Text

Tech Specs 1.0-5.0 for Facility;App B to License DPR-54
	ML19319E164
Person / Time
Site:	Rancho Seco
Issue date:	08/16/1974
From:	; SACRAMENTO MUNICIPAL UTILITY DISTRICT
To:	;
References
	NUDOCS 8003310683
	Download: ML19319E164 (53)
	v • d • e

{{#Wiki_filter:i, I \\ O APPENDIX B E OPERATING LICENSE NO. DPR-54 TECHNICAL SPECIFICATIONS FOR THE RANCHO SECO UNIT 1 SACRAMEN'ID MINICIPAL ITTILITY DISTRICT DOCKET NO. 50-312 \\ m 9 4 4 V 4 sf soessie g 3 f 4M r m y e~r w--- - ~ q

s TABLE OF CONTENTS fage_ l.0 DEFINITIONS 1 2.0 ENVIRONMENTAL PROTECTION CONDITIONS 4 2.1 Maximum Discharge Temperature 4 2.2 Chlorine 5 2.3-Dissolved Solids 5 2.4 -pH 7 2.5 Other Chemicals Which Affect Water Quality 7 2.6 Radioactive Discharges 9 3.0 NON-RADIOLOGICAL ENVIRONMENTAL SURVEILLANCE PROGRAMS 25 3.1 Erosion 25 3.2 Drift Contaminants 25 3.3 Liquid Effluent Contaminants 26 3.4 Noise 26 3.5 Fogging 27 3.6 Reservoir Drawdown 29 4.0 RADIOLOGICAL ENVIRONMENTAL MONITORING 31 4.1 Fish 31 4.2 Algae and Other Aquatic Plants 31 4.3 Surface and Runoff Water 32 4.4 Mud and Silt 33 4.5 Fresh Milk Sampling 34 4.6 Rabbits 35 4.7 Edible Vegetation 36 4.8 Well Water 37 4.9 Airborne Particulate and Iodine 37 4.10 Direct Radiation - 38 i 5.0 ADMINISTRATIVE CONTROLS-42 5.1 Responsibility 42 5.2 Organization 42 5.3' Review and~ Audit 42 5.4 Action to be taken in Event of Violation of an Environmental Protection Limit 43 5.5 Procedures 44 5.6 Plant Reporting Requirements 44 5.7 - Records Retention 46 5.8 Special Requirements 47 3 -1

-..:mw e,ww-m m eam m. - w., w m m a a u :ww imwmew.. l -1.10 Daily -(A time paciod.a within 24-ho~.r span from'0000 to 2400 hours from Monday through Friday excluding District holidays. 1.11 ' Weekly - A time period from Monday through Sunday spaced to occur 52 times a year. 1~.12 Fortnightly - A time period covering two consecutive weeks spaced to occur 26 times a year. 1.13 Monthly - A time period from the first.to last day of a calendar month spaced to occur 12 times a year. 1.14 -Quarterly - A time period of three calendar months spaced to occur four times a year. 1.15 Semi-Annual - Time periods from January 1 and July 1 covering the sub-sequent six months. 1.16 Composite Sample - A composite sample is defined as a combination of no fewer than eight individual samples obtained over the specified sampling period. The volume of each individual sample is proportional to the discharge flow rate at the time of-sampling. The sampling period shall equal the discharge period, or 24 hours, whichever period is shorter. 1.17 Radioactive Materials - The radioactive materials originated by the nuclear reactive process. This specifically excludes the concentrating _ of naturally-occurring environmental radionuclides. 1.18 Critical Path - Any significant food chain mechanism which terminates with consumption (eating or drinking) b? man. 1.19 Receiving Waters.- The water body downstream from the confluence of Clay Creek and Hadselv111e Creek. ~1.20 Shift - A time period covering 8 hours, three shifts equally dividing a .24-hour' time period. ~ Functional'T0st - Injection' of an internal or external test signal 1.21 into the channel to. verify its proper response, including alarm I and/or trip initiating action,.~where applicable. l-1.22- ' Instrument Check - Verification'of acceptable instrument performance L .by observation of its behavior and/or state; this verification includes L comparison of output and/or state of independent channels measuring i the same variable.. 1.23 Instrument Channel Calibration - An instrument channel calibration is a measurement, and adjustment (if necessary), to establish'.that the . channel' output responds with acceptable range.and accuracy to known values.of the parameter which the channel measures or an accurate

simulation of these values.:. Calibration shall. encompass the entire l

9 Ih 1 11.0 DEFINIT 10NS 1.1 ~ Environmental Technical Specification - l Limitations, conditions and requirements which are considered necessary for the protection of the environment and require

appropriate action to be taken if exceeded.

1.2 Emergency Load Demand - Load demand in excess of power supply 1 which, if not met, would result in system voltage reductions -or load shedding of some Sacramento Municipal Utility District customers or contractual customers. 1.3 A' Grab Sample is defined as an individual sample collected in -fever than 15 minutes. i 1.4 CRWQCB defined as the State of California Regional Water Quality Control Board, Central Valley Region and its order 1 No. 74-174 dated February-22, 1974. 1.5 Noise - The mechanica'l vibrations within the audible range as measured within the requirements set forth in the USASI American National Standard Specification for General Purpose Sound Level Meters S1.4 (1971). 3 - 1.6-State of California Department of Water Resources Contract - The Davis-Grunsky Act Grant Contract No. D-GGR28 between State of Ca Mfornia and Sacramento Municipal Utility District of April 6, F... Exhibit B. ~1.7 Continuous Monitorina - Defined as the automatic analysis equip-ment that produces a permanent recording of the measured parameter or an increased grab sampling technique-for obtaining the values of .the measured parameter as' described in Section 4 of these-

specifications.

1.8 Chlorine - The measurement'is defined-as total residual chlorine, ..which is capable of killing bacteria and. algae. The method of analysis will-include chloramines and organically bound chlorine. E 1. 9. Environmental Deviation - An environmental deviation is said to occur;.whenever an envirot. mental protection condition or report Llevel is-exceeded, or'whenever, in'the opinion of the plant superintendent,..an unusual event involving significant environ-y/: mental ~. impact has occurred.' 1 -- s .-m_.,

_;m 3 s + ; ; y m 3,e ; g ; g.;g - , ;n ;, - p ~:n;. ;cgg;Q l ENVIRONMENTAL PROTECTION CONDITIONS 2.0 i -2.1 Maximum Discharge Temperature i Objective i l To protect biota in Clay Creek and other bodies of water into which the liquid effluent from the station may flow. ' Specification The cooling water effluent temperature at the discharge _ structure shall not _ exceed 90*F except for brief periods for operational adjustments of.the dilution flow, or as necessary to enable the station to meet emergency load demands on the licensee's power supply system. If the 90'F limitation is exceeded for as long as 4 hours in any 24-hour _ period,.the effluent temperature shall be decreased as necessary by reducing the station's power operating level and the AEC shall be notified in accordance with non- . routine reporting procedures - (Section 5.6.2.C). Monitorina Requirement O. Plant water discharge temperature shall be continuously recorded at-the discharge structure. An. alarm will be provided in the Control Room to' indicate the status of this temperature. During periods when the measuring equipment-is defective or under repair,. alternate instrumentation shall be provided within 4 hours during water discharges or representative data readings of the discharge water temperature shall be logged every 4 hours during water dis-charges using a handheld thermometer. Basis The 90*F effluent temperature.was selected by the CRWQCB as the ' maximum permitted for Rancho Seco. The AEC's environmental renew (see the Final Environmental Statement) did.not reveal. j_ that exposure to higher temperature discharges (which could result without prior mixing with cooler dilution water) for short j periods of time'would have significant impacts on biota. l l-Normally, between 800 and 1000 spa of plant affluent with chemical impurities'will be' discharged to Clay Creek. Little, if any, will reach Hadselville Creek due to irrigation use of the effluent;- however the water may reach Hadselville Creek and the Consunnes River in the winter.- During-the summer, Rancho Seco may have to add up to 3,200'gpa of Folsom South Canal water to dilute the plant ' effluent so that' the discharge temperature will not exceed ^' 90* F.- 4-

-( channel,. including equipment actuation, alarm, or trip and shall be deemed to include the channel test. 1.24 Environmental' Release Point - The location on any effluent release -line, stack tube pipe or similar conduit from the site, beyond which the licensee has no control, as referenced by Criterion 60 and 64, 10 CFR Part 50 and 10 CFR Part 20.106. 1.25 Principle Isotopes - Those radionuclide isotopes which constitute 95% of the total activity. 1.26 Critical - The term " critical," as used in Regulatory Guide 4.1 on " Measuring and Reporting of Radioactivity 174 the Environs of Nuclear Power Plants," is defined in ICRP Publication 7 approximately as follows: certain nuclides and certain expor re pathways are much more important than others in t'a situation of a given nuclear power plant on a specific site. These important pathways (and nuclide's) are designated " critical". They are treated in the AEC's Final Environmental Statement and are the pathways generally proposed to be monitored in these Environmental Technical Specifications. j -3.

w mw: - am ma,w w mew.mrp. 2.w,x w wm n+ m1x C. The discharge shall not cause visible oil or grease slicks, scum or foam on the receiving waters. D. The discharge-shall not cause fungus, slimes or other bio-logical growths in the receiving waters or along the creek banks. Monitoring Requirements A. Plant water discharge conductivity shall be recorded con-tinuously at the discharge structure. An alarm will be provided in the Control Room to warn the operator prior to exceeding a level of conductivity which corresponds to the specification limit. If the setpoint is exceeded on the conductivity monitor, the discharge will be diluted to bring the dissolved solids concentration below the specification. B. During periods when the discharge conductivity monitor is out of' service, alternate instrumentation'shall be provided within 4 hours or grab samples will be taken every 4 hours h' during water discharges. C. The discharge water course will be inspected weekly at 100 yards downstream of the site discharge, 100 yards up Hadselville Creek from the confluence of Hadsciv111e and Clay Creeks, 1 and 100 yards downstream of the confluence of 11adselville and Clay Creeks for pollutants, oil, grease slicks, scum, foam or undesirable biological growths. Records of each inspection will be documented, indicating the individual, his findings and investigation made to determine the cause, l Basis i All plant effluent water will be transferred through the waste water' system either directly to Clay Creek or-temporarily to one .of two'500,000 gal.-retention basins before release'to the creek.- The restrictions require that. discharged ~ waste water not exceed a monthly average concentration of 800 mg/i total dissolved solids, placing the water in Class II for21rrigation use. ~ The combination of-treatment.and dilution of the station effluent water, coupled with the continuous monitoring program, will assure that effluent quality conforms with the CRWQCB standards-and will permit safe disposal of. effluent to the public domain. -) l

t The maximum ' discharge velocity 'will be 2.6 f t/sec. at the. exit - with a total flow of 4,000 gym. The average discharge velocity will be'O.66 ft/sec. at the 1,000 gym discharge flow rate.

2. 2 -

Chlorine Objective To prevent discharging chlorine at concentration levels intolerable to living organisms. Specification-The effluent water shall contain total residual chlorine not to exceed a maximum rate of 0.2 mg/ liter. Monitoring Requirement Grab samples of the effluent water shall be collected and analyzed weekly for total residual chlorine. The samples will be obtained from the outlet of the discharge structure at the interval after chlorination which is found experimentally to indicate the =av1== 7 - concentration. If there is no chlorination during the scheduled . 1 (.. sample period, the sample will be obtained during the following. -period. Basis Interni.ttent use of chlorine will be required for cont.21 of algae in the circulating water system and will result in periodic . low residuals of chlorine in the effluent water which will not be + harmful to living organisms. The limit of 0.2 ag/ liter was established by the CRWQCB. 2.3 Dissolved Solids Objective To prevent discharging' materials that would make the effluent unusable for-irrigation, or that would be detrimental to the environment surrounding the-receiving water. . Specification A. The total' dissolved' solids shall not exceed a maximum con-centration.of.850 mg/i or a maximum daily amount of 34,000 lbs. f' -B. 1The total dissolved solids shall not' exceed a 30-day average G/ ' . concentration of 800 mg/i or a 30-day average daily amount .of 32,000 lbs.. - 5'- r .--I . -=.. -. - - - - -. ,,e.r-

.w-wma q~ m " ww+ a n u t a x m a 4 3 ma.e l Specification. .A.- The discharge shall not cause the concentration of dissolved . oxygen'in the receiving waters to be less than 5.0 mg/1. --B. The effluent water shall not contain dissolved boron in excess of 1.2 mg/L or 48 lbs per day and 1.0 mg/L or 40 lbs/ day when ~ averaged over 30 days. C.. The effluent. water shall not contain dissolved zine in excess 'of 0.4 mg/L or 16-lbs per day and 0.3 mg/L or 2 lbs/ day when averaged over 30 days. i-Monitoring Requirement -Grab: samples of'the plant effluent water for oxygen analysis shall be , obtained 100 yards downstream of the plant discharge and from Hadsel-ville Creek at points 100 yards upstream and 100 yards downstream of the confluence with Clay Creek and analyzed weekly. These samples will give an indication of the quality of the effluent water from the plant and be representative of the overall plant operations. Samples of the affluent water for boron and zine analysis shall be collected and atalyzed on a monthly 24-hour composite schedule. The samples will be obtained from the outlet of the discharge structure. Basis All limite.tions in this specification were established by the CRWQCB. L The Aquatic Life Advisory Committee

recommends that the dissolved oxygen content of warm-water fish habitats be not less than 5 mg per liter during I'

at least 16 hours of'any 24-hour period. It may be-less than 5 mg per liter for a period not to exceed 8 hours within any 24-hour. period, but at no time;should the dissolved oxygen content be less than 3 mg per liter. The above analyses indicate that there is a reasonable assurance that a minimum of 5.0 mg per'11ter dissolved oxygen in the plant effluent will not adversely affect fish life in the receiving waters.. Dissolved oxygen of the effluent waters should be near saturation because of the aeration within the cooling towers. The minute quantities of boron and zinc'are received from the"Folsom South Canal as makeup water and concentrate in the cooling towers.- Dilution before discharge may be required to reduce the levels below these limits. These-elements may-be present'in the plant, but are mainly derivec from the concentrating mechanisms of the cooling towers and, in general, are not of plant origin.

Anon., Aquatic Life Water Quality-Criteria, First Progress Report, Ohio River

Valley Water Sanitation Commission,: Aquatic Life Advisory Committee, Sewage &

Industrial Wastes 27, 321 (1955). 8-

s g-216 -Radioactive Discharges Obj ective : To define the limits and. conditions for the controlled release of radioactive materials in liquid and gaseous effluents-to the environs. j to ensure that these releases are as low as practicable. These re-1 leases should not result in radiation exposures in unrestricted areas greater than a few-percent of. natural background exposures. The - release rate for all effluent discharges shall be within the limits - specified in 10 CFR Part 20. - To assure that.the-releases of radioactive-material above background to unrestricted areas be as low as practicable as defined in Appendix I . to 10 CFR Part 50, the following design objectives apply-1 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 dis-chargel from the plant should result in an air dose due to ~ gamma radiation of'less than 10 mrad, and an air dose due to beta radiation of less than 20 mrad, at any location near ground ' level which could be occupied by individuals at or.beyond the . boundary of.the site. D.- The annual total quantity of all radioiodines and radioactive material in particulate forms above background from all reactors at a site should not result in an' annual dose to any organ of an ~ . individual in an unrestricted area from all pathways of exposure .in excess of 15 mrem. - E. .The: annual quantity of iodine-131 discharged from each reactor at a-site should'not exceed 1 Ci. '2.6.1 Specifications for' Liquid Waste Discharges-i ^ . A. The. concentration'of radioactive materials released in liquid wastes from all reactors at'the site-shall not exceed the values specified in 10 CFR Part!20,EAppendix B Table II, Column 2, for F unrestricted areas. _9_

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-B.. The release ~ rate of radioactive materials in liquid wastes, ex-cluding tritium'and dissolved gases,-shall not exceed 10 Ci/ reactor / -calendar quarter. C. 'The release rate of_ radioactive materials in liquid wastes, excluding tritium and dissolved gases, shall not exceed 20 Ci/ reactor in any 12 consecutive months. D.- During release of radioactive wastes, the effluent control moniter shall be set to alarm _and to initiate the automatic closure of the waste discharge valve prior to-exceeding the limits specified in 2.6.1.a above.. .E. The-operabilf_ty of_the automatic isolation valves in the liquid discharge lines shall be demonstrated quarterly. F. - The equipment installed in the liquid radioactive waste system i shall be maintained.and shall be operated to process radioactive liquid wastes prior to theiridischarge when the projected cumulative release rate.will exceed 1.25 C1/ 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 C1, excluding tritium and dissolved gases.

H.

.When the release rate of radioactive materials in liquid wastes, excluding tritium and dissolved gases, exceeds 2.5 Ci/ reactor / calendar quarter, the licensee shall_make-an investigation to identify the causes for such release rates, define and inititate a program of action to reduce such release rates to the design objective levels listed in Section 2.6, and -report these actions to the~ Commission within 30 days from the end of the quarter during which.the release occurred. 2.6.2 Specifications for Liquid Waste Sampling and Monitoring .A._ " Plant records shaltbe maintained of the radioactiva concentration ~~and volume befone dilucion:of liquid waste intended for discharge 8 and the averagefdilution flow and length of time over~which each discharge occurred. Plant records shall'be submitted in accordance -with Section 5.6.1 of _these specifications. Estimates of the error associated with1each reported _value shall be included.-

B..

Prior to release of each batch of liquid waste, a sample shall be (taken from that batchLand' analyzed for'the concentration of each significant gamma energy'peakiin accordance with Table 2.6-1 to . demonstrate compliance with Specification 2.6.1 using the fJow rate ]) + Linto which the waste is discharged during the period of discharge. i.

4

~ ?. l m7; f ~ i C. Sampling'and analysis of liquid radioactive waste shall be per-formed in accordance with Table 2.6-1. Prior to taking samples I from~a M 'oring tank, at least two tank volumes shall be .recirculateu or the agitator shall be operated sufficiently to achieve complete mixing. l D. Theiliquid: radioactive wastes shall be continuously monitored and recorded during release. Whenever these monitors are inoperable i

for.a period not to exceed 72 hours, two independent samples of ear.h tank to be discharged shall be analyzed and two plant personnel shall independently check valving prior to the discharge.

If these monitors are inoperable for a period exceeding 72 hours, no liquid waste tank shall be released and any release in progress shall be' terminated. E. The flow rate of liquid radioactive waste shall be measured and recorded during release. i F. All liquid' radiation monitors shall be calibrated at least quarterly by means of a radioactive source which has been calibrated to a1 National Bureau of Standards source. Each i monitor shall also-have a functional test monthly and an instrument check prior to making a release. 1 Bases - The release of radioactive materials in liquid waste to unrestriered . areas shall not. exceed the concentration limits specified in 10 CFR Part 20 and should be as low as practicable in accordance with the - requirements-of 10 CFR Part 50.36a. These specifications provide reasonable ~ assurance _that the resulting annual exposure to the total body or any organ of an individ"el in an unrestricted area will not exceed 5 area. At the.same tin-. these specifications permit the flexibility of: operation, compatible with considerations of health - and safety,sto 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 'withinlthe concentration limits specified in 10 CFR Part 20. It is expected that~by using'this' operational flexibility under unusual operaticnfconditions,~and exerting every effort to keep levels of radioactive material in_ liquid wastes as low as. practicable, the . ann'ual releases willinot exceed a small fraction of the concentration limits-specified'in 10 CFR Part 20. - The design. objectives have been ~ developed based :on operating experience - taking into account a combination of variables including defective fuel, primary system ~1eakage,. primary to secondary system leakage and the - performance of the various waste treatment systems,'and are consistent l-with Appendix Iito 10 CFR Part 50. i: - ~. ~ w s-w- e w-- a, v- - -- u -,v-v -wr o nev---- - ~mv g,

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4 7, ) TSpec'ification'2.6.1.A requires the licensee to limit the concentration of radioactive materials'in'11guid wastes from the site to levels specified in 10 CFR Part 20, Appendix B Table-II,. Column 2, for unrestricted areas. This specification provides assurance that no member of the general public 'will;be exposed to liquid containing radioactive materials in excess of limits: considered permissible under the Commission's Rules and Regulations .using the guidelines given in Regulatory Guide 1.21. Specifications 2.6.1'B and 2.6.1.C establish-the upper limits for the -release of' radioactive materials in liquid effluents. The intent of these Specifications 1s 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 aystems are functioning as designed. Re-leases of up to these limits will result in concentrations of radioactive l' material in liquid wastes at small percentages of the limits specified j in'10 CFR Part 20. Specifications 2.6.1.D and 2.6.1.E require that suitable equipment to con-trol and'ronitor the releases of-radioactive materials in liquid wastes are operating'during any period these releases are taking place consistent I with,the_ requirements of 10 CFR Part 50, Appendix A, Design Criterion 64. f f' Specification 2.6.1.F. requires that the licensee maintain and operate the equipment installed in the liquid. waste systems to reduce the release of radioactive materials in liquid effluents to as low as practicable consistent with the requirements of 10 CFR Part 50.36a. Normal use and maintenance of installed equipment in the liquid waste system provides reasonable assurance that-the quantity released will not exceed the design objective. In order to keep releases of radioactive materials as-_ low as practicable, the specification requires operation of equipment whenever 'it appears that the projected cumulative discharge rate will exceed 'one-fourth of.this design objectiv'e annual quantity during any calendariquarter. ' Specification 2.6.1.G.' limits the amount of radioactivity that may be i inadvertently released to the environment to an amount'that will not l- . exceed the: Technical Specification limit. ~ In addition to limiting conditions for operation listed under Specification 2.6.1.B and :2.6.1.C,the' reporting requirements of s-l c Specification 2.6.1.H : delineate that the licensee shall identify the cause whenever the release rate of radioactive materials in liquid wastes: exceeds one-half the' design objective: annual quantity during any. calendar. quarter and describe the proposed program of action to reduce.such; release rate to design objective levels on

actimely basis. This report must be filed within 30 days following

-the calendar quarter in which the release occurred. L

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~ 4 The sampling and monitoring requirements given under c ^cification a 2.6.2 provide assurance that radioactive materials f-tuid wastes - -are-properly controlled and monitored in conformanc .. the re-quirements'of Design Criteria 60 and 64. These requirements provide the data for the licensee and the Commission to evaluat.e the plant's performance relative to radioactive liquid wastes released to the environment. Reports on the. quantities of radioactive materials released in liquid wastes are' furnished to the Commission according to'Section 5.6.1.of these Technical-Specifications in conformance with. Regulatory Guide 1.21. On the basis of such. reports and any . additional information the Commission may obtain from the licensee or others, the Commission'may from time to time require the licensee to take such action as the Commission deems appropriate. The environmental release points to be monitored in Section 2.6.2 . include all the monitored release points as provided for in the ~ Final Safety Analysis Report. 2.6.3' Specifications for Gaseous Waste Discharges ( A.. (1) The-release rate limit of noble gases shall be: j EQ [ 62 i + 110 igg ] <_1 gy 1+n release rate (sum of 3 vents) from the unit where Q = l- ~ y vent in Ci/sec (ground release) 1 the individual nuclide n = total nuclides i = iy = the average gamma energy.per disintegration-56 = the average beta energy per disintegration Refer to Table.2.6-3-for E and E values to be used. Y D -(2) _TheLrelease' rate limit of-all'radioiodines.and radioactive l materials in particulate form'with half-lives greater than -eight-day's,-released to the environs'as part of the gaseous wastes chall?be: t 5 'l.7 x 10 q f. L "2,; -where Q,=' release rate (sum of 3 vents) from the unit vent'in Ci/sec (ground release) l l' - I31-' ~ m-

s, w m., - m yww;,%, m o -B. (1) The average release rate of noble gases during any cale dar quarter shall be: IQ, [390 Y g + 350 E ] 5 1 g gg 1+n' (2) The average ~ release rate of noble gases during any 12 consecutive months shall be: IQ [780 I + 700 I .1 11 gy gg i+n (3) The average release rate of all iodines and radio-actim materials-in particulate form with half-lives J greaur than eight days during any calendar quarter shall be: 6 2.14 x.10 gi7 y (4)- The average release rate of all iodine and radio-active materials in particulate form with half-lives greater than eight days during any period'of 12 con-secutive months shall be: 6- -4.28 x 10 iy (5) The amount of iodine-131 released during any calendar quarter shall not exceed 2 C1. -(6j 1he amount of iodine-131 released during any period of 12 consecutive months shall not exceed 4 C1. C.- 5 Should[the conditions of 2.6.3.C(1), (2), or (3) listed below exist, the licensee shall make an investigation to identify - the causes of the release rates, define and initiate a program of action to reduce the d1 ease rates to design objective levels, listed in Section.2.6,: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 during any -calendar quarter is: 'IQ, [1545 Eg + 1413 5 ] > 1- ], 1 g 1+n. ' 14 -

m ( (2) If the average release rate of all iodines and radioactive materials in particulate form with half-lives greater than eight days during any calendar quarter-is: 6 8.55'x 10.q ,1 -(3) If the amount of iodine-131 released during any calendar quarter is greater than 0.5 Ci. D. During the release of gaseous wastes from the primary system waste gas holdup system the effluent 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 4 specified in 2.6.3. A (1) above. The operability of the automatic ' isolation valves shall ba demonstrated qua.terly. E. The maximum activity to be contained in one waste gas storage tank shall not exceed 135,000 curies (considered as Xe-133). 2.6.4 Specifications for Gaseous Waste Sampling and Monitoring 'A. Plant reco,rds 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 error associated with each reported value should be included. B. Gaseous releases'to the environment, except from the turbine building ventilation exhaust and as noted in Specification 2.6.4.C,.shall be. continuously monitored for gross radioactivity and the flow measured and recorded. 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. E C.- During the release of gaseous wastes from the primary system waste gas holdup system,'the gross activity monitor, the iodine collection device, and the particulate collection device shall be operating. D. All' waste gas. monitors shall be calibrated at least quarterly .by means'of'a known radioactive source which has been calibrated to a National Bureau of Standards source. Each monitor shall have a functional test at least monthly and instrument check at least daily.- E.; ' Sampling and analysis of radioactive material in gaseous waste, { 4, ^^" ~. particulate form, and radioiodine-shall be performed in accordance with Table 2.6-2. (Monitoring offradiciodine in gaseous release 1 from the turbine gland seal' exhaust. is not required until-December 1, 1974) - - 15 '- .me--- .,-e m ,ne n en ,,,ew- -e u.

a, an.mc y n x, w :: y & n.; d v e~t~ n w n v e s, x : w ; %Tuwxww w R% xwwwan ~ ) ^ ~ I l -1 Bases The^ release of radioactive: materials in gaseous wastes to un-restrictedLareas shall not exceed the concentration limits specified in 10~CFR Part 20, and in accordance with the require-ments of 10 CFR Part 50.36a. r These' specifications provide reasonable assurance that the re-sulting annual air dose due to gamma radiation will not exceed 10 mrad, and an annual air dose due to beta radiation will not

exceed 20 mrad from noble gases and that the annual dose to any organ of an individual from iodines and particulates *".11 not 2

o . exceed 15 arem. 'At the same time these specifications permit the flexibility of operation, compatible with considerations-of health and safety, to assure that the public is provided with ~ a dependable source of power under unusual. operating conditions which may-temporarily result:in releases higher: than.the design- -objective levels but still within the concentration 1Laits speciffad.in 10'CFR'Part 20. :It.is expected that using'this'

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~ operational flexibility under unusual operating conditions, and. by exerting every effort to keep-levels of-radioactive material in gaseous wastes as' low as practicable, the annual. releases will' not exceed -a' amallifraction of the concentration -limits specified'in>10 CFR-Part 20. These efforts should include con-sideration'of meteorological conditions during releases. There is a reduction factor of 243 by which-the maximum permissible concentration of radioactive =iodi'e iu. air should be reduced to allow for.the grass-cow-milk path ay. (The' factor is-1220 for the~ grass-goat-milk pathway.) T7 a factor has been derived'for -radioactive iodine. taking into account the milk pathway. It has been applied'to radionuclides of iodine and to all radionuclides in particulate form with a~ half-life' greater than eight days.- The factor-is!not appropriate"for iodine where milk is not a pathway J of exposure or. for che other radionuclides'. s The design objectives have been developed based on operating ' experience taking into account-al combination of system variables- --including defective. fuel, primary system leakage, primary to ~

secondary system leakage,'and~the performance of the various cwaste treatment: systems.

- Forl Specification 12.6.3. A(1) ~ dose calculations have been made for the_critica11 sector.': These' calculations' consider site meteorology, -buoyancyLcharacteristics, and.radionuclide content of the effluent ^ - 16

. ( of each unit. Meteorological calculations for offsite locations were performed, and the most' critical one was selected to set the . release _ rate. TheLeontrolling distance is 640 meters to the north. The gamma dose contribution was determined using the equation 7.63 in Section 7-5.2.5 of Meteorology and Atomic Energy - 1968. The releases from vents are considered to be ground level releases which acould 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 Meteorology and Atomic Energy - 1968. The beta dose contribution was determined on the basis of an infinite cloud passage with semi-infinite geometry for a ground level release (submersion. dose). The beta and gamma components of the gross -radioactivity in gaseous effluents were combined to determine the allowable continuous release rate. Based on these calculations, a continuous release rate of gross radioactivity in the amount specified in 2.6.3. A(1) will not result in offsite annual doses above background in excess of the limits specified in 10 CFR Part 20. The average gamma and beta energy per disintegration used in the equation of Specification 2.6.3.A(1) will be based on the average . composition of gases determined from the plant vent and ventilation exhausts. The average energy per bata or gamma' disintegration for those radioisotopes determined to be present from the isotopic analyses are given in Table 2.6-3. Where isotopes are identified that are not listed in Table 2.6-3, the gania energy are determined from Table of Isotopes, C. M. Lederer, J. M. 3ollander, and I. Perlman, Sixth Edition,1967, and the beta' energy shall be as given in USNADL-TR-802, II. Spectra of Individual Negatron Emitters (Beta Spectra), O. Hogan, P. E. Zigman, and J. L. Mackin. 4 For Specification.2.6.3.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-Jives -greater than eight days. The' calculations consider site meteorology for these' releases. 'For radioiodines and radioactive materials in particulate form, the controllingsectorforunitventreleasgsistgeNsectarata - sec/m ) for die dose due to distance of 640 meters (X/Q = 7.8 x 10 inhalation. :The nearest milk cow is located in.the NW sector at a distance'of ll,000 mgters. 3The applicable X/Q at the nearest 4 - sec/m. The grass-cow-milk-child thyroid milk cow is 7.05 x'10 chain is_ controlling. The assumptions used for these calculations are: (1) onsite meteoro-logical. data-for'the most critical 22.5 degree' sector; (2) credit for b, building wake;fand (3) a reconcentration factor 243 was applied for possible ecological chain effects from radioactive iodine and particulate releases. - -..-

w-w n wm +v ~wrm, =.amm mu-amwwcasum ~ + 4 J + Specification ~ 2.6.3.B establishes upper limits for the releases of

noble gases, iodines and particulates with half-lives greater eke.n eight days, and iodine-131 at.twice the design objective _annuel quantity during any calendar quarter, or four times the. design objective annual quantity during any period of 12 consecutive months.

The intent'of this specification is to permit the licensee the flexibility of operation to assure that the public is provided a _ dependable. source of power under unusual operating' conditions which may temporarily result in higher releases than the objectives. In addition to-the limiting conditions for operation of. Specifications ~ -2.6.3.Aland 2.6.3.B, the_ reporting requirements of 2.6.3.C delineate that'the cause.be identified.whenever the release of gaseous effluents exceeds.one-half the design objective annual quantity during any calendar quarter'and describe the proposed program of action to reduce such release rates to the design objectives. Specification 2.6.3.D requires-that suitable equipment to monitor and.centrol-the radioactive gaseous releases are operating during-any pcriod these. releases.are taking place. xm- -Specification 2.6.3.E limits the maximum'offsite dose above background

D$/

to below the limits 'of 10. CFR Part -20,. posttiating that the rupture of a waste gas storage tank holding the maximum activity releases all of the contents to the atmosphere. The sampling and monitoring requirements given under Specification 2.6.4 provide assurance that radioactive materials released in -gaseous wastes are properly controlled and' monitored in conformance with the' requirements of Design Criteria 60 and 64.. These require-(mentsLprovide the data for the licensee and the Commission to evaluate - the" plant'sl performance relative to ra/.oactive wastes released to the -environment. -. Reports on the quantities.of radioactive materials re-leased in gaseous effluents are furnished to the Commission on the-basis .of Section 5.6.1 of these Technical Specifications and in conformance .with Regulatory Cuide.l.21.. On the basis of'.such reports and any ! additional information the Commission ~may obtain-from-the licensee-or = others, the 1Coastission may. from time to time require the licensee to'take such action as'-the< Commission deems appropriate.. The environmental release points to.be monitored in'Section 2.6.4 in- .clude-allithe1 monitored release points l identified inithe Final Safety ~ . Analysis' Report.. Inasmuch as the monitoring of.radiciodines in gaseous release from the turbine gland seal exhaust is a recent requirement, -a:short; delay _for, implementation:of this monitoring.is-allowed in'

Specification 2.6.4.E ;to enable-the licensee to provide appropriate Leapability. fFulfillment of this item of the General Design Criteria-

) Epriortto Decembet'1, 1974 is not necessary to assure _the' health and } .18 c

s .a 4 ~ safety of the'public for the following reasons: (a) provisions .are included to monitor.for. radioactive contamination in the secondary coolant,.which is the' source of. turbine gland seal steam; (b) pro- _Lvisions are included to monitor individual gamma emitters in the. . gland seal' exhaust, which will provide an indicator to estimate s possible radiciodine from this low-flow release point; and (c) based .on provisions (a) and (b) above,'the radioiodine-release from the gland seal exhaunt may be estimated and corrective action pursued. i . Specification 2.6.4.B excludes monitoring the turbine building venti-lation exhaust since this release is expected to be a negligible i release; point. Many PWR reactors do not have turbine building , enclosures. To be consistent.in this requirement for all PWR reactors, the monitoring of gaseous releases from turbine buildings is not required. L 2.6.5

Specifications for Solid Waste Handling and Disposal A.

Measurements shall be made to determine or estimate the total - b curie _ quantity and principle isotopic composition ~of all radio- ' active solid waste shipped offsite. B.~ -Solid wastes in storage and preparatory to shipment shall be monitored and packagedLto assure compliance with 10 CFR Part 20, 10 (20t Part 71, and 49 CFR Parts 171-178. C. Reports of the radioactive solid waste shipments, volumes, principle isotopes, and total curie quantity, shall be submitted in accordance { .-with Section 5.6.1. Bases The requirements for solid radioactive waste handling and disposal .given under Specification 2.6.5: provide assurance that solid radio-active materials. stored'at the plant and shipped offsite are packaged in.conformance with 10 CFR.Part 20, 10 CFR Part 71, and 49 CFR Parts "171-178. ~These requirements provide the data for the licensee and the 0 - Commission to' evaluate.the. handling and storage facilities for solid lradwaste, Land to evaluate the^ environmental impact of offsite shipment and' storage. Reports on the quantities, principle isotopes and volumes of the-shipments, are furnished to.the Commission according to Section'5.6.1 of these. Technical Specifications. On the basis of~such

reports'and any additional information the Commission may obtain from

~ ~ the Llicensee or others,. the Commission may fran time to time require. -the: licensee to take such action as the Commission deems. appropriate. r -(', r ,.2 .L...

e; E + .. s

(

Table 2.6-1

1

-RADI0 ACTIVE LIQUIL SAMPLING AND ANALYSIS Q \\ Liquid Sampling Type of Deteetable Source Frequency Activity Analysis Concentrat; ions - ls (UCi/ml)t3)'

s A.

Tank Batch Releases Each-Batch Individual Gamma Emitters 5 x 10-7 (2) 3 One Batch / Month Dissolved Gases 10-5 i Weekly' Composite ( ) Ba-La-140, I-131 10-6 j. s "} g Sr-89 5 x 10-8 j Monthly Composite ( 11-3 '10-5 -7 Gross a 10 fiw Quarterly Composite ( Sr-90 5 x 10-8

.h l

_.s . i, i j.

W f ',. Table 2.6-1 (Continued) NOTES: (1) ' ' sampled is proportional to the quantity of liquid waste A composite. sample is one in which the quantity of liquid discharged from the plant. (2)- For certain mixtures of gamma emitters, it may not be possible to measure radionuclides in concentrations near their sensitivity limits when other nuclides are present in the sample in much 3 greater concentrations. Under these circumstances, it will be 'more-appropriate to calculate the concentrations of such radio-nuclides using measured ratios with those radionuclides which are routinely i$entified and measured. ' (3) - The detectability 10mits for activity analysis are based on the technica1' feasibility and on the potential significance in the environment of the quantities released. For some nuclidas, lower detection ILmits may be readily achievable and when nuclides s are measured -below the starad limits, they should also be reported. - (4) The power level and cleanup or purification flow rate at the sample time shall also be reported. a A e h., ~ 21 -

n w.: lj n j Table 2.6-2 = g RADIOACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS [ .Gaseousi Sampling Type of. Detectable; -Source Frequency Activity Analysis Concentrgons (pCi/ml) aA.:.. Waste Gas DecayL Each Tank Individual Gamma Emitters l'O 2) Tank Releases -6/ H-3 10 B.. Containment Purge Rele'ases' Each Purge Individual Gamma Emitters 10-(21 -6 11-3 ?10 -4 (2)(3). C. Condenser Air Ejector Monthly Individual Gamma Emitters 10 Releases: -6 11-3 10 ~4 ( )( ) D. Environmental Release Points Monthly Individual Gamma Emitters 10 (Gas Sampics) ' i 11-3 10 'E ~1 (4) Weekly (Charcoal Sample) I-131- + 10 G Honth1y (Charcoal Sample) 1-133, I-135 10 l ~ M Weekly. (Particulates) Individual Gamma Emitters _yy (4) f (at least for Ba-La-140, 1-131 10 Monthly Composite (5) ~1 Sr 10 (Particulates) 2 _yy_ Quarterly Composite ( ~11 Sr-90 10 (Particulates) .h.

e J ~. Tabic 2 6-2 (Continued) NOTES: (1) The above detectability limits for activity analysis are based on technical ~ feasibility and on 'the. potential significance in the environment of the quantities rcicased. For some nuclides, loker detection limits umy be readily achievable and when nuclides are measured below the ' stated limits, they should also be reported. (2) Analyses' shall also be performed following each refueling, startup or similar oper'ational occurrence which could alter the mixture of radionuclides. (3) For certain mixtures of gamma emitters, it may not be possibic to measure radionuclides at 1cycis near their sensitivity limits when other nuclides are present in the sampic at much higher icvels. Under these circumstances, it will be more appropriate to calculate - ( the -levels of such radionuclides' using observed ratios with those radionuclides which are measurable. (4). When the average daily gross radioactivity release rate exceeds that - given in 2. 6.3.c. (1) or where the steady state gross radioactivity . release rate increases by 50% over the previous corresponding power level steady state release rate, the iodine and particulate collection device shall be removed and analyzed to.dctermine the change in iodine-131.and particulate release rate. The analysis shall be done daily.following.such chang.c until it is shown that a pattern exists which can_be used to predict the release rate; after which it may revert to weekly sampling ~ frequency. (5) .To be representative.of the average quantities and concentrations of radioactive materials in particulate form released in gaseous effluents, s,amples should be collected in proportion to the rate of' flow of the effluent strcas.

aw- -c vm,, m m a m,,1. ) Table 2.6-3 AVERAGE ENERGY PER DISINTEGRATION Isotope E, mov/ dis. (Ref). E,.mev/ dis ( } (Ref) g Kr-83m 0.00248 (1) 0.0371 (1) 'Kr-85 0.0022 .(1) 0.250 (1) Kr-85m 0.159 (1) O.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) O' .Kr-90 2.10 (2) 1.01 (2) Xe-131m O.0201 -(1)- b.143 (1) Xe-133 0.0454 (1) 0.135 (1) Xe-133m O.042 (1) 0.19 (1) Xe-135' O.247 ' .(1)~ 0.317 (1) Xe-135m-O.432 (1) 0.095 (1) ~Xe-137 0.194 (1) 1.64 (1) Xe-138 ~1.18~ (1) O.611 (1) (1) ORNL-4923,' Radioactive Atoms - Suppleme'nt I, M.. S. Martin, November' 1973. (2) NEDO-12037, " Summary of Gamma and Beta Emitters and Intensity Data; M. E. ' Meek,-R.f S. - Gilbert, January 1970. (The average 8 energy was computed from.~th~e. maximum energy using the ICRP II equation, not.

the 1/3'value assumption used.'in this reference.)

(.1) The average,6 energy includes conversion electrons.- - 24'-- 3

- s

3. 0.

NON-RADIOLOGICAL ENVIRONMENTAL SURVEILLANCE PROGRAMS 3.1 Erosion Obj ective To prevent effluent water from Rancho Seco from causing severe erosion of the stream *oed ~ degradation of soil banks surrounding the effluent stream. _ Specification Visual inspection of the water course shall be made quarterly and documented. Prior'to initial criticality, a baseline inspection will be' performed. Any channeling or erosion *by the stream resulting in vertical cuts greater than 2' feet or lateral washouts greater than 5 feet in excess of the baseline shall be corrected. Reporting Requirement \\' Erosion above the specification 1Luits that is not or cannot be corrected shall be reported as required in Section 5.6.1. Bases The hardpack at the discharge structure is not expected to show significant soil erosion. However, if erosion is detected, corrective action can be taken well in advance of causing ecological damage. 3.2 Drift Contaminants Obj ective The objective of monitoring cooling tower drif t contaminants is to determine and' estimate deposition of entrained chemicals discharged as drift and particulates in some offsite regions. Specification Th'e sulfate content in soil shall be monitored quarterly from three sampling points. located symmetrically 0.25 miles from the cooling i towers. .The data on leachable sulfate in soil shall be used to determine the l significance of drift contaminants as addition to the existing sulfate

I ccatent-level in. soil.'

1 I i - 25'- L

,.:a - yL;a. : a ' % v= '.a.my n,,~ : = : x. mf? - m ww. Reporting Requirement If the-sulfate content in soil exceeds 1500 ppm as sulfate, a report .will be made to the AEC as per specification 5.6.1. Bases The most. predominant dissolved ion in the cooling water will be sulfate (430 ppm SO expected) due to the sulfuric acid injection 4 into the cooling water to reduce alkalinity. Sample locations will be selected after drift rain patterns have been observed from cooling tower operation. 3.3 Liquid Effluent Contaminants Obj ective ,The objective of monitoring liquid effluent contaminants is to deter-mine and estimate deposition of chemicals discharged and entrained on offsite agricultural regions. Specification The sulfate content-in soil shall be monitored quarterly from three sampling points located downstream in agricultural areas where plant effluent is used for irrigation. The data on leachable' sulfate in soil shall be used to determine the significance of effluent con-taminants as additions to existing sulfate levels in irrigated pas tures. Reporting Requirement If the sulfate content in soil exceeds 1500 ppm as sulfate, a report will be made to the AEC as per specification 5.6.1. Bases l The most_ predominant dissolved ion in the cooling water will be 1 sulfate (430 ppm SO expected) due to sulfuric acid injection into 4 L the cooling water to reduce alkalinity. Sample locations will be selected at three points on agricultural land downstream of the l plant where high usage is made of the effluent. i

3. 4 '

._ Noise obj ective To insure that noise levels emitted from.the plant are within normally ~ acceptable limits and to obtain a representative noise level'at the . plant boundaries.. - 26

. x )

(?J Specification A.

-During the initial startup and semiannually, noise level measure-ments shall be performed along the site boundary at 200 yard intervals. B. Records shall be maintained for all noise measurements and documented in special log book specifying noise level, location, instrumentation used and personnel making the measurements. Report Requirement The measured results of sound pressure level at the site boundary during normal plant operations at full power and at various weather-conditions shall be within normally acceptable NC-40 curve (see ' attached) for noise criteria as defined in Section 1. 1 Sound levels in excess of NC-40 curve for " clearly unacceptable" ranges shall be reported as required in Section 5.6.1. Bases

A typical power plant is a complex source of noise, making operational

.( . analysis of anticipated noise levels difficult and of little value Prime sources of noise at the Rancho Seco plant are expected to be the high speed turbine driven feed pumps, the transformers, and, infre-quantly,. operation of the safety relief valves. From the standpoint of the plant operators, protective actions will be taken which are consistent with the requirements of the State of California, Division of-industrial Safety. From the standpoint of the offsite public, extrapolation of test results obtained from operating fossil fueled power plants (a far greater source of noise than a nuclear unit) in-dicates that at the site boundary, the sound pressure level attrib-utable to plant operations at normal conditions of operations and weather is expected to be compsrable to the NC-40 curve for noise criteria. 'At the nearest dwelling, approximately one mile away, the sound pressure level would equal daylight. background conditions, with on'y. inoffensive. low octave rumble apparent at night. There is no:real criteria to-determine noise. Since noise 1s a relative' term,lthe measurements will be performed by measuring sound power as specified in the definitions. However, if complaints are' received from the local residents, this will be a criteria for consideration of corrective actions. '3.5 . Fogging' -Objective k _,' To record'ihe fogging patterns.that are associated with the cooling towers and to plot the extent of the cooling tower plume for ~ comparison with design characteristics.-. -. - -

1n., n-c;; - w- .m, + -- ^ .) NC-40 NOISE CURVE 09.9 g j 99.8 ( s \\, \\ Clearly 99.5 Unseceptsble 99.0 g 98 0 95.0 \\ \\ \\ S0.0 i\\ .a 80.0 y \\ \\ Normally 1 70.0 Unacceptable 60.0 a \\ l N \\ U 50.0 = \\ -sc==uy \\ \\ - 40.0 Accepechle \\ l \\ \\ \\ A 20.0 g \\ N \\ 10.0 \\ \\ \\ j \\ 5.0 N \\ \\ 2o x x x 2o ~ Clearly ~N \\ \\ Acceptable g 0.2 x x 0.1 40 50 60 70 80 A-Level (dB) ]l' -

Specification The thermal plume will be plotted on a map showing the intersection of the plume along State Highway 104 at ground elevation whenever such intersections are observed. Appropriate action will be initiated to warn motorists of possible fog cover at locations east and west of the plant. Reporting Requirement The extent of the fogging and duration shall be recorded and a report will be made to the AEC in accordance with Section 5.6.1 of these specifications. Bases There is little that can be done to prevent infrequent plume inter-section with the ground since this will be greatly dependent on atmospheric conditions. If there is an extended period of fogging, the plant power may have to be increased to produce maximum updraft to produce a greater lift force to penetrate the lower atmosphere. The vapor plume from the cooling towers has received extensive analysis. Environmental Report, Table 9.4-1 Incremental Environment Effects, Section 3.1 states that there will be zero hours of fogging that will interfere with ground and air transportation. The effects are discussed at length in Appendix 3C of the Rancho Seco Environ-mental Report and stated as " negligible" in the Final Environmental Statement. 3.6 Reservoir Drawdown Objective To provide notice when =ater for the recreational resources at the reservoir may not be available. Specification The licensee shall record in its semiannual operating reports any instances of deviations from the followins requirements which are included in a contract between the licensee and the State of California Department of Water Resources: "The_ reservoir level shall be maintained as ne rly as practicable at elevation 240 feet but in no event less than 239 feet, provided that: 1. For circulation of water to maintain proper water quality, the Aa reservoir may.be drawn to an elevation not less than 237 feet -on weekdays except national or state holidays between April 1 and October 31 each year. -

w..,.. _ x.

r.

w -

n,

n. n n uz w,:.c, n 0

2..

Between-November 1 and March 31 each year, the reservoir may be operated so that the pool elevation is not less than 237 feet. 3. To meet a physical need for water at Rancho Seco which cannot be satisfied from other sources, the reservoir may be drawn below elevation 237 feet. 4. The reservoir may be drawn below the above elevations for another purpose only with the prior written consent of the State. " Monitoring Re'quirement -A visual elevation monitor calibrated to read reservoir level is installed in the Control Room. The levt.1 shall be recorded and logged daily. When the visual monitor is inoperable, a direct reading shall be obtained and recorded from the reservoir level indicator on the inlet-outlet tower. Bases The availability of the Folsom South Canal should be high. During -the brief outages of the canal,. makeup from the reservoir will be required. To provide sufficient makeup water to Rancho Seco when the canal is not available, drawdown below 239 feet will be allowed. Decreasing the water level from the normal 240 feet level to-239 ft'et will not affect the recreational facilities nor endanger any aquatic species. At 237 feet, the recreational facilities are de-creased but still no aquatic life is endangered. Below 237 feet elevation,.many. factors must be considered, which will be evaluated .before obtaining.the written consent of the State. .h i :.30.-

[ \\ 4.0 RADIOLOGICAL ENVIRONMENTAL MONITORING 4.1 Fish Objective To obtain a representative sample of the fish in the site reservoir and to verify that Rancho Seco operations has not altered the radio-logical environment by determining no significant deviations between pre-operational and operational monitoring measurements. i Specification Two varieties of edible fish, one top feeder and one bottom feeder, in the site reservoir shall be collected quarterly, when available. The edible portions of the fish shall be analyzed for gross beta (less K40) and Sr90 Samples shall be collected as specified in Table 4-1. Reporting Requirement a The AEC will be notified according to Section 5.6.1 if the gross beta j activity' exceeds 54 nanocuries/kg or if the Sr90 level exceeds 9.2 nanocuries/kg. s Bases Samples obtained and analyzed from the above location will verify that Rancho Seco has not altered the radiological environment within the vicinity of the plant. This specification is a continuation of the pre-operational environ-mental radiological monitoring program established in the Rancho Seco Final Safety Analysis P. port. 4.2 Algae and Other Aquatic Plants J0bjective To obtain a representative sample of the algae in the Rancho Seco effluent and to verify that Rancho Seco operation has not altered the radiological environment by determining no significant deviations between pre-operational and operational monitoring measurements. Specification l Algae samples shall be obtained when available from the mixed plant effluent at the site boundary. A pint sample shall be collected (,c quarterly and analyzed for gross beta (less K40), Sr90 and gamma scan..

x. vi - ~ m TLw ~,";.- T U> v n :%ywdsi, c & W s Samples shall be. collected as specified in Table 4-1. Reporting Requirement The AEC;will be notified according to Section 5.6.1 if the gross beta activity exceeds 74 nanocuries/kg, the Sr90 level exceeds 1.0 nanocuries/kg, or the gamma scan-exceeds background (or minimum

sensitivity) by three' times for.the fission and activation products of plant origin.

$ases Samples obtained'and analyzed.from the plant effluent will verify that Rancho Seco has not altered the radiological environment within the effluent course. Rancho Seco being a dry site.will not have algae available con-tinually. However, when algae samples can be obtained, they will be analyzed and recorded. This specification is a continuation of -the pre-operational environmental radiological monitoring program established in the Rancho Seco Final Safety Analysis Report. 4.3 Surface and Runoff Water Objective ("T d To'_obtain a representative sample of waters within the Rancho Seco -environment and to verify that Rancho Seco eperation has not altered the radiological environment by determining no significant deviations between pre-operational and operational monitoring measurements. Specification Surface water samples shall be collected from the Camanche Reservoir, site reservoir, Folsom Canal and a site drinking fountain. The Camanche Reeervoir, a. major source of drinking water for the San ~ Francisco Bay Area,~ is in the potential fallout pattern when winds originate from the northwest. ;All samples will be collected.on a-monthly basis, and a portion filtered and the filtrate and solids analyzed separately for gross beta activities and a portion analyzed -for tritium. ~ Runoff water samples shall be collected downstream of the junction of - the plant affluent and the area runoff water. Samples are to be collected fortnightly and analyzed. A portion of the sample will be filtered and the filtrates and solids analyzed separately for gross.

beta. A gamma _ spectrum analysis will be performed.on,the filtrates and-solids. - A tritium analysis will also be performed on a portion of the' total. sample.

LSamples shall be1 collected from surface and runoff waters as specified q) ~ in Table'4-l~. - m -7 w r

Reportina Requirement LThe AEC.will be notified according to Section 5.6.1 if the gross beta exceeds 40 picocuries/ liter excluding tritium, the tritium level ex-ceeds 40 nanocuries/ liter or the gamma scan exceeds background (or minimum. sensitivity);by three times for fission and activation prod- .ucts of plant origin. 2 Bases Samples obtained and analyzed from.the above locations will verify that Rancho Seco has not altered the radiological environment within the vicinity of the plant. This specification is a continuation of the pre-operational environ-mental radiological monitoring program established in the Rancho Seco Final Safety Analysis Report. 4.4 Mud and Silt Objective-(: To obtain a representative sample of the sediment at the site 1 -reservoir and plant effluent. point. To verify that Rancho Seco operation has not altered the radio-1 logical environment by determining no significant deviations between . pre-operational and operational monitoring measurements. Specification .I i 'The mud and silt samples shall be collected at the plant effluent down-stream of the junction of the plant effluent and area' runo.'f water, + and in the site reservoir at a quiescent-location. One pin. samples aof mud and silt will be collected quarterly taking the top 3-inch of-material 2 feet out from the shoreline ~. The mud and silt samples will be analysed for gross beta. Samples. shall be. collected as specified in Table 4-1. Reportina Requirement 'The-AEC will be notified according to Section 5.6.1 if'the gross beta activity exceeds 160 nanocuries/kg.. f ' Bases - 4-Samples.obtained and analyzed from the above' locations will verifyf chi # that Rancho Seco'has not altered the radiological environment within lthe. vicinity of'the plant. f -133 ...q

mmmss wgA .x.a. ,aw -,- w -; + -; max 4 .This specification is a continuation of the pre-operational environ-mental radiological monitoring program established in the Rancho Seco Final' Safety. Analysis Report. 4.5 - . Fresh Milk Sampling Objective The purpose of this monitoring requirement is to measure the amount of 1-131. contained in milk used for human consumption produced in the vicinity of-the station. Specification 'During the season when animals ~are on pasture, samples of fresh milk shall be obtained weekly and analyzed for their radioiodine content, calculated as iodine-131. Analysis will be carried out within eight days (one I-131 half-life) of sampling.- Suitable analytical procedures will be used to determine '{} .the radioiodine content to.a sensitivity of 0.5 picoeuries per liter' -of milk.at the time of sampling. Overall error of this analytical procedure will be within + 25%. Results will be reported, with~ associated calculated error, as picoeuries of I-131 per liter of milk at the time of sampling,- in accordance with Reporting Require-ments 'oelow. Samples-shall be collected as specified in Table 4-1. -Reporting Requirement The'AEC will be notified'according to Section 5.6.2: 1. If individual milk samples show I-131' concentrations of.19 -picoeuries/ liter.or greater,.a plan will be submitted within one week advising-the AEC of the proposed action to ensure "the-plant related' annual doses will~be within the design objective of 15 mres/yr to the thyroid-of any individual. 2. If milk samples collected over a calendar quarter show average concentrationsLof 4.8 picoeuries/ liter or greater,.the results shall.be reported and a plan submitted and. implemented within 30 days to limit conditions so that the annual dose to an . individual:will not exceed 15 mrem / year.. ~ 34 - L

-Bases To assure that no one child will receive a dose of greater than 5 mram/ year to the thyroid, it is necessary to know the radioiodine concentration in the milk to the sensitivity given above: 0.5 pci/ liter. A 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 arem/ year, based upon consumption of one liter per day for the year. Rabbits i Obj ective To obtain a representative sample of native rabbits in the vicinity of the Rancho Seco site and to verify that Rancho - (. Seco operations has not altered the radiological environment by determining no significant. deviations between pre-operational -and-operations monitoring measurements. Specification Two adult rabbits shall be collected quarterly from surrounding areas of the site, when available. Rabbit femurs shall be analyzed for Sr90, rabbit th l31, and the edible flesh for gross-beta (less K{roids for I 0), Samples shall be collected as specified in Table 4-1. Reporting Requirement The AEC will be notified according to Section 5.6.1 if the Sr90 activity? exceeds'70 picoeuries/gm of bone, the I131-i activity exceeds 26 picoeuries/ge'or if the gross beta exceeds 110 nanocuries/kg. Bases Samples'obtained and analyzed from the above locations will , verify that Rancho Seco'has not altered.the radiological l = environment within the vicinity of the plant. l l1 This specification is.a. continuation of the pre-operational l l environmental radiological monitoring program established.in l ^ the Rancho Seco Final Safety Analysis Report. l-

_u a.. ,Msa% F:: ^ kn _ &a N uS%g.aufi = 4 4 4.7 ~ Edible Vegetation Objective To obtain a representative sample of land vegetation in the vicinity of the Rancho Seco site and to verify that Rancho Seco operation has not altered the radiological environment by determining no significant deviations between pre-operational and operational monitoring measurements. Specification Samples of edible vegetation, intended for human consumption, shall be collected at four sites within fif teen air miles of the reactor. The locations are Clay, Ione, Clements, and 5 Sloughhouse. Edible vegetation for cows will be collected 10 miles west, 7 miles northwest, 9 miles southwest, and 1 mile east of the site. Two samples of human edible vegetation, including both leafy ] and fleshy vegetables or fruits will be collected from each of the above sites each year when.available. Part of the collection ? is to be made in the spring.(i.e., May and June) and part in the summer and early fall.(1.e., July, August, September). Samples of animal-edible vegetation are to be collected monthly from field vegetation eaten by'the dairy cows. Two kilograms are to be collected at each location for each species of sample. All samples shall be analyzed for gross beta, less K40 Sr90 will be determined in cow foodstuffs so that milk-vegetation balances can be determined. Samples shall be collected'as specified in' Table 4-1. Reporting Requirement The AEC will be notified according to Section 5.6.1 if the. gross beta activity exceeds 82 nanocuries/kg or if the Sr90 .. level exceede 5.0 nanocuries/kg. Bases. ~ Samples.obtained and analyzed from the above-locations will verify that Rancho'Seco has not altered the radiological environment within~the vicinity of the plant. This specification is a continuation'of the pre-operational h ~ environmental radiological monitoring program established in 6 -the Rancho Seco Final Safety Analysis-Report. ' ~ - 362-

'4.8 Well Water Objective To obtain a representative sample of well water on and adjacent to the Rancho Seco site and to verify that Rancho Seco operation has not altered the radiological environment by determining no significant deviations between pre-operational and operational monitoring measurements. Specification. Well water samples shall be collected from the on-site well, the reservoir well 1 1/4 miles east of the restricted area, the Clay Station cattle feedlet one-quarter mile south of the exclusion area, and.a well in the Clay area. The latter is .1.5 to 2 miles west-southwest of the site, in the predominant ~ water flow direction. f The site well samples provide information on natural radioactivity 1 in the waters as they reach the site. The other three locations provide verification that plant' effluents are not affecting .l ( local water supplies. The samples will be collected quarterly i from each water source. Gross beta and tritium analyses will be performed on the samples. 4 Samples shall be collected as specified in Table 4-1. Reporting Requirement The AEC will be notified according to Section 5.6.1 if the gross beta activity exceeds 30 picoeuries/ liter excluding tritium or the tritium activity exceeds 40 nanocuries/ liter. Bases-Samples,obtained and analyzed from the above locations will verify that Rancho Sect has not altered the radiological environment within t b vicinity of the plant. This specification is a continuation of the pre-operational radiological monitoring program established in the Rancho Seco Final Safety Analysis Report. 4.9 ' Airborne Particulate and Iodine Objective-l: ' (' 'To obts %.a. representative sample of the air particulates and gaseous radioiodine at locations surrounding the plant and to. wrify that Rancho _Seco operation has not altered the radiological I environment..by determining no significant deviations between L pre-operational and operational monitoring measurements. 37 -- ... ~ -.

a m.--# %, %,, - ;. a..w, w_m w.w w;;.,o.ss .a;- w.m nm I Specification. Samples'shall be collected from eight stations, whose locations are selected on the basis of available meteorological data and populationLeoncentrations.. Weekly samples are to be collected at each site.~- Continuous air sampling charcoal cartridges and-131 filter papers will be analyzed for I and gross beta, respectively, by direct counting. A gamma spectrum analysis.will be performed on quarterly' composites of the filter papers from each station, while a gross alpha analysis will be performed quarterly on an ashed composite sample from each station. Samples shall be collected as specified in Table 4-1. Reportina Requirement The AEC will be notified according to Section 5.6.1 if the l31 exceeds 40 femtocuries/m, gross beta activity exceeds 3 il 3 3 2.0 picocuries/m, or the gross alpha exceeds 10 femtocuries/m. gq J -Bases Samples obtained and analyzed from the abwe locations will verify that Rancho Seco has not altered the radiological environment thrcugh airborne processes. This specification is a continuation of the pre-operational environmental radiological monitoring' program established in .the Rancho-Seco Final Safety Analysis Report. 14.10 Direct Radiation Objective. To'obtain'.alrepresentative sample of direct and gaseous radiation near the plant and surrounding areas and to verify that Rancho Seco operation has not. altered the radiological environment by i l; determining no significant deviations between pre-operational ~ F~ andl operational-monitoring measurements.

Specification TLD badges are installed at eight onsite and eleven offsite

locations to. measure integrated background radiation levels.

L l.- ~ 9The locations.have-been" selected based on available meteorological ' data, prevailing wind' direction, and population concentration. L

Samples shall be collected.as specified in Table 4-1.-

~ _. x

1 i Reportinc Requirement The AEC will be notified according to Section S.6.1 if the TLD radiation levels exceed 10 mr/ quarter above natural background. Bases Samples obtained and analyzed from the above locations will verify that Rancho Seco has'not altered the radiological environment near the plant and surrounding areas. The eight onsite badges are placed to give an indication of direct ~ radiation from the plant. The eleven offsite locations are well out of direct radiation influence and will give an indication of the gaseous radiation level. This specification is.a continuation of the pre-operational environ- ' (_ ' mental radiological monitoring program established in the Rancho Seco Final Safety Analysis Report. 1 I l -s _ 39 - .~.

m, t TA31.E 4-1 0FERATIOTAL DfV180:rtC;TAL RADIATION *t51NRIE PERAM Seaple Surface location oni Vell Isad 1%st ' Wo., Air hacoff Vater 7egetetloc Milk n d. Pebbits red Be ckgrot:r.d C r** Figure 4 Vaters Silt Fri1* tien On Site C. Drinking Water, 1 M(1)- 0(1)

b. Boservoir.

1 M(1) C(1) M(1) F(1) C(2) 'C(1) C(1) -

c. Fert:: ster Fence 1

V(1),C(1) C(2)* C(7)

4. Flant 7.fnuent 1

F(1) C(1) C(1)* -S . b !" orth 'er Site

o. Eesidence 2

V(1),Q(1) C(1)

b. Dntry 3

M(1) F(1) . c. Tctson South Canal' 4 M(1)

d. Slotdiouse.

5 SY(*) South of Site

o. cerr.1 6

V(1),c(1) c(1) ~ c(1) b, Clements 7 ST(*) .e. Certnehe Asservoir 8 V(1),Q(1) P(1) (1)

d. Dairy 9.

M(1) F(1) C(1) F st of !!te

s. Ione 10 V(1),Q(1)

SY(*) C(1)

b. c rdeceale -

17 v(1), c(1) c(1) "egt cf 3't* a, cl.T 11 c(1) SY(e) ett)

b. Elk Grove Dairy 12 M(1)

F(1) C(1)

s. Colt 13 c(1)

SoutSv-st of Et ta. Zodi 14 V(1),0(1) C(1) Te-tNest of 'ita. Sacrarento (2tD) 16 V(1),q(1) q(g) SF' Irs 8 9 2 8 4 2 2 2 10 1 V - Veekly_ F - Fortnightly. M - Monthly, Q - Qusrterly ST - Semi-Anrs=1 (-) - Indicates r.taber of semples

Sampled when ovellable

'l

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, -. -.., 'o-.-- ly s.* v&, g.;4,_..,. . :M@ i i ,p.. f r .:-l.g !.._Q'.I.-..,,_..L,.. - [. -.. .go 4 i s!** o 4 W.A$ - W., .[y/ ) M --- h..;.- p.V N.. I \\ lgl c i 7 sn (3.(- ..L s / .j s l j .,- 3 ;. 5 a ,Q, [- _.,. q _. D D) V v d' O m' 9 T D<I a f v s .A. ] RANCHO ~ SECO I UNIT'1 FIGURE 4. Sample Collection r. QM ENVIRONMENTA1, TECHNICAL SPECIFICATIONS Location Stations h1 i =

z. ~^ ' ..:~~u

2:.

^ W ';r

m u;b t,

^ - -. ---.. s a L 4 ,O) 'o I. L 5.0: ADMINISTRATIVE CONTROLS i 5.1' Responsibility A. The Nuclear Pir.nt Superintendent is responsible for the operatioa of the facility and to assure that the facility ~ -operates witbin the limits set forth in the environmental 4 technical srecifications'. l B.: In all matters pertaining to nuclear operation of the facility.and to the environmental technical specifications, .the Plant Superintendent shall report to, and consult with, ~the Chief Engineer and Assistant General Manager. i C.. The Plant Chemical and: Radiation-Supervisor is responsible l .for maintaining the environmental monitoring program. There will be a semiannual audit of specifle phases of the program l-by-the Quality Assurance Group which will report their findings directly to'the. Assistant General Manager and Chief N-Engineer.- All audit results will be recorded in the records of the Management Safety Review Committee. l l 5.2 Organization The organization charts are shown in Figures 5-1 and 5-2. 'The functional organization with respect to environmental matters .is shown in cross-hatch. This involves reporting from the a: Chemical Radiation. Supervisor through the Assistant. Superintendent of' Technical. Support to the Plant Superintendent. The Technical-Assistant remains as an independent review and audit authority .to monitor compliance with'these Technical Specifications. 1 15.3 ' Review and Audit

p [

"i:ommitt'ees.for review and audit of plant operation are described 1if; - in Section 6.'5-of.the Safety Technical Specifications. 'In addition to the~ responsibilities specified in Safety Technical

Specifications, the Committees shall havaithe.following responsibilities concerning the environmental impact of the

' plant. - iA.

Plant' Review Committee'(PRC)'

l 11. Coordination of-environmental technical specification o 2 development with the safety. technical specifications to avoid ~ conflicts:and maintain consistency. 4 ~ 7 . - eg -

1 g i-2. Review proposed onsite tests and experiments and results thereof, when such tests have enviro = ental significance. . 3. Review proposed changes to the environmental technical i specifications. 4. . Review written procedures, as described in 5.5, and proposed changes thereto which affect the plant's environmental impace. 5. - Investigation of all reported instances of violations of environmental technical specifications. Where investigation ' indicates, evaluation and formulation of recommendations to prevent recurrence. 6. Review results of the environmental monitoring programs prior to their submittal in each semiannual Environmental Monitoring Report.- See Section 5.6.1. B.- Management Safety Review Committee (MSRC) 1. - Preparation of the proposed environmental technical specifications. i . Review proposed changes to the environmental technical 2.- specifications and the-evaluated impact of the change.. 3. . Review proposed changes ~or modifications to plant systems or equipment which would' affect the plant's environmental 4 impact and the evaluated impact of the changes.- 4. Conduct periodic audits of plant operations. 5. . Review all reported environmental specification violations. 1 ~ 5.4. Action to be Taken in Event of Violation of an Environmental Protection Limit.- 5.4.1 Remedial action as permitted by the technical specification shall be taken until the~ specification can be met. 5.4.2 . A violation of these-Technical Specifications shall-be reported 'immediately to the Plant Superintendent and at=a formal meeting. of the Plant Review Committee by the-Plant Chemical and Radiation-Supervisor or,-if unavailable, by the Assistant Superintendent of ( ' Technical Support; 4 3 - -- ) 7 r 9 e-se 4- -e ,--e -,e.- .w-. o r = we,

a. m,- 3-2,< I e i .R h 5.4.3 ~ The chairman of - the Plant Review Consmittee shall prepare a i detailed, evaluation report outlining the events leading to the violation along with suggestions to prevent or reduce the probability of recurrence. This report shall be completed within one week of the occurrence. The evaluation report will 'be distributed-to the' Plant Superintendent and to the Chairman of the Management Safety Review Consmittee. 5.5

Procedures 5.5.1 Detailed written procedures, including applicable check lists and instructions, will be prepared and adhered to for aU activities involved in carrying out the environmental technical specificaticus.'. Procedures will include sampling and analysis,.

instrument' calibration, and actions to be taken when limits are approached or exceeded. Testing frequency of associated l alarms will.be included. These frequencies will be determined l ~from experience or:from manufacturer's technical manuals. l 5.5.2 In addition to the procedures specified in Section 5.5.1, the i plant' Process Standards will include provisions to ensure the plant and all its systems and components are operated in compliance.with the environmental protection limits established in Section 2 of these environmental technical specifications. 5.5.3~ All procedures described above, and all changes thereto, will be. reviewed and approved by the Plant Review Commaittee prior to. implementation. The procedures will be reviewed periodically thereafter. Temporary changes to procedures'which do not change the intent of'the original procedure may.be made, provided such changes are approved by two members of the plant ' management staff. Such changes'will be documented. 5.6 Plant Reporting Requirements 5.6.1 Routine Renrts j l A. report on operating experience related to the envirennent l-protection limits (Section 2) and on environmental surveillance programs j(Section '3 and 4) for the previous six, months will be i . submitted as part of the Semiannual Operating Report within 60 days after January 1 and July 1 of each year. The first such ' period,will begin with the date of initial criticality. The i report will be a susmary of the results, with detailed. data sonly where necessary, and will' include an assessment of observed -impacts of the station's operation on the environment..In the-evsat that'some results'are not available.within the 60-day period, the report should be submitted, noting and explaining i ~ the reasons for the missing results. The. missing data'shall L be' submitted as'soon as possible in a supplementary report.- ] j ~ 44'.- i .. ~., + ~ ~ -

The report will include a-summary of the quantities of radioactive effluents released from the plant as outlined in USAEC Regulatory l Guide 1.21, with data summarized on a monthly basis following a standard format. l 7.f statistically significant variations of offsite environmental .l 3 radionuclide concentrations with time are observed, a comparison of these results with effluent releases shall be provided. l Individual samples or observations which show results greater than I the levels stated in the Reporting Requirements in Sections 3.0 and 4.0 herein shall be specially noted and discussed in the Report. Results of all radiological samples taken shall be summarized on a quarterly basis following a standard format for inclusion in the semiannual report. 5.6.2 Non-Routine Reports A. Radioactive Discharge i The reporting requirements for radioactive discharges are specified'in Section 2.6 of these specifications. B. Radiological Environmental Monitoring 1. If a measured level of radioactivity in " critical path-way environmental medium samples" indicates that the resultant annual dose to an individual from these levels could equal or exceed 8 times the design objective, a plan will be. submitted within one week advising the AEC of the proposed action to ensure the plant related annual j . doses will be within the design objective. 2. If samples of " critical pathway environmental media" collected over a calendar quarter show total levels of radioactivity that could result in accumulated plant related doses to an individual for that quarter of 1/2 the annual design objective, the results shall be reported.and a plan submitted and implemented within 30' days'to limit.~ conditions so that the annual dose to 4 an individual will not exceed' the design objective. C. Nonradfological- ~ In the event an environmental protection limit (Section 2) 'is exceeded, a report level (Sections 3 and 4) is reached, or 'an unusual event involving a significant environmental impact L t l -: .l

f:0 m._,, ~ _. a i 4 j occurs, a report will be made within 24 hours by telephone or telegraph to the Director of the Regional Regulatory Operations Office, followed by a written report within 10 days to the Director of the Regional Regulatory Operations Office -(cc to Director of Licensing). The written report and to the extent possible, the preliminary telephone and telegraph' report, will: (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 signif! cant changes made in procedures) taken to preclude repetition of the' occurrence and to prevent similar occurrences involving similar components or systems. 5.6.3 Changes 1. Unen a change to the plant design, to the plant operation, or to the procedures described in Section 5.5 is planned which would have a.significant adverse effect on the environment } or which involves an environmental matter or question nor pre- / viousi; reviewed ~and evaluated.by the AEC, a report on the change lwill be made to the AEC prior to implementation. The report will include a description and evaluation of the change tacluding a supporting benefit-cost analysis. 2. Changes or additions to permits and certificates required by Federal, State, local and regional authorities.for the pro-tection of the environment will be reported. When the required changes are submitted to the concerned agency for approval, they will also be submitted to the Deputy Director for ~ Reactor Projects, Directorate of Licensing, USAEC, for information. The submittal will include an evaluation of l the' environmental impact of the change. 3. Request'for changet in environmental technical specifications owill be submitted to the Deputy Director of Reactor Projects, Directorate of-Licensing, USAEC, for prior review and authorization. The request will include an evaluation of .the impact of the change, including a supporting benefit-cost ' analysis.- 5.7 , Records Retention ~5.7.1 1 Records and' logs relative to the following areas will be retained Lfor the: life of the plant: ) s - 46~-:

A. Records and drawing changes reflecting plant design modifications 'made to systems and equipment as described in Section 5.6.3. B. Records of environmental monitoring data. 5.7.2 All other records and logs relating to the environmental technical specifications will be retained for five years. 5.8 Special Requirements Table 5-1 lists the typical amounts of chemiccis that will be dis-charged from the. station. The list includes those chemicals which are purchased and used in plant processes, and B and Z, which are concentrated by the cooling towers from naturally occuEring impurities in raw water, and which have specific waste discharge limits. The quantities actually discharged will be determined on an (~. inventory basis as recorded in the warehouse chemical log book or from calculation of totaLdischarge water and chemical analysis of the affluent.. These quantities shall be-included in the Semiannual Operating Reports (Section 5.6.1) if they appreciably exceed those i in Table 5-1. ?N'

a-

.._ 47 _

~ ~~ a GENERAL MANAGER M a d 4 ASSISTANT l CEf!ER AL M, WAGER AND CHIEF En.'GINEER P MANAGER MANAGEMENT I ENGINEERING SAFETY REVIEW e' COMMITTEE s SUPERINTENDENT i y' RANCHO SECC 1 i PLANT REVIEW COMMITTEE i i-l l-FIGURE 5-1 l MANAGEMENT ORGANIZATION CHART l;

ENVIRON!1 ENTAL TECllNICAL SPECIFICATIONS RANCHO SECO UNIT 1 Oau SACRAMENTO MUNICIPAL UTILITY DISTRICT

.. h6

PLANT SUPERINTENDENT

J s

s TECHNICAL ADMINISTRATIVE ASSISTANT

STAFF P

J s s ASST. SUPT. ASST. SUPT. NUCLEAR PLANT MAINTENANCE TECHNICAL SUPERVISOR OPER ATIONS (SL) S RT

l A

' e SHIFT MAINTENANCE SUPERVISORS (SL) PERSONNEL /,,',,,,,,",',',',',, SR. CONTR OL s ~ 's . ROOM OPER ATORS (L) POWER PLANT / CHEMICAL. RADIATION INSTRUMENT CONTROL ENGINEE RS k SUPERVISOR a ENGINEER (NUCLEAR / MECHANICAL) /, CONTROL ROOM ~ OPE RATORS (LI CHEMISTRY. RADIATION INSTRUMENT CONTROL PERSONNEL PERSONNEL AUXILIARY ~~ OPERATORS SL. SENIOR AEC LICENSE L. AEC LICENSE EQUIPMENT

. ROUTINE REPORTING REQUIREMENTS

~ ATTENDANTS ON PERSONNEL CHANGES FIGURE 5-2 PLANT ORGANIZATION CH ART ANCHO SECO UNIT 1 ENVIRONMENTAL TECIINICAL SPECIFICATIONS l SACRAMENTO MUNICIPAL UTILITY DISTRICT .- p

TABLE 5-1 NON-RADIOACTIVE CHEMICALS AND ELEMENTS TYPICALLY RELEASED BY RANCHO SECO UNIT 1.IN THE EFFLUENT DISCHARCE Average ' Chemical'or-Amount Per. Annual Conc. . Element ~ Year-(1bs) (mg/1) Use and Frequency of Discharge L odium (Na) 1.45 x'105 S 39. Regenerant of ion exchanger resin.as sodium hydroxide. Discharged intermittently. , Sulfate (Sog) 1.6 x 106 431 Sulfuric acid injection into cooling tower water to reduce al.kalinity and regenerant of ion exchanger resin. 1 Discharged continuously I Ammonia'(NH ). .5.2 x 10 14 Regenerant of ion exchanger resin as ammonium hydroxide-4 3

g and pH adjustment for steam generator feedwater.

.i. Discharged intermittently. Chlorine (CE ) <750 <0.2 Biocide to remove aquatic growths in cooling water 2 systems. Injected to cooling towers at %200 lbs. per day. Mainly consumed prior to discharge. 4 Alum [A1 (30 )3] 4.0 x 10 1.7At Coagulant for water treatment system. Discharged 2 9 intermittently. Boron (B) %2 x 103 40.6 Cooling tower concentration of naturally occurring B in raw water. Continuously discharged. No release of B used in plant processes.: Zinc - (Zn) %1 x 103 %0.3 Cooling tower concentration of naturally occurring Za in raw water. Continuously discharged. .Hydrazine (N H ) Negligible Negligible Used for oxygen scavenging of secondary feedwater 24 system. Consumed in process'except during shutdown periods. {j -}}

ML19319E164

Text

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