Elimination, of Table 3.1-3 requirements for tleteorological abmiguity.

Measurement without reference to the Reg. Guides.

3.1.2 Reduction in aquatic sampling Reduced scope Figure 3.1-1 and analysis. supported by intro-Tabl,e 3.1-1 ductory remarks.

Change specification

.purpose to aquatic monitoring effort rather than investiga-tion effort.

3.2 Change sensitivity fo, deter- Conform to the mination of radiodine con- sensitivity of centrations from 0.5 picocuries measurement in-per liter to 1.0 picocuries strumentation.

per liter. Provides adequate margin of safety.

Table 3.2-1 Simplifies and reduces sampling Reduce cost without and analysis procedures for changing the objective radiological monitoring of lake or reducing requirement organisms. Editorial changes.

5.1 Changes in words to conform Editor ial to Appendix A.

Figure 5.3 Yiodification in SRAB to include Editorial PASNY Project Engineer:. Change title of PASNY representative to SORC to correct title.

5.5.1 Changes conforming to deletion Editorial of 5.5.2.

5.5.2 Deleted. Redundant with Section 5.3.

0 I Section Descri tion ~ ~ai t Cl 5.6.1 Change semi-annual to an Annual report annual report. provides required information at lower cost.

5;7 Clarifies records retention Eliminates for non-specified records. ambiguity.

5.8n Survey for bog turtle Two years of eliminated. surveys have indicated that neither the bog turtle nor bog turtle habitat is present in'.this location.

References eliminated. Editorial

V~ r"

~,

I j

Attachment B Niagara Nohawk Power Corporation License Ho. DPR-63 Docket No. 50-220 Su ortin Information It is proposed that the Environmental Technical Specifications for Nine Nile Point Unit 1 be revised in four general areas:

1. Instrumentation sensitivities changes ar'e pro-posed to allow for'easonable deviations inherent to current "state of the art" measurement devices.

2. Changes are proposed to account for site specific rather than generic industry conditions.

3. Changes are proposed to the environmental sampling and analysis program.

4. Changes of an editorial nat'ure are proposed for clarification.

Table 1 lists the sections that have been revised and the justification for revision.

Over the past four years, sampling at the site has been successful

'in .establishing the variety, abundance and viability of the total aquatic community. " The new revised sampling and.analysis program will meet the goal of maintaining "no harm" to the receiving water body by monitoring changes to the established abundance and variety of the present aquatic community and providing for corrective action as necessary. By changing the scope and purpose of the program from discovery to monitoring the characteristics of the aquatic community, it is estimated that annual pro-gram cost will be reduced significantly. Niagara Mohawk believes these savings can be realized without sacrifice of environmental care or reduction in environmental concern.

li 1

Table 1 Summar of Chan's Environmental Technical Specifications Section Descri tion Basis for Chan e Table of Contents Changes required by changes in Edi torial content List of, Figures Changes required by changes in Edi torial content List of Tables Changes required by changes in Editorial content

.1.8 Definition of "Ambient Lake Elimination of Temperature," retitled, '"Lake 1 anguage ambigui ty.

Intake Temperature," establishes

, correlation between the location of the temperature, as defined,'nd the location of the temper-ature', as measured.

2.F 1 The AT is established as the Elimination of difference in temperature language ambiguity.

between measured temperatures in the inlet and discharge tunnels. Change correlates measured temperatures with defined temperatures.

2,1.4 Changes in wording. Editorial 2.3.1 Changes in wording. ~ Edi tori al

\

2.3.2 Changes in wording. Section Editorial refers to Tables 2.3-1 and 2.3-2. .Refer to changes in Tables specified below.

Reference to (Cr 04 2) is, deleted as inconsistent with Table 2.3-1.

Table 2.3-1 Suspended solids is changed EPA effluent guidelines from 15.0'mg/1 to 100 mg/1 have been chanded from prior to dilution. 15 to 100 mg/l.

V tD l

Section Descri tion Basis for Chan e Table 2.3-2 pH measurements of the See basis under monthly composites of the in- Section 2.3.4.

take, discharge, and waste tanks are deleted. Conductivity measurement of waste tanks for each batch js added. Analysis for Cr 0 " is deleted and Cr substi-tute3 therefor.

facile 2.3.3 Reporting specifications are Clarity'f language

'dded for clarity. Wine Nile and conformance to 1 will not use N'ine 2 current situation.

water purification facilities; therefore, the contingency specification is deleted.

2. 3'. 4 Conductivity measurements Basis paragraph added. pH excursion as changed provides authorized for low conductivity support for change tanks. to al'low for site specific pH ex-cursions. Ho adverse impact on water quality is predicted.

2.4.2 Reporting requirements are Elimination of added to the specification. ambiguity.

Table 2.4-1 Sampling and analysis require- Edi tori a 1 ments are adjusted for easier understanding. Table 2.4-3 is delet d. See list of tables for new titles.

2.4.3 The equation in 2.4.3 a (1) Edi tori al is corrected.

2.4.4 Table 2.4-4 and reference Elimination of thereto is deleted as no ambiguity.

1'onger necessary.

Table 2.4-3 Table is adjusted for easier Elimination of understanding and more. ambiguity.

accurate identification of specifications.

3.1 Introductory remarks added; Remards provide gnneral basis for major changes to Section 3.

~q 4

Section Descri tion Basis for Chan e 3.1.1a.'" l]ater quality sampling Reduced scope Figure 3.1-1 specification reduced in supported by Table 3.1-1 scope and modified in introductory remarks.

language. Specification rewritten for clarity of under-standing.

3.1.lb Atomic Energy Comission Editorial changed to Nuclear Regulatory Commission.

Table 3.1-2 Table establishes concise Elimination of Table 3.1-3 requirements for Heteorological abmiguity.

Measurement without reference to the Reg. Guides.

3.1.2 Reduction in aquatic sampling Reduced scope Figure 3.1-1 and analysis. supported by intro-Table 3.1-.1 ductory remarks.

Change specification purpose to aquatic monitoring effort rather than investiga-tion effort.

3.2 Change sens i ti vi ty fo deter- Conform to the mination of radiodine con- sensitivity of centrations from 0.5 picocuries measurement in-per liter to 1.0 picocuries strumentation.

per liter. Provides adequate margin of safety.

Table 3.2-1 Simplifies and reduces sampling, Reduce cost without and analysis procedures for changing the objective radiological monitoring of lake or reducing requirement Editorial changes.

organisms.'hanges 5,1 in words to conform Edi tor ial to Appendix A.

Figure 5.3 Modification in SRAB to include Editorial PASNY Project Engineer. Change title of PASNY representative to SORC to correct title.

5.5.1 Changes conforming to deletion Editorial of 5.5.2.

5.5.2 Deleted. Redundant with Section 5.3.

4 PG.l Section f Change Descri tion semi-annual to an

~Bi<<Ch Annual report annual report. provi'des required information at lower cost.

5.7 Clarifies records retention, Eliminates for non-specified records. ambiguity.

5.8n Survey for bog turtle Two years of eliminated. surveys have indicated that neither the bog turtle nor bog turtle habitat is present in this location.

6 References eliminated. Edi t'or i al '

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• 1