ML20082K549

Environ Rept - OL Stage Amend 2 Page Changes

ML20082K549
Person / Time
Site:	Hope Creek, 05000355
Issue date:	12/31/1983
From:	Public Service Enterprise Group
To:
References
ENVR-831231, NUDOCS 8312050221
Download: ML20082K549 (85)

Text

.

HCGS OLER 12/83 HOPE CREEK GENERATING STATION CONTROLLED COPY

[d 1 ENVIRONMENTAL REPORT-OPERATING LICENSE STAGE AMENDMENT 2 PAGE CHANGES NO.

The attached pages, tables, and figures are part of your controlled copy of the Hope Creek Generating Station E R-O LS . This material should be incorporated into your ER-OLS by following instructions below.

REMOVE INSERT VOLUME 1 Page iv Page iv Page 3-1 and 3-11 Page 3-1 and 3-11 Table 3.3-1 Table 3. 3-1 Figure 3.3-1 Figure 3.3-1 Page 3.5-23 Pages 3. 5-23 thru 3. 5-23( b )

Page 3.5-27 Page 3.5-27 Page 3.5-38 Pages 3.5-38 thru 3.5-38(b)

Page 3.5-39 Pages 3.5-39 thru 3.5-39(b)

Table 3. 5-9, Sh. I thru 4 Ta ble 3. 5-9, Sh. 1 thru 3 Table 3.5-18, Sh. 2 Table 3.5-18, Sh. 2 Table 3.5-19, Sh. 1 Ta ble 3. 5-19, Sh . 1 Table 3.5-25 Table 3.5-2 5 Table 3.5-26, Sh. 4 thru 7 Table 3.5-26, Sh. 4 thru 7 Page 3.6-4 Page 3.6-4

\/ VOLUME 2 Page iv Page iv Pages 5-11 and 5-vi Pages 5-11 and 5-vi Table 5.2-2 Table 5.2-2 Table 5.2-3 Table 5.2-3 Table 5.2-4 Table 5.2-4 Pages 5.3-1 thru 5.3-3 Pages 5.3-1 thru 5.3-3 Figure 5.3-1 Page 10.4-1 Page 10.4-1 Pages 13.1-1 and 13.1-2 Pages 13.1-1 and 13.1-2 13.1 References, Shs 1 and 2 13.1 References, Shs 1 and 2 Page C-16 Page C-16 Page C-39 Page C-49 Page C-4 9 e L 9gy

[^} M P83 123/13 1-gs / Amendment 2 LI

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O HCGS OLER 12/83 AMENDME,NT 2 PAGE CHANGES (CONTINUED)

REMOVE INSERT VO LUM E 3 FRONT COVER Tab " Table of Contents" Pages i thru iv Page E-it Page E-li Page E-iii . Page E-iii Page E291.17-1 Page E291.17-1 Page E291.20-1 Pages E291.21-1 and E291.21-2 Figures 291.21-1 and 291.21-2 Page E291.22-1 Page E450.1-1 Page EP-i Page EP-i ,

Pages EP3-1 thru EP3-5 Pages EP3-1 thru EP3-5 l Pages EP5-1 and EPS-3 Pages EPS-1 and EP5-3 I Page EP10-1 Page EP10-1 Page EP13-1 Page EP13-1 Page EPA-2 Page EPA-2 Page EPQ-2 . Page EPO-2 BACK COVER (3 M P83 123/13 2-gs Amendment 2 d

HCGS OLER 12/83 TABLE OF CONTENTS (Continued)

Page Chapter Title Number 14 REFERENCES APPENDICES Appendix A - Thermal Modeling Methodology... A-1 Appendix B - ............................... (Not Used)

Appendix C - Class 9 Consequence Analysis... C-1 QUESTIONS E-i 2

LIST OF EFFECTIVE PAGES EP-i O .

a M P83 85/17 1-gs iv Amendment 2 k' _ _ _ _ . . . _ _ _ . ma

,3 HCGS OLER 12/83

\ CHAPTER 3 THE STATION CONTENTS Page Number 3.1 E XT E R N A L A P PE A RA NC E . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3.1-1 3.1.1 Physical Appearance........................ 3.1-1 3.1.2 Aesthetics................................. 3.1-3 3.2 REACTOR AND STEAM ELECTRIC SYSTEM................. 3.2-1 3.3 STATION WATER USE................................. 3.3-1 3.4 HEAT DISSIPATION SYSTEM........................... 3.4-1 3.4.1 Intake...................................... 3.4-1 3.4.2 Se rv ice Wate r Sy s te m. . . . . . . . . . . . . . . . . . . . . . . 3.4-3 3.4.3 Circulating Water System................... 3.4-4 3.4.4 Natural Draft Cooling Tower................ 3.4-5 g-sg 3.4.5 Discharge.................................. 3.4-7

\' ') 3.5 RAD 51.".STE SYSTEMS AND SOURCE TERM.................. 3 5-1 3.5.1 So u r c e Te rm . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3.5-1 3.5.1.1 Fission Products... ..................... 3.5-2 3.5.1.2 Activation Products...................... 3.5-8 3.5.1.3 Tritium.................................. 3.5-9 3.5.1.4 Fuel Experience.......................... 3.5-12 3.5.1.E Process Leakage Sources.................. 3.5-12 3.5.2 Li qu id Ra dw a s te S ys te ms . . . . . . . . . . . . . . . . . . . . 3.5-13 3.5.2.1 Design Bases............................. 3.5-13 3.5.2.2 Sy s t e m De s c r i p t i o n . . . . . . . . . . . . . . . . . . . . . . . 3.5-16 3.5.2.2.1 System Operation...................... 3.5-16 3.5.2.2.2 Process Equipment Description. . . . . . . . . . 3.5-19 3.9.2.2.3 Filters................................ 3.5-20 a.5.2.2.4 De m i n e ra l i z e r s . . . . . . . . . . . . . . . . . . . . . . . . . 3.5-20 3.5.2.2.5 Ra dw as te Evapora tors . . . . . . . . . . . . . . . . . . . 3.5-21 3.5.2.3 Rad i oa c t i v e Re le a s e s . . . . . . . . . . . . . . . . . . . . . 3.5-22 3.5.2.4 Estimated Doses.......................... 3. 5-23(a ) I 2 1

M P83 123/10 1-cag 3-i Amendment 2

U HCGS OLER 12/83 CONTENTS (m) Page Number 3.5.3 Gaseous Radwaste Systems................... 3. 5-2 3(a ) l2 3.5.3.1 De s i g n B a s e s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3.5-24 3.5.3.2 System Description....................... 3.5-25 3.5.3.2.1 of f g a s Sy s t e m. . . . . . . . . . . . . . . . . . . . . . . . . . 3.5-25 3.5.3.2.1.1 Process Description.................. 3.5-25 3.5.3.2.1.2 System Design Considerations. . . . . . . . . 3.5-27 3.5.3.2.1.3 Co mp o ne n t De s c r i p t i o n . . . . . . . . . . . . . . . . 3.5-28 3.5.3.2.1.4 Leakage of Radioactive Gases. . . . . . . . . 3.5-31 3.5.3.2.1.5 Instrumentation and Control.......... 3.5-31 3.5.3.2.1.6 Of fgas System Operating Procedure. . . . 3.5-34 3.5.3.2.1.7 Equipment Malfunction................ 3.5-35 3.5.3.2.2 Other Radioactive Gas Release Paths. . . 3.5-36 3.5.3.3 Radioactive Releases..................... 3.5-38 3.5.3.4 Estimated Doses.......................... 3.5-38(a) l2 3.5.4 Solid Radwaste System...................... 3.5-39(a) l2 3.5.4.1 3.5.4.2 Overall System Description............... 3.5-39(a) l2 Treatment of Radioactive Resins.......... 3.5-40 3.5.4.3 Treatment of Concentrates from the Liquid Radioactive Waste System......... 3.5-41 gS 3.5.4.4 Compressible Waste....................... 3.5-42

I 3.5.4.5 Treatment of Other Waste................. 3.5-42 sm/

3.5.5 Process and Effluent Monitoring............ 3.5-42 3.5.5.1 Gaseous Channels......................... 3.5-43 3.5.5.2 Liquid Channels.......................... 3.5-46 3.6 CH EM ICA L AN D B IOC I DE WASTES . . . . . . . . . . . . . . . . . . . . . . . 3.6-1 3.6.1 B i oc i d e S y s t e m. . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3.6-1 3.6.2 Sc ale Co nt rol Sys tem. . . . . . . . . . . . . . . . . . . . . . . 3.6-2 3.6.3 Cooli ng Towe r Blowdow n. . . . . . . . . . . . . . . . . . . . . 3.6-2 3.6.4 Ma keup Demine ralize rs . . . . . . . . . . . . . . . . . . . . . . 3.6-3 l2 3.6.5 Auxiliary Boilers.......................... 3.6-3 3.6.6 Oily Water Wastewater System............... 3.6-4 l2 3.6.7 Metal Cleaning Wastes...................... 3.6-4

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M P83 122/01-1 3-li Amendment 2

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KIE dfR 12/103 TAHLE 3.3-1 tARR LEE SJ9Mr 1 2 3 4 SLI) "6 7 8 9 to IL 12tJ3 13(43 14 15 16 17 le

>mtric (latersArute) tally mannes e tout 127,0u0 6,700 120,300 120,300 52,200(4) 68,10u 2,000,0001,477 130 130 1, 347 1Rs 1,020 15u(3) 114 2u 173 2s7 t291.6 ptrthly Averap e 1005 131,000 6,600 124,400 124,400 43,500 u0,900 2,000,000 789 130 130 659 57 527 75 3u 2.6  % 134 Cnima Iber geratim 131,000 6,603 124,400 124,400 30,100 94,300 1,160,000 7W9 130 130 659 57 527 75 38 2.6 96 134 i

tblio,ithj N3ml "ladam 220,000 , 13,5u0 206,500 206,500 0 206,500 0 7u9 130 130 659 57 527 75 3H 2.6  % 1 34 tolto,Lru twrtpwry Sutam 201,000 13,800 187,200 187,200 0 206,500 0 1,477 130 130 1,347  !?O 1,020 15u(33 114 28 17J Ju?

oulish (callcrrAirunel 2-(4) (3)

Onity Maxima e loot 33,600 1,7HU 31,820 31,920 13,800 18,020 552,000 390 35 35 355 45 270 40 3) 7.6 45 75 lE291.6 pertally Awrap e 100s 34,600 1,74n 32,860 32,860 11,500 21,360 552,000 195 20 20 175 15 140 20 to 0.7 , 25 35 tunima Iber q=raticn 34,600 1,740 32,860 32,860 s,00u 24,860 306,0u0 195 20 20 175 15 140 20 to 0.7 25 35 tollostry Narnet Mutdm $st,000 3,560 54,440 54,440 0 54,440 0 195 20 20 175 15 140 al 10 0.7 25 35 (3) .

tbliosiry twrtpwry thutdun 53,200 3,643 49,560 49,560 0 49,560 0 390 35 35 355 45 27u 40 3) 7.6 45 75 tee this tatla in arrectim with Figav 3.3-1.

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SACS / RACS SER"VICE WATER INTAKE h > HEAT EXCHANGERS DE-ICING LINE COOLING TOWER BLO)

1. TURBINE /REAC1DR STEAM CYCLE 4

jL r CONDENSATE STORAGE TANKS AL 2 JL 1r g jg h LIQUID RADWASTE MAKEUP DEMINERALIZER g , PROCESSING SYSTEM

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g AREA, BUILDING g AND EQUIPMENT g DRAINS 9

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4 g SEWAGE TREATMENT 4 4 SYSTEMS (3) 8 v

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( MAKEUP DEMINERALIZER 4 Q .

WATER STORAGE TANKS (for fire and 4 +2 FEED TANK potable use) b SYSTEM LOSSES V@

DOMESTIC WATER y h >

AUXILIARY BOILERS

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V g POTABLE WATER SYSTEM

< Also Available On Aperture Card HOPE CREEK GENERATING STATION ENVIRONMENTAL REPORT h OPERATING LICENSE STAGE

- STATION WATER USE l CARJ FIGURE 3.3 - 1 AMEND. 2 l

. - - - _ - - - - _ - - - - - - - - - - - - - 8812050221-OI

HCGS OLER 12/83 f~h

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Table 3.5-7 gives the assumptions and parameters used to cal-culate the yearly activity releases. The yearly activity releases for each waste stream and the total appear in Table 3.5-17.

The processed liquid radwaste that is not recycled in the plant is discharged into the cooling tower blowdown line on a batch basis, at flow rates of up to 666 liters per minute (176 gallons per minute) for the low purity waste processing sys-tem, and 95 liters per minute (25 gallons per minute) for the laundry drain waste processing system. (No pump flows are given for discharges from the high purity, chemical or regene-rant waste processing streams since it is not planned to actually discharge any of those streams.) Flow is controlled by a flow control valve; therefore, the actual flow could be substantially less.

The minimum monthly total cooling tower blowdown flow of 72,000 liters per minute (19,000 gallons per minute) dilutes the'above discharge rates by at least a factor of 100 for the low purity waste, and by 750 for the laundry waste streams.

This dilution occurs within the site boundary; the dilution is used in determining specific activity concentrations for the

,,s releases. These concentrations and a comparison to 10 CFR 20

( ) limits appear in Table 3.5-18.

V No actual leak detection methods have been employed but several design measures have been implemented to preclude leakage or the consequences of any leakage. These measures include: the use of stainless steel piping, sampling the rad-waste tanks prior to discharge and discharging only neutral (pH 7 to 10) liquids to minimize the internal pipe corrosion 2 process, hydrostatically testing the pipe prior to burying it, burying the pipe in granular bedding or sandcrete, and supply-ing the piping with impressed current cathodic protection to preclude external galvanic type corrosion.

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M P83 122/01-2 3.5-23 Amendment 2

_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . .__ _n

HCGS OLER 12/83 3.5.2.4 Estimated Doses To ensure compliance with Appendix I of 10 CFR Part 50, dose calculations, based on the liquid source terms described above, are performed in accordance with Regulatory Guide 1.109 by use of the USNRC computer code LADTAP II. For these pur- l1 poses doses are calculated for a maximum individual consuming aquatic biota and receiving shoreline exposure at the edge of the initial mixing zone. There is no potable water or irriga-tion pathway for liquid effluents from HCGS. Table 3.5-19 gives input data for these calculations. The calculated doses are 0.026 mrem per year to the total body of an adult and 1 0.372 mrem per year to the bone of a child. These doses are well within the Aopendix I design guides of 3.0 and 10.0 mrem per year to the total body and any organ, respectively.

Total man-rem and man-thyroid-rem dose to the 80 kilometer (50 mile) population from liquid effluents from Hope Creek Gen-erating Station are estimated to be 0. 25 2 a nd 0. 74 2, respec-tively. Using the methodology presented in Regulatory Guide 1.110, additional equipment can be justified if its total annual cost is less than one thousand 1975 dollars per man-rem or man-thyroid-rem saved. The smallest total annual cost per man-rem or man-thyroid-rem saved (even assuming that the 2 equipment would totally eliminate all 80 kilometer (50 mile) population doses) is estimated to be S14,500 (1975). Since this is greater than S1,000 (1975), it is concluded that no additional equipment can be justified. Thus the liquid waste management system is judged to be designed in accordance with the applicable position of Appendix I to CFR 50.

3.5.3 GASEOUS RADWASTE SYSTEMS The gaseous waste management systems include all systems that process potential sources of airborne releases of radioactive material during normal operation and anticipated operational occurrences. Included are the offgas system and various ventilation systems. These systems reduce radioactive gaseous releases from the plant by filtration or delay, which allows decay of radioisotopes prior to release.

O M P83 122/01-3 3.5-23(a) Amendment 2

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1 HCGS OLER 12/83 O -

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O O M P83 122/01-4 3.5-23(b) Amendment 2

HCGS OLER The function of the of fgas system is to collect and delay the release of noncondensable radioactive gases removed from the main condenser by the air ejectors during normal plant op e ra-tion. Plant ventilation systems process airborne radioactive releases from other plant sources, such as equ ipment leak age ,

maintenance activities, the mechanical vacuum pump and the steam seal system.

3.5.3.1 Design Bases:

a. The gaseous waste management systems are designed to control and monitor the release of radioactive materials in gaseous effluents in accordance with General Design Criteria (GDC) 60 and 64 of 10 CFR 50, Appendix A.

b. The of fgas system design basis source te rms cor-respond to 500,000 microcuries per second of radio-active noble gases after 30-minute de l a y .

c. The gaseous waste systems are designed to limit off-site doses from routine plant releases to signifi-cantly less than the limits specified in 1.0 CFR 20, and to operate within the dose objectives established in 10 CFR 50, Appendix I.

d. The gaseous waste management systems are designed with sufficient capacity and redundancy to accom-modate all anticipated processing requ irements of the plant during normal operation, including anticipated

, operational occurrences.

e. Continuous monitoring is provided for all pote ntial pathways of airborne radioactive releases. with main control room annunciation at levels higher than allowed limits.

f. Design provisions are incorporated that preclude the uncontrolled release of radioactivity to the environ-ment as a result of any single operator error or any single active component failure,

g. The gaseous waste management systems are designed to keep the exposure to plant personnel as low as is reasonably achievable (ALARA) during normal operation and plant maintenance, in accordance with Regulatory Guide 8.8.

O M P82 14 2/15-li 3.5-24

HCGS OLER 12/03 O

\# malfunction of moisture removal features occurs, as well as to adsorb impurities in the process gas that might adversely af fect performance of the main charcoal vessels.

Af ter passing through the guard bed, the offgas enters the main charcoal adsorption beds. The charcoal adsorption beds, maintained at 18'C (65*F) by redundant room heating and air conditioning units, selectively adsorb and delay the xenon and krypton from the bulk carrier gas. This delay permits the xenon and krypton to decay in place. The offgas stream then passes through a HEPA filter where radioactive particulate matter and any charcoal particles are retained.

The offgas stream is then directed to the north vent stack, where it is diluted with a minimum of 41,900 standard cubic feet per minute of air from the solid radwaste system exhaust 2 and chemical lab exhaust, before being released. Table 3.5-22 shows the estimated annual release rate from the offgas system.

All moisture removed from the process stream is returned to the main condenser, except for the condensate f rom the glycolcooler condenser, which is routed to the clean radwaste drainage (CRW) system.

() '3.5.3.2.1.2 System Design Considerations Charcoal Holdup Time

, The charcoal adsorber bed is designed for a delay time of 35 days for xenon under the condition of a 75 standard cubic feet per minute condenser inleakage rate using manufacturer's guaranteed adsorption coefficients (733 cubic centimeters per gram for xenon and 32 cubic centimenters per gram for krypton). The required charcoal mass of 146,000 kilograms (322,000 pounds) is obtained by the following equation from References 3.5-11 and3.5-12:

-- I M = 0.26K where:

T = holdup time, hours K = dynamic adsorption coefficient, cubic centimeters per gram V = air flow rate, standard cubic feet per minute M = mass of charcoal, 103 pounds M P83 122/01-5 3 5-27 Amendment 2

HCGS OLER Using the adsorption coefficients for the condition of 25 C (77'F) operation, 7'C (45*F) dew point, the NUREG-0016, Revi-sion 1 (Reference 3.5-13) methodology yields delay times of 55 days and 3.1 days for xenon and krypton, respectively, for 146,000 kilograms (322,000 pounds) of charcoal. This estimate is very conservative since the adsorption coefficients for 18'C (65'F) operation and 43C (40*F) dew point should be sig-nificantly higher than the ones for 25'C (77*F) operation and 7'C (45'F) dew point (330 cubic centimeters per gram for xenon and 18.5 cubic centimeters per gram for krypton).

Hydrogen Detonation Resistance The pressure boundary of the of f gas system is designed to withstand the effects of a hydrogen detonation during all anticipated modes of operation. In addition, the system includes features tha t reduce the probability of an explosion. Such features include:

a. Mainte nance of nonexplosive mixture throughout the system - loss of dilution steam in SJAE will actuate an alarm and the suction valve of SJAE will be closed to isolate the offgas system.

b. Minimization of pote ntial ignition sources, e.g.,

nonsparking valves.

c. Design with dual hydrogen analyzers which isolate wher the setpoint is reached.

3.5.3.2.1.3 Component Description Table 3.5-23 lists the materials of construction, design temperatures and pressures.

Recombiner Section:

a. Preheater - The preheater is a straight tu be-a nd-shell heat exchanger with the process gas on the tube side and steam on the shell side. Main steam is used to heat the process gas before entering the recom-biner. The process gas enters the preheater at 105*C (221'F) and is heated to 132*C ( 270 *F ) . Auxiliary steam is also available for heating the process gas flow, should main steam be unavailable. Condensate from the shell side of the heat exchanger is col-lected in a flash pot and routed back to the main condenser.

O M P82 142/15-li 3.5-28

HCGS OLER

[/')

HEPA and charcoal filters for cleanup. After reaching a steady state, approximately 7.1 cubic meters per minute (250 cubic feet per minute) of air exhausted from the FRVS recirculation system is filtered again by the FRVS ventilation system, which is equipped with HEPA and charcoal filters, and then released to the atmosphere through a vent at the top of the reactor building; this maintains the building at a negative pressure of 0.25-inch water guage.

During power operation, radioactivity released from minor sys-tem leakage inside the drywell is contained, except for minor releases necessary to control drywell pressure. Pressure is controlled by bleeding air f rom the drywell through five-centimeter (two-inch) lines connected to the RBVS exhaust system prior to release to the environment.

Af ter the reactor is shut down, and before the drywell and torus are purged by the RBVS, the containment atmosphere is first recirculated through the containment prepurge cleanup system (CPCS) for up to 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />, to reduce the level of atmospheric iodine and particulate radioactivity. After the prepurge cleanup. process, the RBVS provides the supply air to and exhausts air f rom the drywell and torus for purge.

Radwaste Enclosure

/x

) The radwaste area supply system delivers filtered and tempered

'- air that is distributed throughout the enclosure in quantities '

sufficient to maintain required temperatures. The equipment compartment exhaust system consists of three 33-1/3 percent capacity fans and 33-1/3 percent capacity filter plenums. The service area exhaust system consists of two 50-percent capac-ity f ans without exhaust filtration since this is a non-radioactive area. The chemical lab exhaust system consists of two 100-percent capacity fans and two 100-percent capacity filter plenums. The solid radwaste area is supplied with filtered and tempered air in order to maintain design tempera-tures. The solid radwaste area exhaust system consists of two 50-percent capacity fans and two 50-percent capacity filter plenums. Each filter plenum has a bank of prefilters and a bank of HEPA filters. This exhaust system is balanced to ensure that the flow of air within the enclosure is into areas with higher potential for airborne radioactive contamination.

The tank ventilation filter system provides a means of filter-ing and venting air from tanks and equipment housed in the radwaste enclosure. Two redundant fans and filter plenums are employed for this purpose. There are HEPA filters and char-coal adsorbers in each filter plenum. Since the flow of air from tanks and equipment varies, space air is admitted as required to maintain system volume.

ex (1 ,/)

M P8 2 14 2/15 li 3.5-37

l HCGS OLER 12/83 All the exhaust system ducts transport the filtered air to O

either the north or south plant vents.

Each of the above exhaust systems and the respective supply systems are interlocked so that failure of the exhaust system shuts down the supply system. This condition is alarmed in the main control room.

Turbine Enclosure During plant start-up, air is removed from the main condenser by two mechanical vacuum pumps. Each vacuum pump discharges to the south plant vent; if excessive release of radioactivity is detected at the vent, the pump trips, automatically closing the pump suction valves, and actuating an alarm.

In the past, discharge from the steam packing exhausters has presented a source of gaseous radioactive releases in some BWR plants; at HCGS, however, clean. steam (produced from deminer-alized condensate) from the steam seal evaporator is provided for sealing purposes. Therefore, essentially no activity is released from this system.

The exhaust air from the turbine building ventilation system is monitored for radioactivity prior to its discharge to the atmosphere.

3.5.3.3 Radicactive Releases The assumptions used in this evaluation are summarized in Table 3.5-i. The calculated annual releases appear in Table 2 3.5-22.

It is expected that the actual releases from the plant will be lower than those referenced above, due to the more realistic parameters associated with the equipment described in this chapter. Table 3.5-28 summarizes the charcoal filtration sys-tems that reduce the airborne radioactive releases. Table 3.5-25 presents a comparison between the concentrations at the site boundary (901 meters (2960 feet)) using the annual X/Q value of 2.47E-7 second per cubic meter with the appropriate 2 recommended concentrations presented in Table II Column 1 of 10 CFR 20.

With the exception of the FRVS ventilaton system which discharges at the top of the reactor building all potentially 2 contaminated gaseous releases are through the north and south plant vents. The north plant vent serves the of f-gas system, O

M P83 122/01-6 3.5-38 Amendment 2 l

s HCGS OLER 12/83

1. the solid radwaste exhaust system, and the chemistry lab exhause system. The south plant vent serves the following systems:

a. Reactor Building Ventilation System (RBVS)

b. Radwaste Ar_ea Exhaust (RWE) System

c. Service Area Exhaust (SAE) System

d. Turbine Building Exhaust (TBE) System .

2

e. Turbine Building Compartment Exhaust (TBCE) System

f. Turbine Building Oil Storage Room Exhaust (TROE)

System

g. Gland Seal Exhaust -

h. Mechanical Vacuum Pump Discharge The height, effluent flow rate, average temperature, exit velocity, heat content, and dimensions of the north and south plant vent are shown on Table 3.5-27, 3.5.3.4 Estimated Doses Table 3.5-25 also presents the whole body dose at the site boundary. To assure compliance with Appendix I of (REMAINDER OF PAGE IS INTENTIONALLY BLANK) 9 O M P83 122/01-7 3.5-38(a) Amendment 2

)

HCGS OLER 12/03 O

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O O

M P83 122/01-8 3.5-38(b) Amendment 2 l

HCGS OLER 12/83 N- 10 CFR Part 50, dose calculations, based on the gaseous source term referenced above, were performed in accordance with Regu-latory Guide 1.109 by use of the USNRC computer code GASPAR (revised 8/19/77). Input data for these calculations are given in Table 3.5-26. X/Q's for the nearest residence in each of the sixteen compass directions were calculated. The sector with the highest X/Q corresponds to that sector with the highest calculated doses and is designated the nearest residence - 5.2 kilometers (3.5 miles) NW. It is conserva-tively assumed that the nearest vegetable garden, milk cow, and meat animal are also located at that residence since it is possible for them to be there. Maximum doses to an individual are calculated using the values for that location. These doses are calculated using the highest pathway doses regard-less of age group; that is, the child thyroid dose is useo for the vegetable ingestion pathway, whereas the infant thyroid 1 dose for the cow's milk pathway is used. The calculated doses are 0.179 mrad per year beta air dose and 0.155 mrad per year gamma air dose for noble gases; the Appendix I design objec-tives are 20 and 10 mrad per year, respectively. Noble gas doses to the total body and skin are calculated as 0.103 mrem per year and 0.279 mrem per year, respectively; the respective limits for these pathways are 5.0 mrem per year and 15.0 mrem per year. The Appendix I design objective for radiciodine and particulates is 15 mrem per year to any organ. The thyroid O dose from this source is calculated as 0.981 mrem per year.

All calculated doses are within the appropriate Appendix I design objectives.

The total man-rem and man-thyroid-rem dose to the 80 kiJometer (50 mile) population from gaseous effluents from Hope Creek Generating Station are estimated to be 16.3 and 31.0 respec-tively. Using the methodology presented in Regulatory Guide 1.110, additional equipment can be justified if its total annual cost is less than one thousand 1975 dollars per man-rem or man-thyroid-rem saved. The smallest total annual cost per 2 man-rem or man-thyroid-rem saved is estimated to be S1,775 (1975). Since this is greater than S1000 (1975), it is con-cluded that no additional equipment can be justified. Thus the gaseous waste management system is judged to be designed in accordance with the applicable position of Appendix I to 10 CFR 50.

O M P83 122/01-9 3.5-39 Amendment 2

I HCGS OLER 12/03 t

l 3.5.4 SOLID RADWASTE SYSTEM 3.5.4.1 Overall System Description The solid radwaste system, as described in Section 11.4 of the HCGS FSAR, collects, reduces the volume, solidifies and pack-ages low-level radicactive waste for its eventual shipment off site to a licensed burial site. The solid radwaste system shown in Figures 3.5-7 and 3.5-8 accepts dry colid trash, potentially radioactive lubricating oil from various pumps, processed concentrated chemical slurries, sludge and spent resins. The solid wastes are grouped for discussion purposes into four general categories. These four categories are:

a. Resin slurries

b. Concentrates f rom the liquid radioactive waste system

c. Compressible waste

d. Other waste The vari.ous types of solid waste are processed dif ferently in order to maximize the amount of volume reduction, and thus minimize the volume of waste requiring packaging and shipping off site for burial. The various treatment methods are described in the following sections.

(REMAINDER OF PAGE IS INTENTIONALLY BLANK) e M P83 122/01-10 3.5-39(a) Amendment 2 j

HCGS OLER 12/83 0

l (THIS PAGE IS INTENTIONALLY BLANK)

O O M P83 122/01-11 3.5-39(b) Amendment 2

HCGS OLER 3.5.4.2 Treatment of Radioactive Resins The solid radioactive waste system accepts waste sludge and resin slurries f rom the waste sludge phase separator, the cleanup phase separators and the spent resin tank. These resin slurries are pumped directly into a radioactive waste centrifuge feed tank on a batch basis by the pumps of the liquid radioactive waste system. A decant pump is used to remove any excess water f rom the f eed tank af ter allowing suf-ficient time for the resin material to settle. The slurries are then recirculated and agitated and the pli is adjusted. A small side stream is then taken off the recirculation loop for control metering, and sent to the centrifuge. The centrifuge separates the carrier water f rom the resin / sludge mixture, and then directs this moist, aerated slurry to one of the two waste extruder / evaporators. The extruder / evaporator mixes the slurry with asphalt at a temperature of approximately 300*F (150aC). This temperature is suf ficiently high to evaporate any remaining water. The asphalt and resin mixture is ex-truded into 55-gallon drums as a more dense and concentrated product. The filled drums are moved using a monorail trans-port system, which is operated by remote control. A closed-circuit television monitors the operation of the system. The monorail system uses a turntable to place empty drums beneath the filling lines of the extruder / evaporator. Af ter the drums are filled, the turntable rotates, and the monorail system removes the filled drums and transports them to the capping and radioactive swiping station. Upon arriving at this sta-tion, the drums are capped, radiation readings are taken, and the drums are swiped a final time, and properly labeled. The drums are then conveyed to the truck bay area where they are loaded into a waiting truck or placed into the radwaste stor-age area for subsequent disposal. The' estimated quantity and activity of resin / slurry waste to be processed is listed below:

Source of Radioactive Waste Besin Anticipated System Annual Volume Activity

a. Waste sludge 330,950 liters 6.18 x 10-1 uCi/cc (normal) phase separator (87,430 gal) 2.03 x 10 uCi/cc (ma x )

b. Clean-up phase 59,280 liters 3.8 x 10 uCi/cc (normal) 2 separator (15,660 gal) 4.0 X 10 uCi/cc (max )

c. Spent resin 38,790 3iters 3.3 x 10-1 uCi/cc (normal) 3 tank (1370 ft ) 1.2 x 10

• uCi/cc (max )

O M P82 142/15-li 3.5-40

HCGS OLER 12/83 q TABLE 3.5-9 (Page 1 of 3) 2 EXPECTED RADIONUCLIDE ACTIVITY CONCENTRATIONS IN REACTOR COOLANT AND MAIN STEAMil) USED FOR EVALUATION OF RADIOACTIVE RELEASES (in uCi/gm)

Isotope Reactor Coolant (2) Reactor Steam (2)

Noble Gases Ar-41 -

0 Kr-83m -

9.lE-3(3)

Kr-85m -

1.6E-3 Kr-85 -

5.0E-6 Kr-87 -

5.5E-3 Kr-88 -

5.5E-3 Kr-89 -

3.4E-2 Xe-131m -

3.9E-6 Xe-133m -

7.5E-5 Xe-133 -

2.lE-3 Xe-135m -

7.0E-3 Xe-135 -

6.0E-3 O Xe-137 -

3.9E-2 Q Xe-138 -

2.3E-2 Halogens (4)

Br-83 1.lE-3 1.7E-5(5)

Br-84 1.4E-3 3.0E-5 I-131 1.9E-3 3.0E-5 I-132 1.lE-2 1.7E-4 I-133 8.0E-3 1.2E-4 I-134 1.4E-2 3.0E-4 I-135 8.0E-3 1.2E-4 Cesium Cs-134 3E-5 3E-8 Cs-136 8E-5 8E-8 Cs-137 2E-5 2E-8 Cs-138 1E-2 lE-5 Tritium (6) .

H-3 lE-2 lE-2 p See page 3 for notes. 2 M P83 122/01-12 Amendment 2

HCGS OLER 12/83 TABLE 3.5-9 (Continued) (Page 2 of 3)

{2 l Isotope Reactor Coolant (2) Reactor Steam (2)

Other Nuclides Na-24 9E-3 9E-6 P-32 2E-4 2E-7 Cr-51 6E-3 6E-6 .

Mn-54 7E-5 7E-8 Mn-56 SE-2 SE-5 Fe-55 9E-4 9E-7 Fe-59 3E-5 3E-8 Co-58 2E-4 2E-7 Co-60 4E-4 4E-7 Ni-65 3E-4 3E-7 I

Cu-64 3E-2 3E-5 Zn-65 2E-4 2E-7 Zn-69m 2E-3 2E-6 Sr-89 9E-5 9E-8 Sr-90 7E-6 7E-9 G Sr-91 4E-3 4E-6 l

Q Sr-92 Y-91 lE-2 4E-5 lE-5 4E-8 Y-92 6E-3 6E-6 l

Y-93 4E-3 4E-6 Zr-95 7E-6 7E-9 Nb-95 7E-6 7E-9 Nb-98 4E-3 4E-6 l Mo-99 2E-3 2E-6

! Tc-99m 2E-2 2E-5 Tc-104 8E-2 8E-5 I

Ru-103 2E-5 2E-8 Ru-105 2E-3 2E-6 Ru-106 3E-6 3E-9 Ag-110m 9E-7 9E-10 Te-129m 4E-5 4E-8 Te-131m 9E-5 9E-8 Te-132 9E-6 9E-9 Ba-139 lE-2 lE-5 Ba-140 4E-4 4E-7 La-142 SE-3 5E-6 i

O M P83 122/01-13 Amendment 2

_ - _ . . _ - ~ __ _ __ ._. _ __.___. - - - - , _ - _ . _ _ . _ . - . _ _ _- . , . . - _ . _ _ _ - . _ . _ _ _ , _ . . -

HCGS OLER 12/83 TABLE 3.5-9 (Continued) (Page 3 of 3) l2 Ce-141 3E-5 3E-8 Ce-143 3E-5 3E-8 Ce-144 3E-6 3E-9 Pr-143 4E-5 4E-8 W-187 3E-4 3E-7 Np-239 8E-3 8E-6 (1) The reactor coolant concentration is specified at the nozzle where reactor water leaves the reactor vessel.

Similarly, the reactor steam concentration is specified at time 0 at the nozzle.

(2) Normal expected concentrations correspond to 50,000 uCi offgas release rate at 30 minutes.

(3) 1.1E-3 = 1.1 x 10-3 (4) All halogen concentrations have been adjusted lower to

/ account for the reduced I-131 source term which was

( reported in Revision 1 of NUREG0016. ,

(5) Halogen concentrations listed in reactor steam are based on a carryover of 0.015. For a carryover of 0.004 the halogen reactor steam concentrations would be reduced proportionately.

(6) Measured values increased to account for liquid recycle.

O M P83 122/01-14 Amendment 2

~ - _ _ _ _ _ _

l llCGS OLER 12/83

[ TABLE 3.5-18 (Continued) (Page 2 of 3)

'w -)

MPC (uCi/ml) 10CFR20 Concentration Table II, Fraction Isotope (uCi/ml)(1) Col. 2 of MPC Tc-99m SE-9 6E-3 8E-7 Ru-103 7E-ll 8E-5

9E-7 Rh-103m 2E-ll lE-2 2E-9 Tc-104 7E-12 3E-6 2E-6 Ru-105 2E-10 1E-$ 2E-6 Rh-105m 2E-10 3E-6 7E-5 Rh-105 lE-10 lE-4 lE-6 Ru-106 8E-10 lE-5 8E-5 Rh-106m 4E-12 3E-6 lE-6 Ag-110m lE-10 3E-5 3E-6 Te-129m SE-ll 3E-5 2E-6 Te-129 3E-ll 8E-4 4E-8 Te-131m 6E-ll 6E-5 lE-6 Te-131 lE-ll 3E-6 3E-6 I-131 3E-8 3E-7 lE-1

/ T Te-132 8E-12 3E-5 3E-7 Cl I-132 2E-9 8E-6 3E-4 I-133 2E-8 1E-6 2E-2

• I-134 SE-10 2E-5 3E-5 Cs-134 4E-9 9E-6 4E-4 I-135 SE-9 4E-6 lE-3 Cs-136 3E-10 9E-5 3E-6 Cs-137 8E-9 2E-5 4E-4 Ba-137m 9E-ll 3E-6 3E-5 Cs-138 lE-10 3E-6 3E-5 Ba-139 2E-10 3E-6 7E-5 Ba-140 4E-10 2E-5 2E-5 La-140 2E-10 2E-5 lE-5 La-141 9E-ll 3E-6 3E-5 Ce-141 4 E-ll 9E-5 4E-7 La-142 lE-10 3E-6 3E-5 Ce-143 2E-ll 4E-5 SE-7 Pr-143 SE-ll SE-5 lE-6 Ce-144 2E-9 lE-5 2E-4 Pr-144 4E-12 3E-6 lE-6 All Others 2E-ll - -

f'v) H3 9E-6 3E-3 3E-3 2

Total lE-7 lE-1 -

M P83 122/01-15.* Amendment 2

HCGS OLER 12/33 O TABLE 3.5-19 (Page 1 of 4)

INPUT DATA FOR AQUATIC' DOSE CALCULATIONS HOPE CREER GENERATING STATION - LIQUID DOSE CALCULATIONS 1 42.3 1.0 0 1 5.97E06 HCGS SOURCE TERM - ONE UNIT WITH MULTIPLIER OF 1.0 F3 26.0 NA24 0.012 P 32 0.00068 CR51 0.022 MN54 0.0013 MN56 0.0088 FESS 0.0041 FE59 0.00011 C058 0.0048 CO60 0.01

'NI65 0.000052 CU64 0.032 ZN65 0.00081

'^) ZN69M ZN69 0.0022 0.0024 0.00048 2 W 187 NP239 0.016 BR83 0.00059 BR84 0.000023 SR89 0.00039 -

SR90 0.000029 Y 90 0.000012 2 SR91 0.0033 Y 91M 0.0021 Y 91 0.0024 SR92 0.0019 Y 92 0.0046 Y 93 0.0035 ZR95 0.0014 NB95 0.002 NB98 0.000075 MO99 0.0049 TC99M 0.014 RU105 0.00022 RH103M 0.000075 TC104 0.000022 RU105 0.00074 RH105M 0.00075 RH105 0.00045 0.0024 O RU106 RH106 0.000012 M P83 122/01-16 Amendment 2

HCGS OLER 12/83 j

(]

t, 1 TABLE 3.5-25 EXPECTED ACTIVITY CONCENTRATIONS (uCi/ml) AT THE SITE BOUNDARY FOR EVALUATION OF GASEC'JS RELEASES MPC (uCi/ml) Annual 10CFR20 External Concentration Table II, Fraction Whole Body Isotope (uCi/ml)(1) Column 1 of MPC Dose (mrem)

I131 2E-14 lE-10 2E-4 6E-5 I133 3E-13 4E-10 8E-4 lE-3 H3 4E-12 2E-7 2E-5 -

Cl4 7E-13 lE-7 7E-6 -

Ar41 lE-12 4E-8 3E-5 lE-2 Kr85m 2E-12 lE-7 2E-5 Kr85 3E-3 2E-11 3E-7 7E-5 3E-4 Kr87 SE-12 2E-8 3E-4 3E-2 Kr88 7E-12 2E-8 4E-4 lE-1 Kr89 52-11 3E-6 2E-5 9E-1 Xel31m SE-13 4E-7 lE-6 8E-5 Xel33 lE-10 3E-7 3E-4 4E-2 Xel35m 8E-11 3E-6 3E-5 3E-1 Xel35 9E-ll lE-7 9E-4 2E-1 Xel37 lE-10 3E-6 3E-5 2E-1 Xel38 8E-11 3E-6 3E-5 7E-1 (j Cr51 7E-17 -

8E-8 9E-10 2E-8 Mn54 SE-17 lE-9 SE-8 CoS8 3E-7 8E-17 2E-9 4E-8 6E-7 Fe59 9E-J8 2E-9 3E-9 Co60 8E-8 9E-17 3E-10 3E-7 2E-6 Zn65 SE-16 2E-9 3E-7 Sr89 2E-6 SE-16 3E-10 2E-6 3E-10 Sr90 2E-18 3E-ll 7E-8 -

Nb95 9E-18 3E-9 3E-9 Zr95 SE-8 5E-18 lE-9 SE-9 3E-8 Mo99 2E-16 7E-9 3E-8 Rul03 2E-7 7E-18 3E-9 2E-9 3E-8 Agl10m 2E-21 3E-10 7E-12 Sbl24 4E-ll 8E-18 7E-10 lE-8 lE-7 Csl34 2E-17 4E-10 SE-8 3E-7 Csl36 9E-18 6E-9 2E-9 2E-7 Csl37 9E-17 5E-10 2E-7 4E-7 Bal40 8E-16 lE-9 8E-7 lE-6 Cel41 8E-16 SE-9 2E-7 4E-7 Total 3E-3 2E0 2 (1) Concentrations have been adjusted to reflect the fact

,4 that the releases presented in Table 3.5-22 are based on a 50,000 uCi/sec noble gas offgas rate (at 30 minute delay).

The concentrations in this table are based on (A) a 500,000 uCi/sec rate.

O M P83 122/01-17 it ' Amendment 2 4 'g ]

HCGS OLER 12/83 3

(V , TABLE 3.5-26 (Continued) (Page 4 of 7)

IKIE SIMIE UTIT TUR0: TEBM hTIH MJLTIPLIER T 1.0 1.0 I 131 2.4E-1 I 133 3.2E00 H3 5.251 C 14 9.5E0 AR41 1.5ED1 .

KR85M 2.9ED1 KR85 2.2ED2 KB87 6.3ED1 KR88 9.50El KR89 6.lE02 XE13]M 6.7E00 XE133 1.8E03 XE135M 9.9E02 XE135 1.2ED3 XE137 1.3E03 XE138 1.0ED3 CRS1 9.2E-4 IE54 6.5Fr4 CD58 1.0E-3 EE59 1.1E-4 l CD60 1.lE-3

(

(')N ZN65 SB89 6.1E-3 6.0E-3 SR90 2.0E-5 1895 1.lE-4 ZR95 5.8E-5 M099 2.7E-3 1U103 9.2E-5 l /G11CM 2.4E-8 I

SB124 1.0Fr4 G134 2.7E-4 G136 1.lFr4 G137 1.lFe3 IaA140 1.0E-2 CE141 1.0E-2 l

HCES GROUND LEVEL X/0 (NORMAL) - HOPE CREEK GROUND LEVEL REIFASE 6

N 2.369E-06 5.078E-07 2.400E-07 1.477E-07 1.046E-07 5.162E-08 1.962E-08 9.584E-09 5.971E-09 4.191E-09 NNE 2.018E-06 4.295E-07 2.032E-07 1.246E-07 8.827E-08 4.355E-08 1 2 1.656E-08 8.088E-09 5.039E-09 3.538E-09 NE 2.004E-06 4.252E-07 2.010E-07 1.235E-07 8.761E-08 4.335E-08 1.655E-08 8.107E-09 5.062E-09 3.559E-09 ENE 1.465E-06 3.123E-07 1.480E-07 9.078E-08 6.432E-08 3.175E-08 1.208E-08 5.900E-09 3.677E-09 2.581E-09

) E 1.349E-06 2.890E-07 1.373E-07 8.462E-08 6.016E-08 2.990E-08 i,147E-08 5.639E-09 3.528E-09 2.484E-09 l M N3122/01-18 Ain diutt 2 l

l

HCGS OLER 12/83 O TABLE 3.5-26 (Continued) (Page 5 of 7)

ESE 1.263E-06 2.664E-07'1.275E-07 7.937E-08 5.685E-08 2.867F-08 1.121E-08 5.581E-09 3.519E-09 2.493E-09 SE 2.528E-06 5.103E-07 2.417E-07 1.514E-07 1.084E-07 5.544F-08 2.200E-08 1.108E-08 7.047E-09 5.821E-09 SSE 2.086E-06 4.332E-07 2.032E-07 1.247E-07 8.840E-08 4.374F-08 1.672E-08 8.215E-09 5.140E-09 3.620E-09 S 2.052E-06 4.339E-07 2.033E-07 1.242E-07 8.770E-08 4.305E-08 1.627E-08 7.926E-09 4.931E-09 3.458E-09 SSW 1.797E-06 3.853E-07 1.812E-07 1.107E-07 7.824E-08 3.844E-08 1.454E-06 7.078E-09 4.402E-09 3.087E-09 SW 2.033E-06 4.323E-07 2.043E-07 1.255E-07 8.905E-08 4.409F-08 i 1.685E-08 8.264E-09 5.164E-09 3.633E-09 WSW 1.711E-06 3.631E-07 1.709E-07 1.045E-07 7.389E-08 3.634E-08 1.377E-08 6.715E-09 4.181E-09 2.934E-09 W 1.963E-06 4.148E-07 1.936E-07 1.180E-07 8.321E-08 4.073E-08 1.535E-08 7.465E-09 4.640E-09 3.253E-09 WNW 2.272E-06 4.841E-07 2.264E-07 1.376E-07 9.682E-08 4.718E-08 1.766E-08 8.541E-09 5.289E-09 3.697E-09 HW 2.652E-06 5.725E-07 2.677E-07 1.625E-07 1.142E-07 5.556F.-08 2.073E-08 1.000E-08 6.185E-09 4.318E.-09 NNW 1.792t-06 3.848E-07 1.793E-07 1 087E-07 7.632E-08 3.703E-08 1.378E-08 6.639E-09 4.101E-09 2.861E-09 O'- HCGS GROUND LEVEL X/0 (NORMAL) - IN PLACE OF DECAYED X/O 6 -

1 2 N 2.349E-06 5.078E-07 2.403E-07 1.477E-07 1.046E-07 5.162E-08 1.962E-08 9.584E-09 5.971E-09 4.191E-09 NNE 2.018E-06 4.295E-07 2.032E-07 1.246E-07 8.827E-08 4.355E-08 1.656E-08 8.088E-09 5.039E-09 3.538E-09 NE 2.004E-06 4.252E-07 2.010E-07 1.235E-07 8.761E-08 4.335E-08

.1.655E-08 8.107E-09 5.062E-09 3 559E-09 ENE 1.465E-06 3.123E-07 1.480E-07 9.078E-08 6.432E-08 3.175E-08 1.208E-08 5.900E-09 3.677E-09 2 581E-09 E 1.349E-06 2.890E-07 1.373E-07 8.462E-08 6.016E-08 2.990E-08 1 147E-08 5.639E-09 3.528E-09 2.484E-09 ESE 1.263E-06 2.664E-07 1.275E-07 7.937E-08 5.685E-08 2.867E-08 1.121E-08 5.581E-09 3.519E-09 2.493E-09 SE 2.528E-06 5.103E-07 2.417E-07 1.514E-07 1.084E-07 5.544E-08 2.200E-08 1.108E-08 7.047E-09 5.821E-09 SSE 2.086E-06 4.332E-07 2.032E-07 1.247E-07 8.840E-08 4.374E-08 1.672E-08 8.215E-09 5.140E-09 3.620E-09 S 2.052E-06 4.339E-07 2.033E-07 1.242E-07 8.770E-08 4.305E-08 1.627E-08 7.926E-09 4.931E-09 3.458E-09 SSW 1.797E-06 3.853E-07 1.812E-07 1.107E-07 7.824E-08 3.044E-08 1 454.E-08 7.078E-09 4.402E-09 3.087E-09 SW 2.033E-06 4.323E-07 2.043E-07 1.255E-07 8.905E-08 4.409E-08 1.685E-08 8.264E-09 5.164E-09 3.633E-09 WSW 1.711E-06 3.631E-07 1.709E-07 1.045E-07 7.389E-08 3.634E-08 1.377E-08 6.715E-09 4.181E-09 2.934E-09 l

M IE3 122/01-19 Aindoit 2

HCGS OLER 12/83 O TABLE 3.5-26 (Continued) (Page 6 of 7)

(_,/

W 1.963E-06 4.148E-07 1.936E-07 1.180E-07 8.321E-08 4.073E-08 1.535E-08 7.465E-09 4.640E-09 3.253E-09 WNW 2.272E-06 4.841E-07 2.264E-07 1.376E-07 9.682E-08 4.718E-08 1.766E-08 8.541E-09 5.289E-09 3.697E-09 NW 2.652E-06 5.725E-07 2.677E-07 1.625E-07 1.142E-07 5.556E-08 2.073E-08 1.000E-08 6.185E-09 4.318E-09 NNW 1.792E-06 3.848E-07 1.793E-07 1.087E-07 7.632E-08 3.703E-08 1.378E-08 6.639E-09 4.101E 09 2.861E-09 HCGS GROUND LEVEL X/0 (DEPLETED) - HOPE CREEK GROUND LEVEL RELEASE 6

N .2.150E-06 4.196E-07 1.893E-07 1.124E-07 7.772E-08 3.557E-08 1.150E-08 4.982E-09 2.868E-09 1.898E-09 NNE 1.829E-06 3.549E-07 1.590E-07 9.486E-08 6.558E-08 3.001E-08 9.700E-09 4.204E-09 2.421E-09 1.603E-09 NE 1.818E-06 3.513E-07 1.581E-07 9.402E-08'6.508E-08 2.986E-08 9.692E-09 4.214E-09 2.432E-09 1.612E-09 ENE 1.329E-06 2.580E-07 1.164E-07 6.910E-08 4.778E-08 2.187E-08 7.073E-09 3.067E-09 1.766E-09 1.169E-09 E 1.224E-06 2.388E-07 1.080E-07 6.441E-08 4.469E-08 2.060E-08 6.721E-09 2.931E-09 1.695E-09 1.125E-09 ESE 1.146E-06 2.202E-07 1.003E-07 6.041E-08 4.223E-08 1.975E-08 1 2 6.566E-09 2.901E-09 1.691E-09 1.129E-09

('"s SE 2.294E-06 4.217E-07 1.901E-07 1.152E-07 8.087E-08 3.820E-08

() 1.289E-08 5.762E-09 3.383E-09 2.278E-09 SSE 1.892E-06 3.580E-07 1.598E-07 9.494E-08 6.567E-08 3.013E-08

'9.797E-09 4.270E-09 2.469E-09 1.640E-09 S 1.862E-06 3.585E-07 1.599E-07 9.454E-08 6.515E-08 2.966E-08 9.532E-09 4.120E-09 2.369E-09 1.566E-09 SSW 1.630E-06 3.184E-07 1 425E-07 8.429E-08 5.812E-08 2.648E-08 8.515E-09 3.679E-09 2.115E-09 1.398E-09 SW 1.844E-06 3.572E-07 1.606E-07 9,555E-08 6.615E-08 3.038E-08 9.870E-09 4.296E-09 2.481E-09 1.646E-09 .

l WSW 1.552E-06 3.000E-07 1.344E-07 7.956E-08 5.489E-08 2.304E-08 8.065E-09 3.490E-09 2.009E-09 1.329E-09 W 1.781E-06 3.427E-07 1.522E-07 8.963E-08 6.181E-08 2.806E-08 8.992E-09 3.880E-09 2.229E-09 1.473E-09 WNW 2.062E-06 4.000E-07 1.780E-07 1.048E-07 7.193E-08 3.251E-08 l

1.035E-08 4.439E-09 2.541E-09 1.675E-09 NW 2.406E-06 4.731E-07 2.105E-07 1.237E-07 8.487E-08 3.828E-08 1.215E-08 5.200E-09 2.971E-09 1.956E-09 NNW 1.626E-06 3.180E-07 1.410E-07 8.275E-08 5.670E-08 2.551E-08 8.074E-09 3.451E-09 1.970E-09 1.296E-09 HCGS D/G CORRECTED FOR DEPLETION - HOPE CREEK GROUND LEVEL RELEASE 6

N 1.305E-08 2.099E-09 8.630E-10 4.807E-10 3.104E-10 1.277E-10 3.823E-11 1.560E-11 8.457E-12 5.352E-12 NNE 1.017E-08 1.636E-09 6.726E-10 3.746E-10 2.420E-10 9.950E-11 2.980E-11 1.216E-1'1 6.591E-12 4.172E-12 I

v M P83 122/01-20 Arudiet 2

8 -

HCGS OLER 12/83

_ TABLE 3.5-26 (Continued) (Page 7 of 7)

NE 9.254E-09 1.489E-09 6.122E-10 3.409E-10 2.202E-10 9.055E-11 2.712E-11 1.107E-11 5.998E-12 3.796E-12 -

ENE 5.999E-09 9.649E-10 3.968E-10 2.210E-10 1.427E-10 5.870E-11 1.758E-11 7.173E-12 3.888E-12 2.461E-12 E 5.325E-09 8.566E-10 3.523E-10 1.96?E-10 1.267E-10 5.711E-11 1.561E-11 6.368E-12 3.452E-12 2.185E-12 ESE 4.948E-09 7.960E-10 3.273E-10 1.823E-10 1.177E-10 4.842E-11 1.450E-11 5.917E-12 3.207E-12 2.030E-12 SE 1.610E-08 2.590E-09 1.065E-09 5.932E-10 3.831E-10 1.576E-10 4 718E-11 1.925E-11 1.044E-11 6.605E-12 SSE 1.303E-08 2.095E-09 8.617E-10 4.799E-10 3.100E-10 1.275E-10 3.817E-11 1.558E-11 8.444E-12 5.344E-12 S 1.228E-08 1.976E-09 8.125E-10 4.525E-10 2.973E-10 1.202E-10 3.599E-11 1.469E-11 7.962E-12 5 039E-12 SSW 1.111E-08 1.787E-09 7.351E-10 4.094E-10 2.644E-10 1.087E-10 3.256E-11 1.329E-11 7.203E-12 4.559E-12 SW 1.136E-08 1.828E-09 7.517E-10 4.187E-10 2.704E-10 1.112E-10 1 2 3.330E-11 1.359E-11 7.366E-12 4.662E-12 WSW 1.095E-08 1.762E-09 7.245E-10 4.035E-10 2.606E-10 1.072E-10

- 3.209E-11 1.310E-11 7.099E-12 4.493E-12 W 1.482E-08 2.385E-09 9.807E-10 5.462E-10 3.528E-10 1.451E-10

/)> WNW 4.344E-11 1.773E-11 9.609E-12 6.082E-12 1.815E-08 2.919E-09 1.200E-09 6.686E-10 4.318E-10 1.776E-10 5.318E-11 2.170E-11 1.176E-11 7.445E-12 NW 2.215E-08 3.564E-09 1.466E-09 8.162E-10 5.272E-10 2.168E-10 6.492E-11 2.649E-11 1.436E-11 9.089E-12 NNW 1.218E-08 1.959E-09 8.055E-10 4.486E-10 2.898E-10 1.192E-10 3.569E-11 1.456E-11 7.893E-12 4.996E-12 1 DAIRY FARM 41 13 4.9 7.389E-08 7.389E-08 5.444E-08 3.042E-10 1SECOND SUN 8 0.5 2.086E-06 2.086E-06 1.892E-06 1.303E-08 1VEG PLOT 41 15 3.5 1.625E-07 1.625E-07 1.237E-07 8.162E-10 1 MEAT COW #1 13 4.0 9.804E-08 9.804E-08 7.366E-08 4.330E-10 1 MEAT COW 42 14 4.0 1.142E-07 1.142E-07 8.581E-08 5.300E-10 ,

O

" DB3122/01-21 Are&e A. 2

L HCGS OLER 8/83 p 3.6.4 MAKEUP DEMINERALIZERS V Two trains of ion exchange demineralizers satisfy the s'ta-tion's high purity makeup water requirements, as was planned at the construction permit stage.

The two ' trains are parallel, each sized to' produce 570 liters per minute (150 gallons per minute) of demineralized water. A train consists of one strong acid cation vessel, one vacuum degasifier (common .to both trains), one strong base anion ves-

' sel and one mixed bed vessel. Each cation / anion train pro-duces 820 400 liters (217,300 gallons) of demineralized water between regenerations, while each mixed bed produces 3,780,000 liters (999,000 gallons) of demineralized water between regen-erations. Each demineralizer train normally requires regener-ation once every three days, except for the mixed beds, which are normally regenerated once every 15 days.

A't the construction permit stage it was estimated that daily regeneration of each train would require 240 kilograms (520 pounds) of 6 6* Baume ' sulfuric acid and 140 kilograms (300 pounds) of sodium hydroxide. Cancellation of Unit 2 and the revised regeneration scheme detailed above result in the following chemical usage per regeneration:

() Cation / anion train 60* Be' H2SO4 332 kg NaOH 139 kg 732 lb 307 lb Mixed bed 65 kg 65 kg 144 lb 144 lb Demineralizer regenerant effluent is stored in one 190,000-liter (50,000-gallon) capacity tank prior to discharge to the oily water and low volume wastewater system.

3.6.5 AUXILIARY BOILERS The station is equipped with three auxiliary boilers to pro-vide building heating, process testing steam and auxiliary steam to the turbine building. The boiler feedwater is treated with ammonia to maintain a pH in the range of 8.5 to 9.0. Daily ammonia consumption is anticipa ted to be approxi-mately 0.5 kilogram per day (1.1 pounds per day) . Hydrazine, a dissolved oxygen scavenger, is also used to treat the feed-water. A daily consumption of approximately 0.8 kilogram per day (1.8 pounds per day) is anticipated. The chemical feed systems for each solution are identical; they consist of a 190-liter (50-gallon) tank and two 14.4 liter per hour (3.8 gallon per hour) chemical feed pumps.

}

M P8 2 109/06 3 -mlp ^"*"d**"D 1 3.6-3

6 HCGS OLER 12/83 A single atmospheric blowdown tank is provided for the con-tinuous blowdown of the three boilers. During normal opera-tion, one boiler operates, while one remains in a standby mode; normal operation results in an average blowdown of 32,200 liter per day (8,500 gallons per day). An equivalent volume of cooling " quench" water is added to the auxiliary 2 boiler blowdown and is supplied by on-site production wells. During plant start-up, a maximum of two boilers operate; the resulting blowdown is expected to be 128 liters per minute'(34 gallons per minute). Composition of the blowdown is expected to be as follows:

Maximum Parameter Daily Average Anticipated TSS (mg/1) <30 100 Oil and grease (mg/1) <10 20 2

. Copper, total-(mg/1) <0.2 0,2 Iron, total (mg/1) <l.0 1.0 The auxiliary boiler blowdcwn discharges to the oily water treatment system.

2 3.6.6 OILY WATER WASTEWATER SYSTEM The oily water collection system is designed to encompass the following waste streams:

O

a. Turbine building emergency sumps

b. Switchyard and transformer drains

c. Auxiliary boiler blowdown, blowdown quench and drains 2

d. Circulating water chemical storage and water treatment

e. Diesel generator and control room drains During the construction permit stage, PSE&G planned to con-struct and operate a treatment facility to accommodate all i these wastes. Publication of revised effluent limitations l

(Tab 3e 5.1.2) on November 19, 1982, prompted PSE&G to re-

! evaluate the system along with several alternatives. PSE&G 2

selected treatment of potentially oily water in an API type i

separator and transportation of low volume waste (demin-

.eralizer regenerant wastes) for treatment off-site. The system is described in Section 5.3.1.1.

I

! 3.6.7 METhL CLEANING WASTES l

During the start-up process, various HCGS systems are flushed to insure their integrity. Well water followed by demineralized water comprise the only flushing agents.

These wastes accumulate in a lined 4.9-million liter (1.3-million gallon) capacity surface impoundment to allow par-ticulate settlement.Upon verification that the contents meet the NJPDES and the DRBC effluent limitations, the water is discharged to the Delaware River.

M P83 123/15-cag 3.6-4 Amendment 2 l

w HCGS OLER 12/83 TABLE OF CONTENTS (Continued)

Page Chapter Title Number 14 REFERENCES APPENDICES Appendix A - Thermal Modeling Methodology. . . A-1 Appendix B - ............................... (Not Used)

Appendix C - Class 9 Consequence Analysis... C-1 OUESTIONS E-i LIST OF EFFECTIVE PAGES EP-i 2 M P83 BS/17 1-gs iv Amendment 2

1 HCGS OLER 12/83 CONTENTS (Continued)

Page Number 5.2 RADIOLOGICAL IMPACT FROM ROUTINE OPERATION (Cont'd) 5.2.3 Radiological Impact to Biota other than Man....................................... 5.2-4 5.2.4 Dose Rate Estimates for Man................ 5.2-5 5.2.5 Summary of Annual Radiation Doses.......... 5.2-6 5.3 EFFECTS OF CHEMICAL OR BIOCIDE DISCHARGES......... 5.3-1 5.3.1 Surface Water.............................. 5.3-1 5.3.1.1 Oily Water............................... 5.3-1 2 5.3.1.2 Cooling Tower Blowdown................... 5. 3-1 (a) l l

5.4 EFFECTS OF SANITARY UASTE DISCHARGES.............. 5.4-1 l l

5.5 EFFECTS OF OPERATION AND MAINTENANCE OF THE TRANSMISSION SYSTEMS............................. 5.5-1 5.5.1 Hope Creek - New Freedom 500 Kilovolt Transmission Line......................... 5.5-1 G 5.5.2 Hope Creek - Keeney 500 Kilovolt Transmission Line......................... 5.5-1 5.5.3 Hope Creek - Salem Transmission Line....... 5.5-1 5.5.4 Salem - Deans 500 Kilovolt Transmission Line (Portion from Salem - New Freedom.... 5.5-2 5.5.4a Salem - Deans 500 Kilovolt Transmission Line 1 (Portion From Tower 42/3 to Tower 2/1 on the New Freedom - Deans Line ) . . . . . . . . . . . . . . . . . 5.5-7 5.6 OTHER EFFECTS..................................... 5.6-1 5.6.1 Historic Resources......................... 5.6-1 5.6.2 Sound Levels............................... 5.6-1 5.6.3 Air Quality................................ 5.6-2 5.6.4 Groundwater Effects........................ 5.6-2 5.6.5 Flood Plain Effects........................ 5.6-2 5.7 RESOURCES COMMITTED DURING OPERATION.............. 5.7-1 5.7.1 Materials Invo1ved......................... 5.7-1 5.7.2 Water and Air Resource Impacts............. 5.7-2 5.7.3 Land Resource Impacts...................... 5.7-2 5.7.4 Environmental Resource Impacts............. 5.7-3 M P83 91/24 1-df 5-ii Amendment 2

HCGS OLER 12/83 FIGURES (Continued)

O Figure Number Title 5.1-16 MONTHLY ESTIMATED NUMBER AND WEIGHT OF IMPINGED SPOT, SALEM SFS - 1977 5.1-17 MONTHLY ESTIMATED NUMBER AND WEIGHT OF IMPINGED SPOT, SALEM SWS - 1978 5.1-18 AVERAGE SALT DEPOSITION PATE lE290.3 5.2-1 PATHWAYS TO BIOTA OTHER THAN MAN 5.2-2 PATHWAYS TO MAN 5.2-3 FLARED ESTUARY 5.3-1 OILY WATER, LOW VOLUME WASTEWATER FLOW DIAGRAM lE291.17 O

b

HCGS OLER 12/83 O

(j TABLE 5.2-2 ANNUAL !VOCIMth! INDIVIDUAL DOSE (Dft1I'IMENIS DJE 'ID GASEOUS AND LIQUID EFFUJENTS (mRen unless noted)

RADIOIODINE AND PARTICULATES IN GASDOUS EFFLUENIS

'IUPAL HIGHEST IOCATICE PA'IEWAY_ DODY ORGAN 'IHYROID Nearest (1) Ground deposit 1.27E-3 1.49E-3 (skin) 1.27E-3 farm residence Inhalation 4.64E-4 7.38E-2 (thyroid) 7.38E-2 milk cow and (teen-total body) meat animal (child-thyroid) at 3.5 miles Milk (infant) 3.64E-2 7.69E-1 (thyrcid) 7.69E-1 2 E470.4 IM Vegetables (child) 2.38E-2 1.17E-1 (bone) 1.16E-1 Meat (child) 5.41E-3 2.63E-2 (bone) 2.10E-2

'ICIAIS LIQUID EFFLUENTS

'IUrAL BODY BCNE LIVER Nearest fish Fish ingestion 1.66E-2 2.89E-1 2.75E-2 at outfall (adult) (child) (teen) 1 (3

NOBLE GASES IN GASEDUS EFFLUENIS

'IUrAL BODY SKIN GAMMA AIR DOSE (mrads) BETA AIR (mrads)

Nearest 1.03E-1 2.79E-1 1.55E-1 1.79E-1 1 2 residence 3.5 miles NW (1) " Nearest" refers to the location where the highest radiation dose to an individual fran all applicable pathways has been estimated.

M P83 122/01-22 Amendnent 2 I

_ - _ - _ - ____ _ 1

HCGS OLER 12/83

'T TABLE 5.2-3

[Q APPENDIX I ANNUAL MAXIMUM INDIVIDUAL AND POPULATION DOSE COMMITM.2TfS(1)

APPENDIX I CALCULATED DESIGN OBJECTIVES DOSES Liquid Effluents Dose to total body from 3 mrem 0.026 mrem all pathways '

1 Dose to any organ from 10 mrem 0.372 mrem all pathways (bone)

Noble Gas Effluents (at nearest actual resident)

Gamma dose in air 10 mrad 0.155 mrad Beta dose in air 20 mrad 0.179 mrad 1 2 Dose to total body of an 5 mrem 0.103 mrem individual Dose to skin of an 15 mrem 0.279 mrem l1 l2 individual Radiciodines and Particulates(2)

Dose to any organ from all 15 mrem 0.981 mrem

(\

x_- pathways (thyroid) l1 l2 POPULATION DOSES WITHIN 80 km (50 mi)

'IOTAL BODY THYROID Annual Dose Natural Radiation Background (3) 490000 man-rem Liquid Effluents 0.252 man-rem 0.742 man-rem Noble Gas Effluents 15.3 man-rem 15.3 man-rem Radioiodines and Particulates 1.04 man-rem 15.7 man-rem 1 2 (1) Appendix I Design Objectives from Sections II.A, II.B, II.C and II.D of, Appendix I,10 CFR Part 50, considers dose to maximum individual and population per reactor unit. From Federal Register, 40, p.19442, May 5,1975.

(2) Carbon-14 and tritium have been added to this category.

(3) " Natural Radiation Exposure in the United States," U.S.

Environmental Protection Agency, ORP-SID-72-1 (June, 1972);

using the average terrestrial plus cosmic background (82 mrem per year for the Hope Creek area) and year 2010 projected

/N population of 5970000.

\--]

M P83 122/01-23 Amendment 2

HCGS OLER 12/83 O

Q TABLE 5.2-4 ANNUAL 'IOTAL-BODY U.S. POPULATION DOSE COMMITMENT U.S. POPULATION-DOSE COMMITMENT CATEGORY (man-Rem)

Natural background radiation (l) 28,400,000 (man-rem /yr)

General Public Gas and particulates 34.6 1

I2 Liquid effluents 1.53 Transportation of fuel 3 and waste (1) Using the average U.S. background dose (102 mrem per year) and year 2010 projected U.S. population from "Popula-tion Estimates and Projections," Series II, U.S. Dept. of Commerce, Bureau of the Census, Series P-25, No. 541, February, 1975.

L e

bD M P83 122/01-24 Amendment 2

_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ __. )

HCGS OLER 12/03 m

I \ 5.3 EFFECTS OF CHEMICAL OR BIOCIDE DISCHARGES d

5.3.1 SURFACE WATER HCGS uses the Delaware River to assimilate liquid discharges from the chemical and biocide systems described in Section 3.6. The DRBC and NJDEP require that specific stream quality objectives for Zone 5 of the Delaware be met within 1100 meters (3,500 feet) of the discharge (mixing zone). Table 5.1.1 provides these water quality objectives.

PSE&G controls station discharges to meet these objectives and the discharge limitations imposed by the EPA and DRBC (see Section 5.1.1). A description of chemical and biocide dis-charge effects on the Delaware River follows:

5.3.1.1 Oily Wate'r l2 At the construction permit stage, PSE&G planned a chemical waste treatment system. Publication of revised ef fluent limi-tations (Table 5.1-2) on November 19, 1982, prompted PSE&G to evaluate treatment alternatives. Potentially oily water, including auxiliary boiler blowdown, is now treated at HCGS ,

and low volume wastewater is collected and trucked for treat-ment at Salem Generating Station.

[ ) Low volume waste neutralization is accomplished in the 190,000

\~ / liter (50,000 gal) waste tank, if necessary, to ensure that shipments are in the pH range of two through twelve, prior to removal from HCGS ( see Figure 5.3-1) .

Figure 5.3-1 also depicts the flow of potentially oily wastes which are treated and discharged at HCGS. As shown, water that may be contaminated with oil is collected from various points onsite and delivered to either of two lif t stations (lB or 1C). 2 Potentially oily water collected at lift station 1B ranges in flow from 0 - 390,000 (0 - 100,000 gallons per day), depending on the presence of rainwater and/or oil spills. Pollutants encountered here can include oil and suspended solids, and iron and copper at low concentrations. Water collected at lift station 1C emanates from sources whose flows are inter-mittent or rare, depending on rainfall or spills. Only auxiliary boiler blowdown and blowdown quench water provide continuous flow. Both blowdown and quench water each range from 32,200 (average) to 98,400 (maximum) liters per day (8,500 (average) to 26,000 (maximum) gallons per day).

Typical contaminants found in both sources include suspended solids, iron, and copper at levels acceptable for direct dis-charge without special treatment.

I ws' M P83 91/24 2-df 5.3-1 Amendment 2

HCGS OLER 12/83 The lif t stations pump the waste to a 1900 liter per minute (500 gallon per minute) American Petroleum Institute (API) type oil separator. Average flow through this system is approximately 121,000 liters per day (32,000 gallons rar day).

The API separators are equipped with a surge chamber, oil skimmer and 56,800 liter (15,000 gallon) waste oil holding tank. Any sludges removed from the tank are stored in a 2,000 gallon oily sludge holding tank. These sludges are disposed of in accordance with current Resource Conservation 2 and Recovery Act (RCRA) and NJDEP hazardous waste regulations.

The API separator's treated effluent is monitored to ensure compliance with the station's NJPDES permit and current DRBC regulations. This ef fluent discharges into the cooling tower blowdown line and eventually to the Delaware River.

This level of treatment, although accomplished differently, is consistent with CP stage plans. Only the wastes from a single unit are now involved, however.

5.3.1.2 Cooling Tower Blowdown As Section 3.4 describes, a natural draft cooling tower is the major feature of the station's heat dissipation system. The service water system obtains make-up water from the Delaware River to replace evaporative losses and cooling tower blowdown.

Make-up water requires treatment with chlorine (see Section 3.6.1) prior to its use in both service and circulating water systems in order to control biofouling. Similarly, sulfuric acid prevents deposition of calcium carbonate (scaling) when added to circulating water.

The EPA regulates the concentration of residual chlorine (bio-cide) in cooling tower blowdown (see Table 5.1-2). Free available chlorine (FAC) in cooling tower blowdown may not exceed 0.5 milligram per liter as a one-day maximum or 0.2 milligram per liter as a 30-day average. Additionally, daily chlorination is limited to two hours each day (see Table 5.1-2).

M P83 91/24 3-df 5.3-1(a) Amendment 2

HCGS OLER f )' Cooling tower blowdown flow averages approximately 80,900 liters per minute (21,360 gallons per minute) over an average month at full power operation.

In order to meet make-up water chlorine demand and maintain an ef fective' FAC residual in the service and circulating water systems, HCGS utilizes a maximum of 145,600 kilograms (390,000 pounds) of chlorine (as Cl 2 ) annually (400 kilograms (1,100 pounds)_per day).

The release of FAC should not have a significant impact on Delaware River water quality. The chlorine, which is added as sodium hypochlorite~, exists in the dissolved state as hypo-chlorous acid (HOCl) and hypochlorite ion (OCl-). These species disperse, and are diluted, as in the near field of the ,

thermal. plume (see Section 5.1.2). Dilution alone of the chlorinated effluent assures a minimal effect on Delaware River water quality. If the station releases 0.5 milligram per liter of FAC, under conditions of least dilution (August,

. during ebb tide on the river bottom), the FAC concentration at the end of the 1070 meter (3,500 foot) mixing zone would be less than 0.01 milligram per liter.

It should also be considered that the EPA limits to two hours the time during which any measurable chlorine res idual is

( allowed. Additionally, dilution does not account for ambient l river chlorine demand, which further reduces chlorine levels.

! It can be seen that both regulation and physical f actors l (dilution, chlorine demand, etc.) protect river quality.

If all chlorine is converted (reduced) to Cl , the river load-ing of 0.2 milligram per liter of the ion within the plume is

, negligible compared to ambient (median) river chloride levels (3,725 milligrams per liter) . If it is assumed that the cool-i ing tower creates two cycles of river water concentration, the l combination of reduced chlorine and concentrated chlorides would generate a chloride concentration of only 3,982 milli-grams per liter at the boundary of the plume (during the period of least dilution) .

The use of sulfuric acid to control scaling should not affect river water quality. HCGS utilizes an average of 1,550 kilo-grams (4,150 pounds) of sulfate daily and discharges a concen-tration of approximately 1,029 milligrams per liter (assuming doubling 'of ambient river water sulfates by cooling tower).

At the boundary of the plume during the period of least dilu-tion, the sulfate concentration would be 543 milligrams pe r -

, liter (ambient river level is approximately 507 milligrams per l liter).

O M P82 134/07-11 5.3-2 i

i e

HCGS OLER In like fashion, the other chemical constituents of cooling tower blowdown, as Table 3.4-2 describes, disperse and are diluted within the plume to levels well within stream quality standards.

O M P82 134/07-11 5.3-3

h _

COOLING TOWER BLOWDOWN MAKE-UP DEMINERALIZER REGENERANT WASTE WASTE TANK 50,000 GAL,

,AU.X. BOILER OILY DRAIN , _7 { TRUCK LOADING STATION AUX. BOILER BLOWDOWN l WASTE PUMP AUX. BOILER QUENCH WTR. TREATMENT BLDG. DRAINS l I

SODIUM HYPOCHLORITE TANKS DIKE DRAIN SULFURIC ACID TANK DIKE DRAIN - ,, 15,000 GAL.

l CIRC. WTR. CHEMICAL CONTROL BLDG.

l CIRC. WTR. PUMP STRUCT./ ELEC. SWGEAR BLDG.

CIRC. WTR. CHLORINE ANALYZER DRAIN ont FUEL OIL DAY TANK DIKE DRAIN 7I SEPARATOR n FIREWATER / WELLWATER TANK DRAIN  %/

FIREWATEP PUMP HOUSE DRAIN MONITORING STATION DIESEL GENERATOR / CONTROL RM. DRAINS SERV. WTR. CHLORINE ANALYZER DRAIN _

E)

MAIN TRANSFORMERS DIKE DRAINS LIFT TRANSF. DlKE DRAINS '

STATION 1C EMER. SUMP DISCHARGE FROM TURD. DLDO.

OIL SLUDGE TANK SWICHYARD DIKE DRAIN 2,000 GAL.

TRANSF. AT COOLING TOWER RECYCLE PUMP SERV. WTR. HYPOCHLORITE PUMP BLDG. DRAIN DIESEL OIL TRUCK AND BARGE DELIVERY h

LIFT STATION 10 i

TO RIVER FUEL OIL PUMP HOUSE DRAIN FUEL OIL STORAGE TANK DIKE DRAIN ?d HOPE CREEK GENERATING STATION ENVIRONMENTAL REPORT SERV. WTR. INTAKE STRUCTURE PUMP DRAINS OPERATING LICENSE STAGE CERV. WTR. HYPOCHLORITE TANK DIKE DRAIN 74l OILY WATER, LOW VOLUME WASTE WATER TO RIVER FLOW DIAGRAM FIGURE 5.3 - 1 AMEND. 2

HCGS OLER 12/83 O\

V 10.4 CHEMICAL UASTE TREATMENT At the construction permit stage, PSE&G reviewed four alter-native chemical waste treatment systems, and selected one:

pH adjustment and precipitation followed by discharge to the river via the cooling tower blowdown line. Also addressed at the construction permit stage were scale prevention and corrosion control methods.

In light of revised USEPA effluent guidelines and elimina-tion of Unit 2, PSE&G reassessed chemical waste treatment alternatives and elect ed to treat all potentially oily 2 wastes on-site in an API type separator , while shipping low volume wastes off-site for treatment. Section 5.3.1.1 dis-cusses this topic.

M P83 ll6/14-df 10.4-1 Amendment 2 O

l

,1 HCGS OLER 12/83

! \

'v' 13.1 CHLORINATION EFFECTS STUDY

" Prior to initiation of power operation the Applicants shall conduct a study of proposed chlorination methods to assure that the use of these methods will result in ac-ceptable chlorine residuals in the station effluent under the full range of conditions anticipated during operation of the station. Acceptable chlorine residuals currently recommended by the EPA for warm f'resh water are less than 0.2 mg/ liter for intermittent discharge not to exceed 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> per day or less than 0.01 mg/ liter for continuous discharge. The study shall include an evaluation of the effects of variable ammonia and organic nitrogen concen-trations, chlorine demand, temperature and pH on the con-centrations of both free and combined chlorine residuals in the treated water. Alternative methods of reducing chlorine residuals shall also be investigated and these are to include, but not be limited to, optimizing chlo-rine dosage and time of dosage, sequential treatment of sections of each condenser, blowdown scheduling, and ad-wate r. "

PSE&G has studied chlorination and related technologies es including work in conjunction with the Electric Power Research

( ) Institute and the U.S. Department of Energy, with the goal of optimizing biocide use and monitoring techniques at all its generating stations, including HCGS. This work is continu-ing. Reports and publications resulting from efforts to date a re listed as Re ferences 13.1-1 through 13.1-10. l2 These studies were conc 'd at a number of locations, provid-ing a broad base of inG  :-ion not necessarily limited by site-specific considerai. '

. These studies addressed three major areas of interests

a. Analytical Methods - Re ferences 13.1-1 through 13.1-3 are l2 representative ot efforts made to evaluate analytical methods and instrumentation for monitoring chlorine re-siduals in power plant effluents under actual in-plant conditions.

b. Chlorine Optimization - All the listed references include results which are related to minimizing the amount of chlorine released to the environment. Monitoring capa-bilities (Re ferences 13.1-1 through 13.1-3) are necessary l 2 to insure compliance with minimum ef fluent standards.

References 13.1-4 through 13.1-10 are results of studies aimed at comparing the performance of alternative bio-l2 cides to chlorine. To do such a comparison required

,-s optimizing the chlorination process to provide a baseline M P83 123/11 4-cag 13.1-1 Amendment 2 l

_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _a

l HCGS OLER 12/83 O

f or comparison of the alternatives. Conducted over periods of time and at various locations, the optimiza-tion studies included a representative range of water quality conditions. Optimization was achieved ( Re f e r-ences 13.1-6, 13.1-9 and 13.1-10) by determining the l2 minimum chlorine dose necessary to maintain acceptable condenser performance. In addition, environmental ef-fects were studied by exposing indigenous aquatic species to chlorinated effluents ( Re f erences 13.1-7, 13.1-8 and l2 13.1-10).

c. Alternative Methods - Several biocides, including BrCl (Reference 13.1-1) and ozone (References 13.1-6 through l2 13.1-10), have been studied as possible alternatives to chlorine. Studies continue on the utilization of ozone or dechlorination to minimize the impact of utility operations on the aquatic environment.

O M P83 123/11 5-cag 13.1-2 Amendment 2

w HCGS OLER 12/83 REFERENCES 13.1-1 C. Sengupta, G. R. Helz, J. W. Gretz, P. Higgins, J. C. Peterson, A. C. Sigleo and R. Sugam, A Survey of Chlorine Analytical Methods Suitable for the Power Industry, Report EA-929, Electric Power Research Institute, 1978.

13.1-2 R. Sugam, W. Swallow and J. Trout, Field Evaluation ot Chlorine Monitoring Techniques, Report EA-2070, Electric Power Research Institute, 1981.

13.1-3 R. Sugam, " Chlorine Analysis: Perspectives for Compliance Monitoring," in: Water Chlorination:

Environmental Impact and Health Effects, Vol. 4, Book 1, Chemistry and Water Treatment (e d. , R . L.

Jolley, R. B. Cumming, J. S. Mattice) Ann Arbor Science (1982), pp. 653-666.

13.1-4 E. C. Wackenhuth and G. Levine, An Investigation of Bromine Chloride as a Biocide in Condenser Cooling Water, Paper No. IWC 74-1, presented at 35th Annual International Water Conference, Pittsburgh, PA, 1974.

13.1-5 E. C. Wackenhuth and G. Le vine , Experience in the use of Bromine Chloride for Antifouling at Steam E291.20 Electric Generating Stations, presented at Work-shop: An Assessment of Technology and Ecological Effects of Biofouling Control Procedures at Thermal Power Plant Cooling Water Systems, Johns Hopkins University, Baltimore, MD, 1975..

13.1-6 R. Sugam, C. R. Guerra, J . L. De lMonaco, J . H.

Singletary and W. A. Sandvik, Biofouling Control with Ozone at the Bergen Generating Station, Report CS -1629, Electric Power Research Institute, 1980.

13.1-7 C. R. Guerra, R. Sugam, J. W. Meldrim, E. R.

Holmstrom and G. E. Balog, Comparative Evaluation of Effects of Oz'onated and Chlorinated Thermal Dis-charges on Estuarine and Freshwater Organisms, F inal Report, U. S. Department of Energy (1980),

125 pages.

O V M P83 12 3/11 2-cag Amendment 2

HCGS OLER 12/83 REFERENCES (Continued) 13.1-8 J. W. Meldrim, E. R. Holmstron, G. E. Balog and R.

Sugam, "A Comparative Evaluation of the Effects of Ozonated and Chlorinated Condenser Discharges on the White Perch, Morone Americana," Ozone: Science and Engineering, 3 (1981), 155-158.

13.1-9 R. Sugam, J. H. Singletary, W. A. Sandvik and C. R.

Guerra, " Condenser Biofouling Control with Ozone," E291.20 Ozone: Science and Engineering, 3 (1981),

pp.95-107.

13.1-10 R. Sugam and C,, R. Guerra, " Comparison of Chlorine and Ozone for Power Plant Cooling Water Treatment,"

Li n: Ozone Treatment of Water for Cooling Applica-tions, ed., R. G. Rice, International Ozone Associ-ation (1981), pp. 63-74.

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) M P83 12 3/11 3-cag Amendment 2 s_/

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allows only a small amount of fuel to come into contact with water on the drywell floor. Third, the amount of water on the drywell floor is relatively small and is limited to a depth of approximately two feet because of the location of the vent pipes. Fourth, for transient events, most of the water in the reactor vessel is boiled off to the suppression pool before core melt and this will not be deposited on the drywell i

floor. These considerations lead to the assignment of a neg-ligibly small value to S for transient events (TW, TC and TQUV) and a small value, 10-4, for LOCA events (AE) . .

3.3 HYDROGEN BURN OR EXPLOSION l

As far as hydrogen burns ( p) or explosions ( p') are con-cerned, their probability of occurrence is limited by the availability of oxygen. The containment is normally inerted p and is expected to remain so during operation for all but d approximately 70 hours8.101852e-4 days <br />0.0194 hours <br />1.157407e-4 weeks <br />2.6635e-5 months <br /> of the year. Hence, there is an upper limit of'about 10-2 for this probability. Hydrogen burns or hydrogen explosions are not considered further in the present work because of this low probability relative to that of Y and Y'.

3.4 OTHER CONTAINMENT FAILURE MODES The probability of all other potential containment failure modes (6 , containment isolation failure in the drywell; e ,

containment isolation failure in wetwell; (, containment l

leakage greater than 2,400 volume percent per day; 4 , reactor building isolation failure; and 6, standby gas treatment system failure) is taken to be very small relative to over-pressure.- These negligibly small release probabilities are consistent with those used in WASH-1400 and in the Brown's O

C-15 NUS CORPORATION

12/83 Ferry IREP study for the transient core melt sequences (TC, O

TW, TOUV) tha t we re found to dominate risk.

4.0 SOURCE TERM MAGNITUDES Source term magnitudes are displayed in Table C-1. Major factors controlling these source terms are as follows.

4.1 SEQUENCE TOUV-Y '

This is a sequence in which the ability to cool the core is lost and the core subsequently melts in an intact vessel and containment. The radiologically important volatile fission products I, Cs and Te are mostly released from the fuel dur-ing this phase (90%, 90% and 80%, respectively).. These melt release fractions are based on NUREG-0772 (Ref. C-13) and the SASCHA experiments (Reference C-14) and are greater than those used in WASH-1400 and in the rebaselined analysis (88%, 76% and 15%, respectively), especially the Tellurium.

It is assumed that these melt release fission products are blown through the main steam relief valves into the pool.

The pool remains subcooled throughout this sequence: a review of experimental data on pool scrubbing shows that a decontamination factor (DF) of at least 100 can be justified in this case (References C-37 through C-40). Hence, less than 1% of the melt release will pass through the pool and E450.1 be available for release to the atmosphere.

Once the core has melted, it will slump to the lower head of the vessel, which will subsequently fail. The core will fall to the concrete floor beneath and non-condensable gases will be generated by the core-concrete interactions. The buildup (REMAINDER OF PAGE IS INTENTIONALLY BLANK)

M P83 123/07 7-df C-16 Amendment 2

12/83 predicted to be about 42 million by the year 2010. This is the population within which most of the latent cancer fatal-ities would be predicted to occur. In modern industrialized Os societies, the individual risk of death due to cancer is about 2.5x10-3yr -1 This figure may be deduced by ref-erence to the Statistical Abstract of the United States. It implies that there would be about 100,000 deaths due to can-cer each year among the population in question. By con-trast, even the peak event would cause only about 1,500 deaths each year for some 30 years or so, beginning a few years after the accident (1500x30=45,000 the peak of Figure C-8).

The actual fatality of 3.3x10-Syr -1 may be put in pe r-spective by noting that an approximation of the population at risk is that within about 16 km (10 mi) of the plant, about 27,400 persons in the year 2010. Accidental f a tal-ities per year for a population of this size, based upon overall averages for the United States, are approximately 8 from motor vehicle acidents, 3 from falls, 1 from burns, and one every three years from firearms (Ref. C-24).

The individual risk of early fatality as a function of dis-tance is displayed on Figure C-10. As can be seen, these risks are all small. For comparison, the following risks of fatality per year to an indiivudal living intheUnjted States may be noted: automobile accidents, 2.2x10 yr-1 and firearms 1,2x10-S yr-1(Ref. C-24),

p/

%, The economic risk associated with offnite property could in principle be compared with property damage costs associated with alternative energy generation technologies. The use of fossil fuels--coal or oil, for example, would emit substantial (REMAINDER OF PAGE IS INTENTIONALLY BLANK)

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(_ M P83 123/07 5-df C-39 Amendment 2

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/-s\

b from Liquid Pathways After a Reactor Meltdown Accident, SAND 80-1669 (NUREG/CR-1596) Sandia National Laboratories, 1981.

C-33 U.S. Nuclear Regulatory Commission, Final Environmental Statement Related to the Operation of Palo Verde Nuclear Generating Station, Units 1, 2, and 3, (NUREG-0841), 1982.

C-34 H. W. Lewis et.al., Risk Assessment Review Group Report to the U.S. Nuclear Regulatory Commission, (NUREG/CR-0400), 1978.

C-35 Commonwealth Edison Company, Zion Probabilistic Safety Study, 1981.

C-36 I.B. Wall, P. E. McGrath, S. S. Yaniv, H. W. Church, R. M. Blond, and J. R. Wayland, Overview of the Reactor Safety Study Consequence Model, (NUREG-0340),

U.S. Nuclear Regulatory Commission, 1977.

C-37 Marble, W. J., et. al., 1982. Retention of Fission Products by BWR Suppression Pools During Severe Accidents, General Electric Company, August 1982

[} (presented at the ANS Thermal Reactor Safety Meeting

\-- held from August 30 to September 2, 1982, in Chicago, Ill.).

C-38 Rastler, D. M., 1981. Suppression Pool Scrubbing Factors for Postulated Boiling Water Reactor Accident Conditions, General Electric Company, NEDO-25420, E450,1 Class 1, June 1981.

C-39 Devell, L., et. al., 1967. " Trapping of Iodine in Water Pools at 100 C," Centainment and Siting of Nuclear Plants, Proceedings of a Symposium, I.A.C.A.,

1967. CONF-67042.

C-40 Diffey, H. B., et. al., 1965. Iodine Cleanup in a Steam Suppression System, United Kingdom Atomic Energy Research Establishment.

M P83 123/07 6-df C-49 Amendment 2 v

u ..

o as' om JLufr 33 Pl,d Q' \ni ig a tpi \o g ,

dr uk r o oiuk E e e i, a tonnSo o oouvok

. - -___ a x = : - -,- = 2 APPLICANT'S ENVIRONMENTAL REPORT-OPERATING LICENSE VOLUME 3 STAGE o . . _ . . . .

O PSEG l

HCGS OLER

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PUBLIC SERVICE ELECTRIC AND GAS COMPANY

, HOPE CREEK GENERATING STATION

+ENVISONMENTAL REPORT - OPERATING LICENSE STAGE

, TABLE OF CONTENTS Page Chapter Title Number 1 PURPOSE OF THE PROPOSED FACILITY 4

AND ASSOCIATED TRANSMISSION 21 THE SITE AND ENVIRONMENTAL INTERFACES 2.1 Geog raphy and Demography . . . . . . . . . . . . . 2.1-1 2.2 Ecology............................... 2.2-1 2.3 Meteorology........................... 2.3-1 2.4 Hydrology............................ 2.4-1 2.5 Geology............................... 2.5-1 2.6 Regional Historic, Archaeological, Architectural, Scenic, Cultural and Natural Features.................... 2.6-1 2.7 Noise................................. 2.7-1

) 3 , THE STATION v

3.1 External Appearance................... 3.1-1 3.2 Reactor and Steam Electric System..... 3.2-1 3.3 Station Water Use..................... 3.3-1 3.4 Heat Dissipation System.............. 3.4-1 3.5 Radwaste Systems and Source Term...... 3.5-1

3. 6' Chemical and Biocide Wastes.......... 3.6-1 3.7 Sanitary and Other Waste Systems. . . . . . 3.7-1 3.8 Reporting of Radioactive Material Movement............................. 3.8-1 3.9 Transmission Facilities............... 3.9-1 4 ENVIR'ONMENTAL EFFECTS OF SITE PREPARATION, FIATION CONSTRUCTION AND TRANSMISSION l'ACILITIES CONSTRUCTION 4 .1 Site Preparation and Station Construction......................... 4.1-1 4.2 Transmission Corridors............... 4.2-1 4' . 3 Resources Committed during Construction......................... 4.3-1 4.4 Radioactivity........................ 4.4-1

' 4.5 Construction Impact Control.......... 4.5-1 i

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HCGS OLER

(

\~ # TABLE OF CONTENTS (Continued )

Page Chapter Title Number 5 ENVIRONMENTAL EFFECTS OF STATION OPERATION 5.1 Effects of Operation of Heat Dissipation System................... 5.1-1 5.2 Radiological Impact from Routine Operation........................... 5.2-1 5.3 Effects of Chemical or Biocide Discharges........................... 5.3-1 5.4 Ef fects of Sanitary Waste Discharges. . 5.4-1 5.5 Effects of Operatio'n and Maintenance of the Transmission Systems.......... 5.5-1 5.6 Other Effects......................... 5.6-1 5.7 Resources Committed during Operation.. 5.7-1 5.8 Decommissioning and Dismantling. . . . . . . 5.8-1 5.9 The Uranium Fuel Cycle................ 5.9-1 6 EFFLUENT AND ENVIRONMENTAL MEASUREMENTS AND MONITORING PROGRAMS 6.1 Preoperational Environmental Programs. 6.1-1

[s h N- l 6.2 Proposed Operational Monitoring Program............................. 6.2-1 6.3 Related Environmental Measurement and.

Mo n i t o r i ng Prog ra ms . . . . . . . . . . . . . . . . . . 6.3-1 6.4 Preoperational Environmental Radiological Monitoring Data. . . . . . . . . 6.4-1 7 ENVIRONMENTAL EFFECTS OF ACCIDENTS 7.1 Scation Accidents Involving Radioactivity....................... 7.1-1 7.2 Transportation Accidents Involving Radioactivity....................... 7.2-1 7.3 Other Accidents...................... 7.3-1

8 ECONOMIC AND SOCIAL EFFECTS OF STATION CONSTRUCTION AND OPERATION 8.1 Benefits............................. 8.1-1 8.2 Costs................................ 8.2-1

? ALTERNi.fIVE ENERGY SOURCES AND SITES 4

M P82 148/15-df li

HCGS OLER O

(s,) TABLE OF CONTENTS (Continued)

Page Chapter Title Nuanbe r 10 STATION DESIGN ALTERNATIVES 10.1 Circulation System................... 10.1-1 10.2 Intake System........................ 10.2-1 10.3 Discharge System..................... 13.3-1 10.4 Chemical Waste Treatment............. 10.4-1 10.5 B ioc ide Tre a tme n t . . . . . . . . . . . . . . . . . . . . 10.5-1 10.6 Sanitary Waste System................ 10.6-1 10.7 Alternative Liquid Radwaste Systems.. 10.7-1 10.8 Alternative Gaseous Radwaste Systems. 10.8-1 10.9 Transmission Facilities............. 10.9-1 11

SUMMARY

COST BENEFIT ANALYSIS 11.1 Benefits............................. 11.1-1 11.2 Costs................................ 11.2-1 12 ENVIRONMENTAL APPROVALS AND CONSULTATION 12.1 Permits............................. 12.1-1 a

"') 12.2 consultation.............. , ........ 12.2-1 13 SUMPARY OF ACTIONS TAKEN 13.0 General.............................. 13.0-1 13.1 Chlorination Effects Study.......... 13.1-1 13.2 Ecological Monitoring Program........ 13.2-1 13.3 Compensating Water Supply........... 13.3-1 13.4 Salem Ecological Impact.............. 13.4-1 13.5 Cooling Tower Drift and Salt De po s i t i o n . . . . . . . . . . . . . . . . . . . . . . . . . . 13.5-1 13.6 Hope Creek - Tuckerton 500 Kilovolt Trancmission Line................... 13.6-1 13.7 Construction Impact Control.......... 13.7-1 13.8 Audible Signals...................... .~. 3 . 8 - 1 13.9 Hope Creek Ecological Monitoring Program............................. 13.9-1 13.10 Radiation Monitoring of Wells. . . . . . . . 13.10-1 13.11 Medical Preparedness................. 13.11-1 13.12 Publication of Reports............... 13.12-1 13.13 Cooling Tower Performance Measurement 13.13-1 13.14 Television Reception................. 13.14-1

. 13.15 River Traffic Study.................. 13.15-1 (h

( ,/ M P82 148/15-df lii

HCGS OLER 12/83 TABLE OF CONTENTS (Con tinued )

Page Chapter Title Number 14 REFERENCES APPENDICES Appendix A - Thermal Modeling Methodology. . . A-1 Appendix R - ............................... (Not Used)

Appendix C - Class 9 ronsequence Analysis... C-1 OUESTIONS E-i 2

LIST OF EFFECTIVE PAGES EP-i O .

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HCGS OLER 12/83

~s INDEX

\

GROUPING OF RESPONSES TO QUESTIONS BY APPLICABLE OLER SECTION NUMBER OLER Section Ouestion Number Number 2.1 E290.6 E291.1 E291.12 E310.1 E310.2 E311.1 E311.2 E470.1 E470.6 2.2 E290.1 E290.2 E291.2 E291.3 2.3 E451.1 E451.2 b)

%J E451.3 2.4 E240.1 E240.2 E291.13 E291.14 E470.2 E470.3 3.4 E291.4 E291.5 E291.6 E291.15 E291.18 3.6 E291.16 3.9 E310.3 5.1 E290.3 E291.7 E291.8 E291.21 l2 E451.4 E451.5 E470.5

\s -) M P83 85/17 3-gs E-ii Amendment 2

• I HCGS OLER 12/83 1

l

INDEX (Continued) 1 OLER

Section Ouestion

Number Number l 5.2 E470.4 E470.f l

4  :

! 5.3 E291.17 '

!' 5.5 E290.4 E290.5

! 5.8 E320.1 4 6.1 E451.6  ;

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.1 i 8.1 E310.4

'; E310.5 E310.6 E310.7 E310.8-E310.9 E320.2 13.1 E291.19 E291.20 2 f~ 13.4 E291.ll Appendix C E450.1 l l2 l

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HCGS OLER 12/83 OUESTION E291.17 (Section 5.3.1.1) s Update the status of the planning of the treatment systen for station low volume waste water. If available, provide infor-mation on the type and degree of treatment, expected quality of the system effluent, effluent discharge rate, and location of discharge.

RES PONSE The requested information has been incorporated into Sections 3.6, 5.3, and 10.4. 2 V

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OUESTION E291.20 (Section 13.1)

Provide a copy of Environmental Report reference 13.1-1 entit1ed Chlorine Ana1ysis Evaluation Program On-Site 6 Comparison of Free Chlorine Analyzers for Use in Estuarine Wa te rs , PSE&G, 1975.

j RESPONSE i Due to the availability of more up-to-date information in the recent references (e.g., Sengupta et al, Sugam et al, and Sugam), PSE&G has amended the list of references for Section,13.1 by deleting reference 13.1-1. ,

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I HCES OIER 12/83 A

U QtESTICN E291.21 (Section 5.1)

%e cooling tower blowdown discharge location has been changed sin the CP stage FES frm 200 feet offshore to 10 feet offshore (essentially shoreline) in the river. Provide a cxmparative discussion of the impacts to the river biota (frm thermal and chmical effluents) die to this relocaticn.

RESPCNSE nelocation of the cooling tuer blowdown discharge and decreasing its flow (see Tables 3.4-5 and 3.4-9) changes the extent and configuration of the discharge pitme frm that anticipated at the CP stage to that discussed in Section 5.1.2. It is anticipated that thermal discharge related inpacts on aquatic biota, as described during the CP stage, will decrease with single triit operation.

At the CP stage, the length of the two unit, buoyant thermal p1tme, as denoted by the 40F (2.20 C) surface isotherm, was estimated by PSE&G to be approxi-mately 300 feet for both sumer (June) and winter (February) operating and river conditions (see Figures E291.21-1 and E291.21-2). With cancellation of Unit 2, shortening of the cooling tower blowdown discharge line and elimina-tion of the cold water bypass, the thermal pitme is a predcminantly negatively buoyant bottm pitme with the 40F (2.2 0F) botton isotherm extending approximately 100 feet during the simmer (August) and up to 2000 feet during the winter (February) (Section 5.1) . A contributing factor is the fact that j cold side blowdown is discharged at a velocity of about 3.5 feet per semnd (1.1 meters per second) at normal blowdown flows. Originally, the discharge velocity under similar operating conditions was estimated to be 8.5 feet per second (2.67 meters per second).

Fishes and other organisms found in the HOGS vicinity are not unique. All are found throughout the Delaware Estuary and adjao3nt coastal waters. Se effects of thermal discharges on species found in the vicinity of Artificial Island have been presented in great detail in several reports (Ibferences 1 through 3).

mese species are physically excluded frm the waraest portions of either the original or current thermal plume due to its near-field velocities exceeding the maximun sustained swim speed of the fish present. (21anges in tidal direction and velocity will effect the pitme's direction and extent, further limiting the ntmber of fish in the warmest portions of the thermal pitme.

Because of the pitme now having a negative buoyancy, benthic macroinvertebrates will be subjected to increased tenperatures not previously discussed. Such organisms are, however, extremely dynamic and etunistic. mey survive normally large shifts in bottm material caused by the river's movable Mi=nt load and the fact that large anounts of sediment ara deposited in the vicinity of the site. The original discharge design, now replaced by the current configuration of the discharge is anticipated to scour conparable, small areas of river bottan in the vicinity of the discharge O

v outlet. -

E291. 21-1 Amendment 2

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l HO3S OLER 12/83 Neither the plume as discussed at the CP stage, nor the present configura-O tion significantly affects the spanung of fishes and other organisms in the vicinity of HO3S. 'Ihermal shock related deaths of organisms found near the station are not expected to be significant nor different frcxn those anticipated for the original plume configuration. It is also anticipated that the new thermal plume will not block the seasonal migrations of such fishes as American shad, whic:h pass in the vicinity of HCCS during spring and fall.

'Ihe heated plunn may possibly attract fishes during all periods of the year except during the warmest sunTner mcnths. As these fish encounter the far field of the plume they will nove towards their preferred tenperature.

During the periods of highest natural river temperatures, fish may avoid the inmediate vicinity of the discharge as well as be excluded due to discharge velocity. No nortality of fishes is anticipated due to the introduction of the heated effluents described in Section 3.4 either during the sunmer or winter.

No winter fish kills have been cbserved in the vicinity of Artificial Island dur to Salem's heated effluent frcra its cnce through cooling system.

Nevertheless, in the case of shutdown of HOGS in winter, the fish that may occur within the vicinity of the thermal plume could find similar preferred tenperatures in the Salem thermal plume. Neither station has a discharge canal which would create a sicw-moving source of warm water; the discharges are dynamimlly affected by currents and tides.

Onaical discharges associated with cooling tower operation are also present in cooling tower blowdown. Sodiun hypochlorite to control biofouling and sulfuric acid to control scale buildup are anong the chmimla present. 'Ihe biocide methodology for HCG at the OL stage is currently under study (see Questions E291.16 and E291.19) . For ncw it can be said that (temical use will be reduced due to the cancellation of Unit 2. Also any biocide such as chlorine and any other chemical such as sulfuric acid which will be discharged in the cooling tower blowdown will meet applicable effluent limitations and be diluted to a low level at a short distance frczn the end of the pipe due to the rapid mixing of the discharge with river water. It is expected that the concentrations of all chmienla found in the blowdown will be small and will not hann any organisms that may be present.

lemeNCES

1. Public Service Electric and Gas 02npany 1974. Salem Nuclear Generating Station Section 316(a) Demonstration, Type 2. Newark, N.J.

2. Public Service Electric and Gas Q2npany 1976. Salem Nuclear Generating Station Section 316(a) Demcnstration, First Supplement. Newark, N.J.

3. Public Service Electric and Gas 02npany 1978. Salem Nuclear Generating Staticn Section 316(a) Desucnstration, Second Supplement.

O E291.21-2 Amendment 2 l 1

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SUBMERGED JET DISCHARGE O 300 l g HO,PE CREEK',,

3F GENERATING STATION L

NORTH ARTIFICIAL ISLAND 1

l SHORELINE l

I I ISOTHERMS OF WASTE HEAT IN THE 1.5F 5 FOOT SURFACE LAYER SUMMER CONDITIONS ( JUNE OR NOVEMBER )

MAXIMUM HEAT RELEASE-134 cfs AT AT 7.5F

( O.225 X 10' BTU /HR )

THE PATTERN SHOWN WOULD BE PRESENT FROM O.5 HOUR AFTER SLACK TO END OF EBB CURRENTS.

A SIMILAR PATTERN WOULD BE PRESENT BUT ORIENTED UPSTREAM DURING FLOOD TIDE.

i HOPE CREEK GENERATING STATION ENVIRONMENTAL REPORT q g OPERATING LICENSE STAGE-THERMAL PLUME ANTICIPATED AT CP- STAGE, SUMMER CONDITIONS

( JUNE OR NOVEMBER )

FIGURE E291.21 - 1 AMEND. 2

1 l

SUBMERGED JET DISCHARGE O 300 l

( l i 4F ,, HOPE CREEK I GEN 5 RATING SIATION L

i NORTH l I

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3F  !

l ISOTHERMS OF WASTE HEAT '

IN THE 5 FOOT SURFACE LAYER  !

SHORELINE 1

I I i

WINTER CONDITIONS - ( FEBRUARY )

MAXIMUM HEAT RELEASE - 134 cfs AT AT 7.5F

( O.42 X 10 BTU /HR )

THE PATTERN SHOWN WOULD BE PRESENT FROM O.5 HOUR AFTER SLACK TO END OF EBB CURRENTS.

A SIMILAR PATTERN WOULD BE. PRESENT BUT ORIENTED UPSTREAM DURING FLOOD TIDE.

1.7F f HOPE CREEK GENERATI G ST 10 ENVIRONMENTAL RE RT 4 g OPERATING LICENSE .

THERMAL PLUME ANTICIPATED AT CP - STAGE WINTER CONDITIONS

( FEBRUARY-)

FIGURE E291.21 - 2 AMEND.'- 2

. _... - _.. . . ~ . . . . - . . - - . _ . . _ . - - _ . . - . _ - . _ . . . . - . - = - . . . - . . . . . . - . _ . - _ _

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HCGS OLER 12/83 [

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OUESTION E291.22 -

f Provide a copy of the NPDES permit renewal application when i submitted to the state.

, RESPONSE 7

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} A copy of the NPDES permit renewal application will be sent I to the Nuclear Regulatory Commission when it is submitted to the state in the early part of 1984. l l

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HCGS OLER 12/03 m

U QUESTION E450.1 (Appendix C)

The scrubbing of fission products from gas or vapor bubbles passing through the suppression pool is discussed for several accident sequences. However, there are no refer-ences for the experimental data on pool scrubbing, even though the review of these data was mentioned (Pg.C-16).

Provide referenccs for these data, and any new relevant data on pool scrubbing.

RESPONSE

The requested references have been added to Appendix C as References C-37 through C-40. New data considered are the suppression pool decontamination factors (DF's), used in the 1983 draft report of BMI-2104 (Radionuclide Release under specific LWR Accident Conditions), which have been reviewed against those used in Appendix C and found comparable.

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HCGS OLER 8/83 Ol'ESTIONS

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