ML19319D930

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ETS for Facility
ML19319D930
Person / Time
Site: Rancho Seco
Issue date: 10/31/1973
From:
SACRAMENTO MUNICIPAL UTILITY DISTRICT
To:
References
NUDOCS 8003270605
Download: ML19319D930 (43)
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Text

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t: "3"d n OPERATIIG LICEiSE fio. DRP-56 4 / at to - BNIIUSEITAL TECRICAL SECIFICATIfTiS FOR TrE PKlGiG SECO !!LCLEAR POIR STATIM li!IT 1 SACP#E4TO lE!ICIPAL LTILITY DISTRICT DOCKEl !i0. 5}312 DATEOFISSUANCE: OCTO?iR,1975 b?0DYD00l.TTcnppE,y

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, ;A.1 ? e 1.0 DEFIfilTIGIS 1.1 EnvlRONIGITAL IECHNICAL SPECIFICATION - Limitations, conditions and requirements whic:t are considered necessary for the protection of the environment and require appropriate action to be taken if exceeded. 1.2 LOSTPONER-A serious need for lost power is the condition which would result in voltage reductions or load shedding of the Districts or con-tractual customers. 1.3 NOT SPPLICASLE TO RANCHO SECO - Because of the unique feature of the Rancho Seco Plant, this is defined as not having an effect upon the environment to which these Technical Specifications apply. CRN][3definedastheStateofCaliforniaRegionalWaterQualityControl 1.4 Board, Central Valley Region Resolution - as stated within their order No. 71-176 dated January 22, 1971 and amended by their new interim Water Quality Control Plan for dissolved oxygan limits. 1.5 NOISE-The mechanical vibrations ~within the audible range as measured within the requirements set forth in the USASI American National Standard Specification for Gener.1 Purpose Sound Level Meters S1.4 (1971). 1.6 STATE OF CALIFORNIA DEPADTTENT OF UAER P= SOURCES CONTRACT - The Davis-Grunsky Act Grant Contract No. D-GGR28 between State of California and Sacramente Municipal Utility District of April 6, 1971, Exhibit B. 1.7 CONTINUOUSI#ONITORITG - Defined as the automatic analysis equipment that produces a permanent recording of the measured parameter or an increased manual sampling technique for obtaining the values of the measured para-meter 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.

1. 9 ENVIRONTE4TAL DEVIATION - An environnntal deviation is said to occur when-ever an environmental protection condition or report level-is exceeded, or whenever. in the opinion of the plant superintendent, an unusual event involving significant environmental impact has occurred.

1.10 DAILY - A time period within a 24-hour 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.. 4 j

n d' . l.12 - FORTMIGfrLY - A time period. covering two consecutive weeks spaced to occur 26 times a year. 1.13- - Ikyrn4_Y - A time period from the first to last day of a calendar month spaced to occur 12. times a year. _1.14

QUARTERLY - A tira period of three calendar months spaced to occur four times.a year.

1.15 SEM-NMUAL - A. time period from January 1 and July 1 covering the subse-quent six months. 4 r 6 M V T 4. k y-e-- T y -e -..,m,- ,,,--i, .rn-- y ete -- t7 - w-

f t [ 2.0 BMITIEffAL PFDTECTIQI CGlDITIUlS 2.1 Maximum Discharge Temperature Objective To comply-with the State of California Regional Water Quality Control -Board requirements. Specification The cooling water effluent temperature at the discharge structure shall not exceed 90* for a time period in excess of two hours. The station's generating capacity shall be limited, as necessary, to keep the discharge temperature from exceeding 90*F. If there is a serious need for the lost power, the licensee shall notify AEC/ DOL Division of Regulatory Operations Region V by telephone of intent to exceed the above limits. Monitoring Requirement-Plant water discharge temperature shall be continuously recorded et the discharge structure. An alarm will be provided in the Control Room to indicate the status of this specification which, if exceeded, will be decreased by increasing the dilution water flow rate. During periods when the ceasuring equip =ent is defective or under repair, representative data readings of the discharge water temperature shall be logged every 4 hours during water discharges using a handheld thermometer. Bases The 90*F effluent temperature has been selected by the CRWQCB as the maximum permitted for Rancho Seco. .r.. e,q rg E y,,.;> p.p,n,, 4,.,,.,1t.,.;.4 A Wa, s%, ,A., r;. t,.;gj; p.,d;,,pwg. e G

c 2.2 _GEMICAL Chlorine Objective To prevent discharging chlorine at levels intolerable to living organisms. Specification The effluent water shall contain total residual chlorine not to exceed 0.1 ppm. Monitoring Requirement Samples of the effluent water will be collected and analyzed on a weekly sch'edule. The sample will'be obtained from the outlet of the discharge structure during periods after chlorination. If there is no chlorination during the required sample period, the sample will be obtained the follow-ing period, etc. Bases Intermittent use of chlorine will be required for control of algae in the circulating water syste= and. vill result in periodic low residuals of chlorine in the effluent water. The chlorine levels that will be present in the circulating water system may.be slightly above the discharge limit. With the dilution, the chlorine levels will be reduced below the discharge limit. Wh .o 5 = f

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,s a 2.3 Suspended and Dissolved Solids objective To prevent discharging materials that would be detrimental to the environment surrounding the receiving water or be unusable for irri-gation. Specification A. The discharge shall not cause visible oil or grease slicks, scum or foam on the receiving waters. B. The discharge shall not cause fungus, slimes or other biological growths in the receiving waters or along the creek banks. C. The total dissolved solids concentration shall not exceed 800 mg/1. Monitoring Requirements A. The discharge water course up to unnamed creek will be inspected weekly for pollutants, oil, grease slicks, scum, foam or other bio- ~ logical growths. Records of each inspection will be documented indicating the individual, his findings and corrections taken for improvements. B. Plant water discharge conductivity shall be recorded continuously 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 a TDS value of 800 mg/1. If the setpoint is exceeded on the conductivity monitor, the discharge will be diverted to one of two retention basins for holdup or the discharge will be terminated. If the automatic diversion system is inoperable, the discharges will be manually channeled to the retention basins. Samples will be ob- -iA'*?<.44d.a 9&@ Stained and analyzed torcomply with -these specificatiops > p.rioret;cL.-@.4ySta release to the discharge structure. Bases All plant effluent water will be transferred through the waste water system either directly to the unnamed 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 800 mg/L total dissolved solids, placing the water in Class II for irrigation use. The combination of treatment, retention and dilution of the station -S-s v, ~

e 8-t s: P effluent vater, coupled with the continuous monitoring program, will . assure that effluent quality conforms with California standards and will permit safe disposal of the effluent to the public domain. gg,, e

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-4 0 _:2$ PH Objective Tc comply with the CKWQCB and to prevent discharging acidic or basic 11 61ds that woald be detrimental to the terrestialrenvironment cithin 9 6i d6ar the receiving waE5r~si;' - 2;22-#;- " 7 2'

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..c.::. Specification Plant effluent pH shall be maintained within the limits of 6.5 to 8.5. blfcharge-'outsidethisradge-kil'l-beallowe'donly-ki[th*CRNQCBapproval. 2 ...:........ m_. : ___ :. s__: 3. Monitoring Reauirement Plant water discharge pH shall be recorded continuously at the discharge hEfu6turel-in'51 arm will'be provid' ed;in'thi'ConFr51'Roohi h ~ wain' the# ; t 6piritor' of usciedihg 'the AccepEhbii;opAriting hind-b6EU' ed;6'.37ind'8.5. ~ e 7 2 2 7 It'th6 pH 11 hit *is exceeded [#bhE2dischaige kil1 be'asthmaEiciliy~ diverted Eb bas of tho're~inti5n-basins 2for'651du E6rsihatedf' If thi;astomai~c diversich p or the;diic'hArgE' hill be' *I;*2 t F ~ 1 sysied 1s;ihophiabihlor Ehe pH 56hlEbr fails;2 the*disch~arges Oill-be hanuhlly chahhelid Eo thi ritention ~ i Fisl6s'. Sadples vill'be'5btiihed and hna~lyzed t6'iompiy Uith this~l!2' " e

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Bases All plant effluent water will be transferred through the dilution su=p IIEhsr. 'diric. Ely. *i. b. Eh. i, be f ore -..iEnha..med d..ri.ik B_r tEEpoisilly to'8nd i 2 .~.o 300,000 e.l.. retention basins-.__ release to th~e creekd. ga The r=strictions re - e (stre~that-discharged vaste water dot cxteed ths pH lidits ef-6:5~to 8.5, plYcins'the%hthFsithin'etie'-hatiohai TEEhhichi'Enith;5aivihe%cahdasdi"

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2.5 Other Chemicals which' Affect Water Quality Objective To comply with the CRWQCB and to release water that is sufficiently pure and will support aquatic life within its receiving waters. Specification 1. The median MPN (most probable number) of coliform bacteria organisms in the domestic sewage discharge shall not exceed 23 per 100 mi, nor shall more than 10% of the samples exceed 500 per 100 mi. 2. The discharge shall not cause the concentration of dissolved oxygen in the receiving waters to be less than 5.0 mg/1. 3. The effluent water shall not contain dissolved elements in excess of 1.0 mg/L for boron and 0.3 mg/L for zinc. Monitoring Requirement Samples of the plant effluent water for oxygen analysis shail be obtained at the site boundary and analyzed weekly. These samples will give an indication of the quality of the ef fluent water from the plant and be representative of the overall plant operations. Samples of the ef fluent water for coliform bacteria, boron and zine analysis shall be collected and analyzed on a monthly schedule. The sample will be obtained from the outlet of the discharge structure during a typical release of the plant waste water. ,,. e, m i 4. -:.>. w a.. s v W M :r, % ' . =. *c m-n n :n :~ 'n

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Bases The State of California

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. 94%*ylvvh cv t.94tena + mer+ w. sysw M' **de ~ > 9 cwvmh.i-s 5 im,WRu weK-W r.&t 1. Less than 50 per 100 mt for water supply, drinking, culinary and food processing without treatment other than simple dis-infection and re= oval of naturally present impuritics. 2. Less than 2000 per 100 m1 when associated with domestic sewage for the use of same purpose of (1) above but with treatment equal to coagulation, sedimentation, filteration, disinfection and any additional treatment necessary for removing naturally present impurities. 3. Less than 240 per 100 mi for bathing, swimming and recreation. l l. l \\ j

4. Less than 70 per 100 mi for growth and propagation of fish, shellfish and other aquatic life. The plant effluent limit is sufficiently low to assure that the State of California recom=endations are met for all possible usages. Dissolved oxygen in domestic water supplies, irrigation water and stock watering is not considered to be of appreciable significance except for use as an indicator of pollution by organic wastes. The =inimum oxygen limit and maximum coliform count assures minimum organic waste content of the plant effluent. 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 at least 16 hours of any 24-hour period. It may be less than 5 mg per liter for a perica 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 liter 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 zine 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 belew these limits. These elements may be present in the plant, but are ma' inly derived from-the concentrating mechanisms of the cooling towers and in general are not of plant origin. .v.w.. wM..'m t.a e.n.. >r: n..~ ri.v.~>.e' ru.mw=*.<+$ G.?.:r--w- -.c. wren M: r:- e - W -A The coliform bacteria organisms will be dependent on the operation.of the on-site package sewage treatment plant that is designed to handle and process all plant originated sewage. Accumulated sludge will be hauled off site and disposed of by a licensed contractor. .A correlation of coli-i p.,3%gigbs_4 form. MEN with free.-available chlorine may-bessade and*-chlorine measurements #- may then be made in lieu of XPN tests. l McKee, J. E. and Wolf, H. W., Water Quality Criteria 2nd Edision, California State Water Ouality Control Board, Publication No. 3-A, (1963). Anon., Aquatic Life Water Quality Criteria, First Progress Report, Ohio River Vallev Water Sanitation Commission, Aquatic Life Advisory Committee, Sewage & Industrial _ Wastes'27, 321 (1955) _9_ g = M*

2.6 Radioactive Discharge '2.6.1 Liquid Effluents Objective To assure that radioactive liquid effluents of plant origin are not released to the environment without proper authorization and to assure that liquid effluent releases are kept as J,w as practicable, and in any event, .any radioactive material released is within the limits of 10 CFR 20. Specification 1. During normal design plant operating conditions, there will 6e no radioactive liquid effluent discharges of plant origin. 2. Should operating conditions require discharge of radioactive liquids, a signed permit will be obtained from the Plant Superintendent or his designated representative authorizing the maximum quantity of radioactivity that may be released. 3. The release rate of radioactive liquid effluents shall be such l that the concentration of radionuclides in the offsite liquid releases does not exceed the limits of 20.106 of 10 CFR 20, Appendix B, for unrestricted areas during release. Monitoring Requirement 1. Prior to any liquid release from the regenerant holdup tank or the retention basins, two independent sample, af the wastes shall be analyzed to determine gross beta, and/or gamma isotopic activity - -, w..ew,uw-sc.co m Ed fat rat foris"." ' "*"~"" * -6 '"" * *" * "^~" r* 2.- All radioactive liquid effluents shall be continuously monitored for flow and gross radioactivity concentration during release.

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sample within two hours of the termination of discharge of radicactive liquid. Bases There will be no radioactive discharge of liquid effluents during normal operation of the reactor. The process system designed to accomplish this has filtration, ion exchange, tank storage capacity, evaporating and degas-sification capability. The method employed for processing the liquid radio-active vastes for re-use incorporates the capability to process the reactor coolant re-using the evaporator distillate in the reactor system and re-using the boric acid from the evaporator. discharge in the reactor control system. i l' ( Additionally, the miscellaneous wastes are processed in the same manner and i _lo_ t l l l ~

2.6.2 Caseous Effluents Obj ective To assure that radioactive gaseous effluents of plant origin are not releaned to the environment without proper authorization, to assure that gaseous effluent releases are kept as low as practicable. Specification Radioactive gaseous effluents shall be released only under controlled and monitored conditions and at rates to limit concentration at the site boundary to those specified in 10 CFR 20 Appendix B Column 1, Table II, for unrestricted areas, and to take corrective action prior to exceeding the limits of proposed 10 CFR 50 Appendix I and Regulatory Guide 1.42. Monitoring Requirements 1. Prior to release, the contents of the radioactive waste gas decay tank shall be analyzed to determine isotopic activity concentrations. 2. During each waste gas decay tank release, the unit vent gross activity, particulate and iodine monitor shall be operable. Whenever either of these monitors is inoperable, appropriate grab samples shall be taken and analyzed before, taring and after any release and at least daily. 3. All discharges from the waste gas decay tank system shall be through a particulate, REPA and charcoal filter. t.,,Q,,,~. % e :.4-a When the. filter system is inoperable, waste gas decay tan'k ca: 4 gaseous wastes shall be held up for the minimum period of 45 days prior to release. Every reasonable effort shall be made to return inoperable filters to the operable condition before re-leases to the environment are made. s -,Wm.frg,ny.9<pwrm-+:.v.hWa.:eim uw-e#2*^:# 45 MW94itM*4AWW## 6 -*4 5.'" Plant exhaust high level trip or loss of plant exhaust fans shall autom.scically terminate discharge. 6. Purging of the Reactor Building shall be governed by the follow-ing conditions: Reactor Building purge shall be through the high efficiency a. particulate filters and charcoal filters until the activity concentration inside the Reactor Building is below the occu-pational limit. b. Whenever irradiated fuel is being handled or any objects are. e ,~ -m-

the distillate retained for re-use. Bottoms are prepared for offsite shipment. Uith this system capability, and all postulated operating conditions, it is considered highly unlikely that any radioactive efflu-ents of plant origin will be discharged. Should abnormal conditions arise, SMUD is permitted the flexibility of operation compatible with considerations of health and safety, to assure that the public is provided a dependable source of power. During unusual operating conditions, the Plant Superintendent or designee will exert his best efforts to keep all effluent discharges as low as practicable. Under no circumstances will radioactive liquid effluents be discharged without the consent of the Plant Superintendent. Even under abnormal conditions which might require discharge of radioactive liquid, the limits of 10 CFR 20 and Resolution 71-176 adopted for Rancho Seco by the CRWQCB will still be maintained. ~ This monitoring program is designed to detect the quantity and kind of l radioactivity to assure that there will be no inadvertant releases to the environment. The program will provide sufficient information of all discharges for analysis, evaluation, and approval prior to any radioactive discharge. Controls will be' administered to prevent exceeding the dis-charge specification and in all cases to keep the discharges as low as practicable. ). g S = f [' dgg g 8 9% M16MNdWWW78ML Mh'$@hidGPt4&ibA%52:iE%?-42riMwA45,111,g WJ7343 .r. 4g /a 9 4 V- ,w

4 7. The release rate shall be such that the annual average con-centration of radionuclides in the discharge gas does nrt exceed the limits specified in 10 CFR 20 for unrestricted areas based on the annual average dispersion factor. 8. The maximum activity to be contained in one waste gas tank shall not exceed 5708/E curies. E will be assumed to be the average energy of the noble gases in the reactor coolant system. Bases Radioactive gases will be those resulting from the fission process and neutron activation. These gases will be collected in the vaste gas tanks from various components associated with the reactor plant. Gaseous wastes ~ in the Reactor Building atmosphere are released by purging to the unit i vent. Any gaseous wastes in the' Auxiliary Building atmosphere will be released through the ventilation system to the e it vent which is monitored. The size of the vaste gas system and holdup capacity has been conservatively designed and gaseous effluents will be significantly below 10 CFR 20, Ap-pendix B, Table II, Column 1. By using the designed waste handling systems and considering even abnormal conditions, the maximum radioactivity that is expected to be discharged for a one-year period should be less than 1 percent of the annual integrated dose limit in 10 CFR 20 at the site exclusion area boundary (2100 feet).

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9 3.0 ESIGl EXUES AT OoEPATIllG PP/LTIES 3.1 Intake System Plant makeup water will be obtained from the Folsom South Canal. During Rancho Seco Unit 1 oper..cion, a maximum of 32 cfs will be used as makeup water. The location of the site is 3.5 miles east of the canal and water is pumped the distance through a 66-inch underground concrete pipe. A storage reservoir is also available for standby purposes in the unlikely event of an outage of the canal. The reservcir normally will have a surface area of 165 acres, a useful storage capacity of 2,700 acre-feet and a shoreline of about 4 miles. Surface runoff and pumping from the canal vill maintain an essentially constant reservoir volume. Occasional minor drawdown may be required in coordination with an outage of the canal. When this occurs, water will be pumped to the reservoir as replacement when the Folsom South Canal is back in service. A separate pipe system provides for circulation of water through the reservoir by withdrawing 2000 gpm near the dam and delivering it to an auxiliary inlet near the upper end of the reservoir. A diagram of the canal intake structure is shown in Figure 3-1. Water will pass first through a trash rack comprised of vertical bars 5/8 inch wide on 2 inch centers, then through traveling screens with 1/8 inch openings. Velocity at the trash racks and the traveling screens will be about 0.2 fps. The screens will be backwashed at a set differential pres-sure of 12 inches H O differential. 2 A diagram of the reservoir intat-outlet structure is shown in Figure 3-2. The structure will s? ve also as an outlet to the reservoir when water is pumped from the canal to the reservoir. The structure is equipped with a trash rack that hcs 6 inch by 13 inch openings and with stationary screens 4 -e- .m...+,vathat have-3/8" inch openings.~ "Duringmormal "operatlons-when~the reservoir --> is recirculating about 2000 gpm for aeration, intake velocities will be about 0.1 fps at the trash rack and about 0.35 fps at the screens.' When makeup water is supplied to the plant, intake velocities will be about 0.9 fps at the trash rack and about 3.2 fps at the, screens. There will +,+4+"@A98tta9(g h mo41ocide tteatmant tof.%he intakeseructuree>-atsthere=== head reservoir..a;w e 1

4 3.2 Discharge System Normally, between 800 and 1000 gpm of plant effluent with chemical impurities will be discharged o the unnamed creek. Very little, if any, of this effluent will reach t Hadselville Creek due to the irrigation use of the effluent; however, the water may reach the Hadselville Creek and Consumnes River in the Winter. During the Su=ner, Rancho Seco may have to add up to 3,200 gpm of Folsom South Canal water to dilute the plant effluent so that the discharge temperature will not exceed 90*F. A diagram of the plant discharge structure is shown in Figure 3-3. The maximum discharge velocity vill be 2.6 ft/sec. at the exit with a total flow of 4,000 gpm. The average discharge velocity will be 0.66 ft/sec. at the 1,000 gpm discharge flow rate. 3.3 Chemical Usage Table 3-1 lists the typical amounts of chemicals that will be discharged from the plant. These quantities will be determined on an inventory basis as recorded in the warehouse chemical log book or from calculation of total discharge water and chemical analysis of the effluent. Consumption quanti-ties of chemicals shall be reported semi-annually to the AEC. 3.4 Land Management During site preparation approximately 100 a'res of ground were stripped c and approximately 300,000 cubic yards of excavation completed. Spoil has been distributed as fill on the property. Erosion has not been and is not contemplated to be'a problem. The downstream face of the reservoir dam has been planted with grass and the complement of the site will be replenished with grcsa. All roads and parkJng areas are paved w o e and final grading, roadways and-landscaping will be completed including J"****' architectural grading and planting in appropriate areas. Over 300 trees, including White Alder, European Hackberry, Desert Gum, Moraine Ash, Crepe Myrtle, Italian Stone Pine, Japanese Black Pine, Coast g,gg-eeBadwood Redbox Gum,and-Drake Evugreen>E14YeitplantattedfAcint*t6:'thWMW Administration Building, parking lot and entrance roadway where the visit-ing personnel will nave maximum visual exposure. In addition, where trees are not feasible, numerous shrubs including Galden Euonymus, Gold Coast Juniper, Springtime Raphiolepsis and Star Jasmine are planted. The remain-ing groundcover_ is ice plant and Dwarf Periwinkle. This terrestrial plantage will be maintained and cultivated throughout the life of the station. The use of herbicides to protect the environmental aspects of the plant will be reviewed with the California Department of Agriculture prior to use. Approximately 60 acres are taken for roadways and 433 acres for a recre-ational area, including the reservoir. The recreational facilities will be operated by the County Department of Parks and Recreation and will pro-vide for bathing, picnicking, boating and fishing activities. The reservoir will be developed and maintained as a warm water fishery. Reservoir development will likely increase the waterfowl population of the area; the development of riparian trees and shrubs along new water courses will provide food and cover for game birds and song birds that otherwise would not occupy the Site area. During the initial year of operation, the recre-ational facilities are expected to obtain a visitor icvel of 75,000 visitor days and by the year 1980 over 100,000 annually. That part of the Site not actually used for Station facilities and not dedicated to recreational use will continue to be used for range land. In addition, water released from the facility probably will be used to upgrade some of the onsite and 3 offsite range land to' irrigated pastures, increasing herbage yields and prolonging the grar.ing season. The exhibit center, located east of the Station and the associated visitors overview, permits a view of the Station. A

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g x ? 'l A TABLE 3-1 4 d }{0N-RADIDAC IVE CHEMICALS AND ELEMENTS RELEASED J f ( $g BY PI,. ANT IN Tile EFFLUENT DISCIIARGE t: .s 5 .h. 1 Chemical or Amount Per h AveraghConc. Element Year (Ibs) k (mg/1j Use and Frequency of Discharge 9': 4 Sodium (Na) .1.58 x 10 h 1} Regenerant of ion exchanger resin as sodium hydroxide, Ij. )); Discharged continuously. ~*r 6 ? 37); Sulfuric acid injection into cooling tower water to Sulfate (SO ) 1.06 x 10 j r 4 k / reduce alkalinity and regenerant of ion exchanger. tI resin. Discharged continuously. 4 c l. Ammonia (NII ) 1.01 x 10 V. 1 Regenerant of ion exchanger resin as ammonium hydroxe 3 3. E and pil adjustment for steam generator feedwater. 8 f Discharged continuously. 3 Chlorine (C1 ) 7.8 x 10 <0.3 Biocide to remove aquatic growths in cooling water 2 5 fa systems. Discharged 20 minutes duration, three times f a day. Alqa [A1 (SO )3] 9.0 x 1 Coagulant for water treatment system. Discharged 10. 2 4 continuously. ? f G Boron (B) 45 4 <0. [ Leak of primary coolant into steam generator at a rate "g, '} of 20 gpd with average boron concentration of 700 ppm b

boron, Normally not discharged.

y f 11thium (L1) <1 .,) 'y Not Det'ectable Leak of primary coolant into steam generator at a rate 4 M of 20 gpd with average lithium concent:ation of 1.7 ppm .,t, g ,5 lithium. Normally not discharged. 4 Hydrazine(N H ) Negligib e Negli ible Used for oxygen scavenging of secondary feedwater 24 i sys t.cm. Discharged continuously. h .{ i

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4.0 BNIEiEffAL SbMElllRKE PPGPAiB 4.1 Ecological Surveillance 4.1.1 Erosion Objective To prevent effluent water from Rancho Seco causing erosion and to prevent abnormal degradation of soil banks surrounding the Rancho Seco effluent stream. Specification Visual inspection of the water course shall b'e made quarterly. Prior to initial plant operation, a baseline inspection will be performed and 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 i f Abnormal erosion above the specification limits that is not or cannot be corrected shall be reported as required in Section 5.6. 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. 4.1.2A Drift Contaminants .r;ra c.w myn v,u..uwm.y -s.+w.s.Mr~ %. . w, .rs. ~..;e w.,. %... .:.a.n ... n.W a,. a Objective The objective of monitoring cooling tower drift contaminants is to deter-5 mine and estimate deposition of entrained chemicals discharged as drift wwgg gMd,py,ticulges. in. some offsite. regions.gw... ;,-WMNdfW.W." MWe:,berQU Specificatien a The sulfate content in soil shall be monitored annually from three sampl-ing points located symmetrically 0.25 miles from the cooling towers. The data on leachable sulfate in soil shall be used to determine the significance of drif t contaminants as addition to the existing sulfate content level in soil Reporting Requirement If the sulfate content in soil exceeds 1500 ppm as sulfate, a report will. -r

d ~ be made to the AEC as per specification 5.6. Bases .The most predominant dissolved ion in the cooling water will be sulfate ~(430 ppm Soq expected) due to the sulfuric acid injection into the cool-ing water to reduce alkalinity. ' Sample locations will be selected af ter drift rain patterns have been observed from cooling tower operation. 4.1.2B Effluent Contaminants Objective-The objective of monitoring plant effluent contaminants is to determine and estimate deposition of chenicals discharged and e : rained on offsite agricultural regions. Specification The sulfate content in soil shall be monitored annually from three sampl-ing points located. downstream in agricultural areas where plant effluent is used for irrigytion. The data on leachable sulfate in soil shall be used to determine the significance of effluent contaminants as additions to existing sulfate levels in irrigated pastures. Reporting Requirencnt If the sulfate content in soil exceeds ppm as sulfate, a report will be made to the AEC as per specification 5.6. Bases 2.m.wc:n.-sw en.s.. ww m ws: w.>.,.. Aw e.n.< m~..m.-w we.s ...*+.~.a..~. - i::. The most predominant dissolved ion in the cooling water will be sulfate (430 ppm S0g expected) due to sulfuric acid injection into the cooling water to reduce alkalinity. Samp2e locations will be selected at three points on agricultural land downstream of the plant where high usage is v,ywigspgr.44sede of;the effluenc. ~.. ' 4W ;pyMyy.pph:3W Hwesw g..swt.Aspicat,,.paM;c.. t 4 3 .; : 4.1.3 Noise. .1

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.v? .t 4-n., -:- e n :) % Objective 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. Specification A. 'During the initial startup and semi-annually, noise level measurements shall be performed at the plant periphery at 200 yard intervals.. 4 B. Records shall be maintained for all noise measurements and documented in a special log book specifying noise level, location, instrumenta-tion used and personnel making the measurements. Peport 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 wichin normally acceptable NC-40 curve for noise criteria as defined in Section 1. Sound levels in excess of NC-40 curve shall be reported as required in Section 5.6. Bases A typical power plant is a complex source of noise, mak' g operational analysis of anticipated noise levels difficult and of 11ttle value. Prime sources of noise at the Rancho Seco plant are expected to be the high speed turbine driven feed pumps, the transformers, and,. infrequently, operation of the safety relief valves. From the standpoint of the plant operators, plant noise levels will be kept within 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 plante (a far greater source of noise than a nuclear unit) indicates that at the site boundary, the sound pressure level attributable to plant operations at normal conditions of operations and weather is expected to be comparable 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 only inoffensive low octave rumble apparent at night. ....... u. w ~,..- ....c. . mn. n. se s.a - a ... - >. w. --... w., + There is no real criteria to determine noise. Sint noise is a relative term, the 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 corrective actions. 40E*pprg { W48Ps@@)i#fF-WtMr#Eie:i4 W9&092w..:.W6fM'9MS-@MpW-n., ..r ...~ Objective To record the fogging patterns that are associated with the cooling towers and to plot the extent of the cooling tower plume for comparison with design characteristics. 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 obsetved. Appropriate action will be initiated to warn motorists of possible Ang cover at locations east and wept of the plant. 8 b

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 of these specifications. Bases There is little that can be done to prevent infrequent plume intersection 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 transportarica. The effects are discussed at length in Appendix 3C of the Rancho Seco Environmental Report and s'tated as " negligible" in the Final Environmental Statement.. 23.a i

I 4.2 Radiological Environmental Monitoring Objective To obtain a representative sample of the fish in the site reservoir and to verify that Rancho Seco operations has not altered the radiological environment by determining no significant deviations between pre-operational and operational monitoring measurements. Specification Two varieties of edible fish, one top and one bottom feeders, in the site reservoir are collected as available. Sarples from the site are collected quarterig). The edible portions of the fisa are analyzed for gross beta 4 (less K and Srso, Samples shall be collected as specified in Table 4.1. Reporting Recuirement The AEC will be notified according to Section 5.6 if the gross beta activity exceeds 54 nanocuries/Kg or if the Srso level exceeds 9.2 nano-curies /Kg. 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 environmental radi,ological monitoring yyggram establish d,in.the.. Rancho.Sqco Final 9 .,..~._4 ..~ safety' Analysis Report. ,....r 4.2.2 Algae and Other Aquatic Plants ,. % % pa,q; p p-u~z., " m*W2.~6S;W CW+%W *h%*'*@W*EM* "%MW'&'WW h To obtain a representative sample of the algae in the Rancho Seco effluent-Y ' T - and to verify that Rancho Seco operations has not altered the radiological environment by determining no signi fictat deviations between pre-operational and operational monitoring measuruaeucs. Specification Algae samples shall be obtained when available from the mixed plant efflu-eut at the site boundary. A pint sample shall be collected quarterly and analyzed for gross beta (less K40), Sr90 and gamma scan. Samples shall be collected as specified in Table 4.1. Reporting Requirement The AEC will be notified according to Section 5.6 if the gross beta activity exceeds 74 nanocuries/Kg or the Sr90 level exceeds 0.68 nano-curies /Kg. Bases 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 continually. 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. 4.2.3 Surface Water Objective To obtain a Tepresentative sample of waters within the Rancho Seco en-vironment and to verify that Rancho Seco operations has not altered the radiological environment by deter =ining no sicnificant deviations between pre-operational and operational monitering ceasurements. Specification Surface water samples are collected from the Camanche Reservoir, site reservoir, Folsom Canal and a site drinking fountain. The Camanche .,.m ,,,Jaservoir,. a. maj or source af.drw=g water for Ahe San Francisco-Say -:- + m. c Area, is in the potential fallout pattern when winds originate from the northwest. All sauples are collected on a monthly basis, and a portion is filtered and the filtrate and solids are analyzed separately for gross beta activities; a portion is analyzed for tritiu=; and samples are f.emAWW-eM. analyzed;, by.. gamma.,spe c.roscopy3 whe,n gross betgastivity.. isdive times.,y. #., gyp-v normal. 3 >. nWQ.o?..d ry ff water samples are collecced downstream of the junction of the.. m' ? + ? .% MN s.-: a"Wra a . : y 1 * ~

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Runo w* plant effluent and the area runoff water. Samples are collected foxt-nightly and analyzed. A portion of the sample is filtered. The filtrates and solids are analyzed separately for gross beta-gamma. A gamma spectrum analysis is also performed on the filtrates and solids. A tritium analysis is performed on a portion of the total sample. Samples shall be collected from surface and runoff waters as specified in Table 4-1. Reporting Requirement The AEC will be notified according to Section 5.6 if the gross beta i - exceeds 10 picccuries/ liter. excluding tritium or the tritium level ex-coeds 200 picoeuries/ liter. t 1 \\ $$E' ~

e : 9 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 environmental radiological monitoring program established in the Rancho Seco Final Safety Analysis Report. 4.2.4 Sediment Objective To obtain a representative sample of the sediment at the site reservoir and plant effluent point. To verify that Rancho Seco operations has not altered the radiological environment by determining,no significant deviations between pre-operational. and operational monitoring measurements. Specification The mud and sile samples are collected at the plant effluent downstream of the junction of the plant effluent and area runoff water, and in the site reservoir at a quiescent location. One-pint samples of mud and silt are collected quarterly taking the top 3 inch of material 2 feet out from the shoreline. The mud and silt samples are analyzed for g: css beta. Samples shall be collected as specified in Table 4-1. Reporting Requiremenc The AEC will be notified according to Section 5.6 if the gross beta activity exceeds 160 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 environmental radiological monitoring program established in the Rancho Seco Final Safety Analysis Report. ~_

4.2.5 Milk Objective To obtain a representative sample of milk 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 operational monitoring _ measurements. Specification Commercial dairies within the collection area are located 10 miles west of the site, 7 miles northwest of the site and 9 miles southwest of the site. Milk samples are collected fortnightly. Each milk sample is analyzed for gross beta (less K4 0), and I131 An' additional sample will be obtained from a " family cow" near the site and analyzed for gross S (less K40) and 1131 Samples shall be collected as specified in Table 4-1 and analyzed within 8 days of sampling. The analysis' procedure for I131 shall have a sensitivity of 0.5 picocuries/ liter with an error less than + 25% at a confidence. Reporting Recuirement The AEC will be notified according to Section 5.6 if the gross beta activity exceeds 8 nanocuries/ liter or if the Il31 sample exceeds 19 pico-curies / liter. Bases-There are no private or family cows located near the site on. pastures irrigated with water from Unnamed Creek. 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 environmental radiological monitoring program established in the Rancho Seco Final Safety Analysis Report. 4.2.6 -Rabbits-Objective 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. i j l

i a Specification s.wsc.4 s.-t Two adult rabbits are obtained from d' "--^at areas of the site. The rabbits are collected quarterly when available. Rabbit femurs are analyzed for Srso40) rabbit thyroids for I131, and the edible flesh for gross beta (less K Samples shall be collected as specified in Table 4-1. .a. Reporting Requirement The AEC will be notified according to Section 5.6 if the Sr90 activity exceeds 70 picocuries/gm Calcium or the 1131 activity exceeds 26 pico-curies /gm or if the gross beta exceeds 10 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 environmental radiological. monitoring program established in the Rancho Seco Final Safety Analysis Report. 4.2.7 Flora Objective To obtain a representative sample of land vegetation 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 devi-ations between pre-operational and operational monitoring measurements.. Specification Samples of edible vegetation, intended for human consumption, are collected at four sites within fifteen air miles of the reactor. The locations are Clay, Ione, C,lements, and Sloughhouse. Edible vegetation for cows is 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 are ' collected from each of the above site ~ each year as they become available. Part of-the collection is made in tue spring (i.e... May and June) and part in the summer - and early fall (i.e., July, August,-September). Samples of animal-edible vegetation are collected .aonthly.from field vegetation eaten by the dairy cows. Twonilograms are collected at each location for each species of sample. All samples are analyzed for gross beta, less K40 Sr90 is determined in cow foodstuffs so.that. milk-vegetation balances can be determined. i

b e Samples shall be collected as specified in Table 4-1. Reporting Requirement The AEC will be notified according to Section 5.6 if the gross beta 90 activity exceeds 60 nanocuries/Kg or if the Sr level exceeds 1.0 nano-curies /Kg. o 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 environmental radiological monitoring program hstablished in the Rancho Seco Final Safety Analysis Report. 4.2.8 Soil Objective To obtain a representative sample of soil on the site perimeter and to verify that Rancho Seco operations has not altered the radiological en-vironment by determining no significant deviations between pre-operational and operational monitoring measurements. Specification A pint of top soil (i.e., top 1 inch) is collected at five locations on the perimeter of the site (N, E, W, SE, and SW). Samples are collected semiannually from each location. The samples will be analyzed for. gross beta. Samples shall be collected as specified in Table 4-1. ~ Reporting Requirement The AEC will be notified according to Section 5.6 if the gross beta activity exceeds 100 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 environmental radiological monitoring program established in the Rancho Seco Final Safety Analysis Report. e q-4'

~. 4.2.9 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 operations has not altered the radiological environment by determining no significant deviations between pre-operational and operational monitoring measure-ments. Specification Well water samples are collected from the on-site well, the reservoir well one quarter mile east of the restricted area, the Clay Station cattle feedlot 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. The site well samples provide information on natural radioactivity in the waters as they reach the site. The~other three locations provide veri-fication that. plant effluents are not affecting local water supplies. The samples are collected quarterly from each water s6urce. Gross beta and tritium analyses are performed on the samples. Samples shall be collected as specified in Table 4-1. Reporting Requirement The AEC will be notified according to Section 5.6 if the gross beta -activity exceeds 15 picocuries/ liter excluding tritium or the tritium activity exceeds 200 picoeuries/ liter. Bases Samples obtained and analyzed from the above locations will verify that Rancho Seco-has not altered the radiolo H,m Wy!.:. T-tede. vTcTnity of the ' plant. '"~'"~F

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z e s. 'This specification is a continuation of the pre-operational radiological monitoring program established in the~ Rancho Seco Final Safety Analysis Report. .4.2.10 Airborne Particulate and Iodine Obj ective To obtain a representative sample of the air particulates and gaseous radioiodine at locations surrounding the plant and to verify that Rancho ~Seco operations has:not altered the radiological environment by determin-ing no significant deviations between pre-operational and operational . monitoring measurements. -3 0-

4 Specification Samples are collected from eight stations, whose locations are selected on the basis of available meteorological data and population concentrations. Weekly samples are collected at each site. Continuous air sampling char-331 coal cartridges and filter papers are analyzed for 1 and gross beta, respectively, by direct counting. A gn=ma spectrum analysis is performed on quarterly composites of the filter papers from each station, while a gross alpha analysis is performed quarterly on an ashed composite sample from each station. Samples shall be collected as specified in Table 4-1. Reporting Requirement 131 exceeds 8.0 The AEC will be notified according to Section 5.6 if the 1 3 3 picoeurie/m gross beta activity exceeds 2.0 picoeuries/m, or the gross 3 alpha exceed 10 femto Ci/m. Bases Samples obtained and analyzed from the above locations will verify that Rancho Seco has not altered the radiological environment through airborne processes. This specification is a continuation of the pre-operational environmental radiological monitoring program established in the Rancho Seco Fin'al Safety Analysis Report. 4.2.11 Direct Radiation .Obiective -

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The TLD badges are installed at eight on-site and eleven off-site locations to measure integrated background radiation levels. The locations have been selected based on available meteorological data, prevailing wind direction, and population concentration. Samples shall be collected as specified in Table 4-1. Reporting Requirement The AEC will be notified according to Section 5.6 if the TLD radiation levels exceed 10 mr/ quarter above natural background. ~. -ce e

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 on-site badges are placed to give an indication of direct radiation from the plant. The eleven off-site 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 environmental radiological monitoring program established in the Rancho Seco Final Safety Analysis Report. 4.2.12 Reservoir Drawdown Ob[ective To comply with the District's contract with the State of California Department of Water Resources Contract and to provide sufficient water to properly utilize the recreational resources at the reservoir and to provide notice if the limits are to be exceeded. Specification The reservoir level shall be maintained as nearly 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 reservoir may be drawn to an elevation not less than

w. wewe e ; v 237 feet on veekdays except n'ational or state holidays between
  • April 1 and October 31 each year.

2. Between November 1 and March 31 each year, the reservoir may be operated so that the pool elevation is not less than 237 m.gw.6&cW@f.%.feetp +':"fM* 4WP %? .**w ' *'nt@r?% %:+' W!A 4.$@W!MP s 'J 3I To meeti a physical need for tiate'r at Rancho' Sec'o whic.h cannot +. iv, j 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 other purpose only with the prior written consent of the State. Monitoring Requirement A visual elevation monitor calibrated to read reservoir level shall be i installed in the Control Room. The level shall be recorded and logged daily. When the visual monitor is inoperable, a direct reading shall l be obtained and recorded from the reservoir level indicator on the in-let-outlet tower.

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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 feet will not affect the recreational' facilities nor endanger any aquatic species. At 237 feet, the recreational facilities are decreased 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. 4 f i <$-v.n:,:. w w w w w..,.n % a. ,,c.,,....m.,...g. .f,.,.. ., w.,, .,.3,_ 4 Je,*4%%(m4$h.Wer-cN;w.%w-3::i.5. %A.3 ;w.a.4.Gftm., tnrfgoex v.e:..;fgpo. o.-aq,2,. '..s .. Qts,:.:. ;.~ ,9 a. . :n s. :,.. ..e. :

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&-- ?"~5' V . _.~ s yf ~" .. \\; & Y.' f V" ,. j..: ;,'%. '..,','~ % ~r:nal&.'y.cf. /,4. --..,.:,./ '. c., .. m ,sn ----...+,>y(* x L.. .a:::.'h.-. p-~.' s > FIGURE 4-1 SAMPLE COLLECTION RANCHO SECO UNIT 1 LOCATION STATIONS - TECHNICAL SPECIFICATIONS. ENVIRONMENTAL O p. ,; ~ O SACRA.*AENTO MUNICIPAL UTILITY D! STRICT,'

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5.0 A51IWISTIMTI\\E OLTf0LS 5.1 Responsibility A. The Nuclear Plant Superintendent is responsible for the operation of the facility and to assure that the facility operates within the limits set forth in the environmental technical specifications. B. In all matters pertaining to nuclear operation of the facility and to the environmen'tal technical specifications, the Plant Superin-tendent shall report to, and consult with, the Chief Engineer and Assistant General Manager. C. The Plant Chemical and Radiation Supervisor is responsible for main-taining the environmental nonitoring program. There will be a semi-annual audit of specific phases of the program by the Quality Assurance Group which will report their findings directly to the Assistant General Manager and Chief Engineer. All audits' results will be., recorded in the records of the Management Safety Review Committee. 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 Chemical Radiation Supervisor through the Assistant Superintendent of Technical Support to the Plant Superin-tendent. The Technical Assistant remains as an indepe,ndent review and audit authority to monitor compliance with these Technical Specifications. 5.3 Review ~4u ww..rc s em-m >.. and Audit m. wm..% c.w.i m :,m :,ce.,0.ms....# m.f 3.c #.g,, Committees for review and audit of plant operation are described in Section 6.5 of the Rancho Seco Technical Specifications. En addition to the responsibilities specified in Rancho Seco Technical ' **"*Y3W'EI'*'3pecificatiohi',' th~e'* Commit' tees sNall hade' t'he"f511owing 'res'p'en'aibili'tiEi4'N 'WJ .;..;., concerning the environmental impact,of the, plant; ,3 A. Plant Review Committee (PRC) 1. Coordination of environmental technical specification develop-ment with the safety technical specifications to avoid conflicts and maintain consistency. 2. Review proposed on-site tests and exp'eriments and results thereof, when such tests have environmental significance.

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-3. Review proposed changes to the environmental technical specifications. 4. Review' written procedures, as described in 5.5, and proposed changes thereto which affect the plant's environmental impact. 5. Investigation of all reported instances of violations of en-vironmental technical specifications. Where investigation indi-cates, evaluation and formulation of recommendations to prevent recurrence. 6. Review results of'the environmental monitoring programs prior to their submittal in each semi-annual Environmental Monitoring Report. See Section 5.6.1. B. Management Safety Review Committee (MSRC) 1. Treparation of the' proposed environmental technical specifications. 2. Review proposed changes to the environmental technical specifi-cations and the evaluated impact of the change. 3. Review proposed changes or modificaticns to plant systems or equipment which would affect the plant's environmental impact and the evaluated impact of the changes. ~ 4. Conduct periodic audits of plant operations. 5. Review all reported environmental deviations 5.4 Action to be Taken in Event of Violation of an Environmental Technical g,w..,. w w @ eg411c3t,1,ory m m m m % p m y p.,.ee.r,. w e e t,c-

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5.4.1 Environmental Technical Specification Violation A violation of these Technical Specifications shall be reported immedi-ately to the #1 ant Superintendant,and at a formal meeting of. the. Plant...n-v.0;;:t

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' ReFiEO Cominittee"bh the Plant Chenical and Radiation Supervisor or, if ~ .,p sanavailable.by the Assistant Superintendent of Technical Support. ' ., s ;.y. ~M 5.4.2 Evaluation Report The Chairman of the Plant Review Committee sh;V prepare a detailed report outlining the events leading to the ' loa stion along with suggestions to prevent or reduce the pro'4b if

  • of recurrer1.e. This report shall be completed'within one v e. SP,, occurrence.

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s... 5.4.3 Report Distribteion The evaluation report will be di.stributed to the Plant Superintendent and to the Chairman of the Management Safety Review Committee. 5.5 Procedures 5.5.1 Detailed written procedures, including applicable check lists and instructions, will be prepared and adhered to for all activities in-volved in carrying out the environmental technical specifications. Procedures will include sampling and analysis, instrument calibration, and actions to be taken when limits are approached or exceeded. Test-ing frequency of associated alarms will be included. These frequencies will be determined from experience or from manufacturer's technical manuals. 5.5.2 In addition to the procedures'specified in Section 5.5.1, the plant Process Standards will include provisions to ensure the plant and all its systems and. components are operated in compliance with the environ-mental protection conditions established as Section 2 of these environ-mental techn,ical specifications. 5.5.3 All procedures described above, and all changes thereto, will be reviewed and approved prior to implementation and periodically thereaf ter by the Plant Review Committee. 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 -s. q. v. >..,.m.:..o r x- <m n,.m. : :wwp,wwms.s-> < c se, --,w,w.nmw.m.v.. saw.~..- The following is an acceptable content for this Section: 5.6.1 Routine Reports ~ 9.y.)*WKytykreport on environmental.' surveillance programsF for the. previous six .Q.O4'S months' operations will be submitted as part of the Semiannual Operating 7 mA M&f: Report within 60 days af ter: January T and July 1 ~of each year. 'The first ' *' N such period will begin with che date of initial criticality. The report will be a summary of _the results of the environmental activities for the 6-month period and an assessment of the observed impacts of the plant operation on the environment. The report will include a summary of the quantities of radioactive effluents released from the plant as outlined in USAEC Regulatory Guide 1.21, with data swnmarized on a monthly basis following a standard for=at. If statistically significant variations of offsite environmental radio-nuclide concentrations with time are observed, a comparison of these results with effluent releases shall be provided.

h Individual samples which show higher than normal. levels (25% above background for external dose, or twice background for radionuclide content) will be noted in the reports. Results of all radiological samples taken shall be summarized on a quarterly basis following a standard format for inclusion in the semi-annual report. In the event that some results are not available within the 60-day period, the report should be sumbitted noting and explaining the reasons for the missing results. The missing data shall be submitted as soon as possible in a supplementary' report. 5.6.2 Non-Routine Reports A. Radioactive Discharge The repcrting requirecents'for radioactive discharges are specified in Section 2.6 of the Technical Specifications. B.,, Radiological Environmental Monitoring 1. If a measured level of radioactivity in " critical pathway 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 en-sure the plant related annual doses will be within the design obj ective. 2. If samples of criticaIl pathway environmental media collected over a calendar quarter show total levels of radioactivity that could result in accu =ulated plant related doses to an individual "' " '#*~ ^ * ' for"tlia't quarteF'o'f"l/2 YNIannua'l'dedisinobj edEiie, t!ie 'resul'ts ~ ' ' ^ 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 _the design obj ective. h4 WirC~W WE T.*J.% @ gigre# Y D N b M MMMMDMMMTM*OD g aF ' +- -r.- h M ~ m - e. ,.w u. aic o n -. a-- w - -.. -s -c - -m In the event an Environmental Protection Condition is exceeded,. ~ or a report level specified in Section 4, Environmental Surveillance is reached, or an unusual event involving a significant environmental impact occurs, a report will be made within 24 hours by telephone and telegraph to the Director of the Regional Regulatory Operations Office, followed by a written report within one week 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. .f. .-,j. u ~

a 1,.., 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. D. Cham es 1. 4 hen 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 en environmental matter or question not previously reviewed and evaluated by the AEC, a report on the change will be made to the AEC prior to implementation. The report will include a description and evaluation of the change including a supporting benefit-cost analysis. 2. Changes or additions to-permits and certificates required by Federal, State, local and regional authorities for the protection of the environment will be reported. When the required changes are subm.itted 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 the environmental impact of the change. 3. Request for changes in environmental technical specifications will be submitted to the Deputy Director of Reactor Projects, Directorate of Licensing, USAEC, for prior review and authori-zation. The request will include an evaluation of the impact of the change, including a supporting benefit-cost analysis. -6 ~ * > 5 h we:Gecords~ Retention' * * -r.* w m *^<* W N m "d e r '" *A 7 N " **

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A. Records and drawing changes reflecting plant design modifications qv.- c/ xmade to s r.r- . pr. -h;..:..r:.r ~ystems and equipment as described in Section S. 0 '- @ 6'*:E'

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5. 7. 2 All other records and logs relating to the environmental technical specifications will be retained for five years.

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c*e a . ~ 5 GENERAL m, MANAGER -i 3 ^ : - i ASSISTANT f f GENERAL MANAGER T,' i AND CHIEF ENGINEER i i -s 3 MANAGER MANAGEMENT T' SUPERINTENDENT ENGINEERING SAFETY REVIEV1 RANCHO SECO COMMITTEE i ~ PLANT R EVIEV1 COMMITTEE e. e ~.a w wp n.w w mu.: w +..r, m 9.s m e.o,:...ru. + w....,,, ,._,.,g.. g. p..,,. 2.ws.vw m ec. n u-3gve w u,t.s.ew y,.g.qpgg,go.p ygg 4.,.g.g

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{ u..O i J. - J f P PLANT e SUPERINTENDENT <s </ </ </ I TECHNICAL ADMINISTRATIVE ASSISTANT STAFF o // < s,. ASST. SUPT. ASST. SUPT. NUCLEAR PLANT MAINTENANC, ' TECHNICAL OPERATIONS (SL) SUPERVISOR SUPPORT . / // // // 'j SHIFT MAINTE N ANCE $ 'j SUPERVISORS ISL) PERSONNEL s i, s s </ ' ' 's 's 's 's 'l< '. < 's 's '. * ', 's *, ' ', ! s SR. CONTR OL jf l ROOM OPER ATORS (L) I CHEMICAL R AOlATION INSTRUMENT-CONTROL POWER PLANT SUPERVISOE ENGINEER ENGINEERS CONTROL ROOM $7 OPER ATORS (L*) CH EMIST RY-R ADI ATION INSTRUMENT-CONTROL PERSONNEL PERSONNEL ... :.:a, m.. .,.. vg

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.-s.... -r .~.- enr. OPE RATORS i SL. SENIOR AEC LICENSE L. AEC LICENSE jg5ph4 c t,yEQUIPMENT. s,- ,3,g. gy.r;/MPsdMCENSE NOT REQUIRED FOR-INITIAL OPERATION ~ 3'M ATTEND ANTS, ? n s..~..... ..n.~etn %yf.9.w~)u+%~w a+.s ri; 2 %q., r. 4 _rg.' -nl;:v.}f ~ - 4 FIGURE 5-2 PLANT ORGANIZATION CHART RANCHO SECO UNIT 1 RANCHO SECO UNIT 1 TECHNICAL S.'ECIFICATIONS ENVIRONMFNTAL b-- SACRAMENTO MUNICIPAL UTIUTY DISTR!CT.. ,}}

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