Text

Proposed Tech Specs Relocating Procedural Details of RETS to ODCM or Process Control Program as Approriate,Per Generic Ltr 89-01
	ML20082G555
Person / Time
Site:	Grand Gulf
Issue date:	08/13/1991
From:	; ENTERGY OPERATIONS, INC.
To:	;
Shared Package
ML20082G548	List: ML20082G545; ML20082G555;
References
	GL-89-01, GL-89-1, GNRO-91-00084, GNRO-91-84, NUDOCS 9108190209
	Download: ML20082G555 (253)
	v • d • e

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At tachmotit 3 tn GNRO-91/00084 PRol'OSED TECllNICAI. SPECIFICATION REVISIONS l'OR PCOL-91/11 G9105141/SNI,1CFI.R - 20 9108190209 91ogin PDR 7 ADOCK 03000114 l P FDR l

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,- '795 4 91/431-4 INDEX r

_6_F.F I N IT IONS t

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SECTION !

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1. 0 DEFINITIONS PAGE l 1.1 ACTION................... ..... ..................................... 1-1 I 1.2 AVERAGE PLANAR EXP050RE.............................................. 1-1 ,

t

1. 3 AVERAGE PLANAR LINEAR HEAT GENERATION RATE......., ,. ..... . ...... 1-1 1.4 CHANNEL CALIBRATION.............. . . . . . . . . ....... ... . ...... 1 t 1.5 CHANNEL CHECK..................... ........................... ... . 1-1

[

1. 6 CHANNEL FUNCTIONAL TEST........ . ............ . ................. .... 1-1

1. 7 CORE ALTERATION. ....,..................................... ....... 1-2

1. 8 CRITICAL POWER RATI0..,........................ . . . . . . ... .. ...... 1-2 1

1. 9 DOSE EQUIVALENT I-131........ ............ ......... ........ ....... 1-2 :;

1.10 ORYWELL INTEGRITY. .......... .. .................................... 1-2 ;

1.11 E-AVERAGE DISINTEGRATION ENERGY.......................... . ..... .. 1-3 ,

1.12 EMERGENCY CORE COOLING SYSTEM (ECCS) RESPONSE TIME....... ........... 1-3 [

1.13 END-0F-CYCLE RECIRCULATION PUMP TRIP SYSTEM RESPONSE TIME............ 1-3 !

1 1.14 FRACTION OF LIMITING POWER DENSITY,,............,.................... 1-3 -

1.15 FRACTION OF RATED THERMAL POWER . . . . . . . . . . . . ......... .... ... . 1-3 1-16 FREQUENCY NOTATION. ,,. .................. ............. ... ...... . 1-3 i r

DELUf,D 1.1 P A P Pnt ar unsuvus M A hl lArT nnunna,Pu T M P A T 1. F a l T i nuninuni

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i p u r e rna avaicn...................... .. 1-3 g 1.18 I D E NT I F I E D L E A KAG E . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1-4 !

1.19 ISOLATION SYSTEM RESPONSE TIME............ .............. ..... .. 1-4 t

1.20 LIMITING CONTROL R0D PATTERN....................................... 1-4 1.21 LINEAR HEAT GENERATION RATE............. ............................ 1-4 I I

1.22 LOGIC SYSTEM FUNCTIONAL TEST......................................... 1-4 1.23 MAXIMUM FRACTION OF LIMITING POWER DENSITY........................... 1-4 l 1.24 MEMBER (5) 0F THE PUBLIC..................................... ..... . 1-4 !

1.25 MINIMUM CRITICAL POWER RATI0................. ....................... 1-5 ,

1.26 0FFSITE DOSE CALCULATION MANUAL (00CM)............................... 1-5 1.27 OPERABLE - OPERABILITY............... . . . . . . . . . ...................... 1-5 l

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GRAND GULF-UNIT 1 i Amend med Mo. - l :

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l INDEX DEFINITIONS SECTION DEFINITIONS (Continued) PAGE 1.28 OPERATIONAL CONDITION - CONDITION.... .. . , , ., . . .. 1-5 1.29 PHYSICS TESTS. . .<. .. . ........ ... ... . .. .... . .. 1-5 1.30 PRESSURE BOUNDARY LEAKAGE.. .. . .. . . . . . .. .. ... .. 1-5 1.31 PRIMARY CONTAINMENT INTEGRITY. ,, .. . . . .. . .. . .. 1-6 1.32 PROCESS CONTROL PROGRAM (PCP), ....... .. .. . . .. .. . 1-6 1.33 PURGE - PURGING., ... . ... ,, . . .. ,,,. ... 1-6 1.34 RATED THERMAL POWER..... .,.

.. . . .. . . . . ., 1-6 1.35 REACTOR PROTECTION SYSTEM RESPONSE TIME , .... .... .. .... . 1-7 1.36 REPORTABLE EVENT, ..... . ... ....... ., . .... . . . . .. . .. .. 1-7 1.37 R00 0ENSITY,............................... .... ... ........., . . . 1- 7 1.38 SECONDARY CONTAINMENT INTEGRITY.. ....... . ........, ,,,. .. . 1-7 1.39 SHUTDOWN MARGIN, .......... ,, . . . . . .., , ,, ,, 1-8 1.40 SITE BOUNDARY .... .. ..... . ., , , .. .. . .. . . .. 1-8 tetcTEn 1.41f30L10lilCAHON. ,, .. . .. .. . ... . . . . .. 1-8 DELETEb 1,42 $OURC[ Cll[CL . , ,. ,,,. ,,,, , ,, ,. ... . . .. ,,,,,,,,. . 1-8 1.43 STAGGERED TEST BASIS... , .... ... .. ................ . .. 1-8 1,44 THERMAL POWER.. ..... .... ..... ... . .. . . .. .... . . 1-8 1.45 UNIDENTIFIED LEAKAGE..., .. . . . . . ...... . .......... 1-8 1.46 UNRESTRICTED AREA.. ....... . ....... .. ... ... . . ... 1-8 DELETED 1.47 VENHtAMOH-EKHAUST-TREATMENT-6YSTEM. . .. ... ., , ,, . . 1- 8 1,48 VENTING. . .. ... .. ,, ...... ...... .... ... ..... . . .. 1-9 TABLE 1.1, SURVEILLANCE FREQUENCY NOTAfl0N. . . .. .. . 1-10 TABLE 1.2, OPERATIONAL CONDITIONS. .. . . . . . . .. 1-11 GRAND GULF-UNIT 1 ii Amendmewk Mo.

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, '91lOl INDEX LINITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION PAGE 3/4.3- INSTRUMENTATION 3/4.3.1 REACTOR PROTECTION SYSTEN INSTRUMENTATION.................. 3/4 3 1 3/4.3.2 ISOLATION ACTUATION INSTRUMENTATION......................... 3/4 3 9 3/4.3.3 ENERGENCY CORE COOLING SYSTEM ACTUATION INSTRUMENT 3/4 3-27 3/4.3.4 RECIRCULATION PUMP TRIP ACTUATION INSTRUMENTATION ATWS Recirculation Pump Trip Systes Instrumentation. . . . . . . . , 3/4 3-37 End-of-Cycle Recirculation Pump Trip System Instrumentation............................................. 3/4 3-41 3/4.3.5 REACTOR CORE ISOLATION COOLING SYSTEM ACTUATION INSTRUMENTATION............................................. 3/4 3-47 3/4.3.6 CONTPOL R00 BLOCK INSTRUMENTATION........................... 3/4 3-52 3/4.3.7 MONITORING INSTRUMENTATION Radiation Monitoring Instrumentation........................ 3/4 3-58 Seismic Monitoring Instrumentation.......................... 3/4 3-63 Meteorological Monitoring Instrumentation................... 3/4 3-66 Remote Shutdown System Instrumentation and Controls........, 3/4 3-69 Accident Monitoring Instrumentation......................... 3/4 3-73 S o u rc e Ra nge Mon i to r s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .3/4 3-77 Traversing In-Core Probe System............................. 3/4 3-78 Chlorine Detection System................................... 3/4 3-79 Fire Detection Instrumentation.............................. 3/4 3-80 Loose-Part Detection System................................. 3/4 3-90 J ioactive di 1 -MeitAons:Instrynetation. . . . . . 3/4-3-%

Raht Ocodeer bsrTreatma em - Expitsp (ns7

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- etiVCOM f. heat Nonitiring 'Instrumentillon. . . . . Qqi A 3/4 3- 6 3/4.3.8 qiP PLANT SYSTEMS 3/4.3.9 TURBINE OVERSPEED PROTECTION ACTUATION INSTRUMENTATION. 3/4 3 *) .

HT SYSTEM.......................... 3/4 3 .

GRAND GULF-UNIT 1 v Amendment No. 62,

76-9) D1 INDEX l

LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION PAGE 3/4.11 RADI0 ACTIVE EFFLUENTS 3/4.11.1 LIQUID EFFLUENTS

-Concenttet4 cr . . . . . . .. ... 3 /4-H -Oose.. . . . . . . ., .. . 3/4 11-fr

-t-4tret44-Mette-4*eet-ment . . . .. 3 /4-H t Liquid Holdup Tanks. . . . . .... ........., . ... ... ... 3/4 11-3/4.11.2 GASEOUS EFFLUENTS

-Dese4ete . . . . 3 /4-H-6--

-Dose 4Me--Gese; . . . .. . 3 /4-1+-le--

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-4r, ";rt iculete Fo rm. . . .. .. . .. .. . .. ,. 3 /4 1-1-1+

Get, ecus "adwatt 'rcatment. . 3/4 11-1+

-Ventiletion [,haust Trestment. . . . 3/4 11--p 2

Explosive Gas Mixture. . . . . ... . . .. . 3/4 11-3 Main Condenser... . .... . ., , , .. . 3/4 11- f n 14 i S/M sr-v . 11.v5

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INDEk BASE 5 SECTION PAGE INSTRUMENTATION (Continued) 3/4.3.7 MONiTORIN3 INSTRtMENTATION Radiation Menitoring Instrumentation. . . . . . . . . . . . . . . B 3/4 3 4 Seismic Monitoring Instrumentation................. B 3/4 3 4 Meteorological Monitoring Instrumentation.......... B 3/4 3 4 Remote Shutdown System Instrumentation and Controls......................................... B 3/4 3 4 Accident Monitoring Instrumentation................ B 3/4 3 4 Source Range Monitors.............................. B 3/4 3 5 Traversing in Core Probe 5yster..................... B 3/4 3 5 Chlorine Detection 5ystem.......................... B 3/4 3 5

- Fire Detection Instrumentation..................... B 3/4 3 5 Main Condenser Loose Part Detection 5ystes........................ B 3/4 3 6 gp3n Tualmed -Recietet4ve-t-icuid4f fluent-Monitoring--

6 stem - t: /plW' m i ns trument a ti c n . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . B 3/*+6-9# / -4e64eeet4ve-Gesteus4ff4uent[ Monitoring [

r~ Instrumentation............................'.fpC'"

..... B 3/4 3-6 3/4.3.B PLANT SYSTEMS ACTUATION INSTRUMENTATION..........., B 3/4 3-E 3 /4. 3. 9 TURBINE'OVERSPEED PROTECT 10N....................... B 3/4 3-7 3/4.3.10 hEUTRON F LUX MohlTORING INSTRUMENTATION. . . . . . . . . . . . B 3/4 3 7 3/4.4 REACTOR COOLANT SY! TEM 3/4.4.1 RECIRCULATION 5YSTEM............................... B 3/4 4 1 3/4.4.2 SAFETY / RELIEF VALVES............................... B 3/4 4 2 3/4.4.3 REACTOR C00LAh'i SYSTEM LEAKAGE Leakage Detection 5ystems.......................... B 3/4 4-2 Operational Leakage................................ B 3/4 4 2 3/4.4.4 CHEM 151RY.......................................... B 3/4 4 3 3/4.4.5 SPEtlFit ACTIV1TY.................................. ,B 3/4 4 3 3/4.4.6 PRES 5URE/ TEMPERATURE 1.lMITS........................ B 3/4 4-4 3/4.4.7 MAIN STEAM LINE ISOLATION VALVE 5...............,.... B 3/4 4*B 3/4.4.8 STRUCTURAL INTEGRITY............................... B 3/4 4*!

3/4.4.9 RESIDUAL HEAT RE mVAL.............................. B 3/4 4 5 GRAC GULF-UNIT 3 xiii Amenement No.16,

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. 7.5 - 9 I/01 INDEX l

l BASES SECTION PAGE REFUELING OPERATIONS (Continued) 3/4.9.8 and 3/4.9.9 WATER LEVEL - REACTOR VESSEL and WATER LEVEL - SPENT FUEL AND UPPER CONTAINMENT FUEL STORAGE P0OLS. .. .. . ..... ... B 3/4 9-2 3/4.9.10 CONTROL R00 REMOVAL. . . . . B 3/4 9-2 3/4.9,11 RESIDUAL HEAT REMOVAL AND COOLANT CIRCULATION. B 3/4 9-2 3/4.9.12 HORIZONTAL FUEL TRANSFER SYSTEM. ... . . B 3/4 9-2 3/4.10 SPECIAL TEST EXCEPTIONS 3/4.10.1 PRIMARY CONTAINMENT INTEGRITY /DRYWELL INTEGRITY. B 3/4 10-1 3/4.10.2 ROD PATTERN CONTROL SYSTEM., .... . . .. B 3/4 10-1 3/4.10.3 SHUTDOWN MARGIN DEMONSTRATIONS.,..... . B 3/4 10-1 3/4.10.4 RECIRCULATION LOOPS.. ... . . . .. . . B 3/4 10-1 3/4.10.5 TRAINING STARTUPS. . .. , ... .. . B 3/4 10-1 3/4.11 RADI0 ACTIVE EFFLUENTS 3/4.11,1 LIQUID EFFLUENTS. . . .. .... . B 3/4 11-1 Conccatration 0 3/4 11-1

-Bose. . C 3/4 11-1 Liquid beste Treatment. . , 0 3/4 11 Liquid Holdup Tanks. . .. . ........ ... ... . . B 3/4 11 3/4.11.2 GASE0US EFFLUENTS. .. . . ..... .. .. . .. . B 3/4 11 Ocsc Rate. . . . . 0 3/4 11 3 Ocsc Neule Csse3 0 3/^ 11-3 Ocac I sd i ne - 1:1, - I c d i n e - 133, T r i t-iw,md-

-Redionuclides in Particulete form B 3/" 11 '

Ca;ccu; Rac c;tc 'rcatment and Ventilatic,

-Exh5ust System. . 0 J/4 11 l GRAND GULF-UNIT 1 xvi Amend enc 41 bJo. ___ 1

+ 7 6 - 91 Of INDEX BASES SECTION PAGE RADI0 ACTIVE EFFLUENTS (Continued)

Explosive Gas Mixture....................... ....... B 3/4 11-O Main Condenser......................... ... ........ B 3/4 11-h

-3/4.11.3 00L IO " A0iOAC-HVE-WA9K . . . . , .. . .. .. .. 03/411 ^*'A -- !

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INDEX ADMINISTRATIVE CONTROLS SECTION PAGE SAFETY REVIEW COMMITTEE (SRC) (Continued)

Review........ ......... .... . .. .. . .............. .... 6-10 Audits...................... ......... ............ ..... . 6-11 Authority. .. .. ...... ......... .. ..., ......... ... 6-12 Records...... . ....... . ............ ... . .. ............. 6-12 6.5.3 TECHNICAL REVIEW AND CONTROL Activities. .. .. ...... .... . . .. ... .. . .... . 6-12 6.6 REPORTABLE EVENT ACTION, .... ... .. . . . .. .. 6-13 6.7 SAFETY LIMIT VIOLATION..... .. ........ .. ... .... ............ 6-13 6.8 PROCEDURES AND PROGRAMS. .. .... . ... . . .... .... .... . 6-14 6.9 REPORTING RE0VIREMENTS Routine Reports... .... . ... , .. ... ... ...... .... 6-15 Startup Reports... ....... ....... ... ... .. .. .. . ..... 6-15 Annual Reports. . .. ......... . .... ......... .. . 6-16 Annual Radialogical Environmental Operating Report... . ,, . 6-17 Semiannual Radioactive Effluent Release Report.. .... . ... 6-17 Monthly Operating Reports............................... .... 6-19 Special Reports... .... ... . .. .. ... ..... .... ... ... . 6-19 6.10 RECORD RETENTION.. .. .............. . ... ...... ........ ...... 6-19 6.11 RADIATION PROTECTION PROGRAM. . ... ............ ......... ...... 6-21 6.12 HIGH RADIATION AREA. . .. .., . .. . ....... . ..... ...... . 6-21 6.13 PROCESS PROGRAM CONTROL (PCP)..... .. .... . .......... ... ... 6-22 6.14 0FFSITE DOSE CALCULATION MANUAL (0DCM).. . .. .. ...... .. 6-22 15 MAJOR C;;ANGES TO RADICACTIVE 'n'ASTE TREATMENT SYSTEM 5. . . ---0 2 3 GRAND GULF-UNIT 1 xx AmerdmeAt bJ o . _

T% -9 t/01 DEFINfTIONS E AVERAGE DISINTEGRATION ENERGY 1.11 E shall be the average, weighted in proportion to the concentration of each radionuclide in the reactor coolant at the time of sampling, of the sum of the average beta and gamma energies per disintegration, in MeV, for isotopes, with half lives greater than 15 minutes, making up at least 951; of the total non-iodine activity in the coolant.

EMERGENCY CORE COOLING SYSTEM (ECCS) RESPONSE LIME 1.12 The EMERGENCY CORE COOLING SYSTEM (ECCS) RESPONSE TIME shall be that time interval from when the monitored parameter exceeds its ECCS actuation setpoint at the channel sensor until the ECCS equipment is capable of performing its safety function, i.e., the valves travel to their required positions, pump discharge pressures reach their required values, etc. Times shall include diesel generator starting and sequence Icading delays where applicable. The response time may be measured by any series of sequential, overlapping or -

total steps such that the entire response time is measured.

END-OF-CYCLE RECIRCULATION PUMP TRIP SYSTEM RESPONSE TIME 1.13 The END-OF-CYCLE RECIRCULATION PUMP TRIP SYSTEM RESPONSE TIME shall be that time interval to complete suppression of the electric are between the fully open contacts of the recirculation pump circuit breaker from initial movement of the associated:

a. Turbine stop valves, and

b. Turbine control valves.

The response time may be measured by any series of sequential, overlapping or total steps such that the entire response time is measured, except for the breaker arc suppression time which is not measured but is validated by sur-veillance tests to conform to the manufacturer's design value.

FRACTION OF LIMITING POWER DENSITY 1.14 The FRACTION OF LIMITING POWER DENSITY (FLID) shall be the LHGR existing at a given location divided by the limiting LHGR for that bundle type.

FRACTION OF RATED THERMAL POWER 1.15 The FRACTION OF RATED THERMAL POWER (FRTP) ct.al be the measured THERMAL POWER divided by the RATED THERMAL POWER.

FREQUENCY NOTATION 1.16 The FREQUENCY NOTATION specified for the performance of Surveillance Requirements shall correspond to the intervals defined in Table 1.1.

-GASEOUS RADWASTE TREATMENT--(OFFGAS)-GYSTEM-1.174The GASEOUS RADWA5TE-TREATMENT-(OFFGAS)-SYSTEM-4$-the-systee-des 4gned-and.

h:ta. led to reduce-eadioactive-geseove-effhents by . cHectir.g pefeery-coolant-

-systee of f geses f re the- peleary-eystem-end-providir,; fcr deley-oe-he4 dup-fee-the-

--purpose-of-ceduchg-the total ridicactivity prior te release-to-the-environmente GRAND GULF-UNIT 1 1-3 Amendment No.18 4,

. . IM #il/DI DEFINITIONS I

l MINIMUM CRITICAL POWER RATIO 1.25 The MINIMUM CRITICAL POWER RATIO (MCPR) shall be the smallest CPR which exists in the core.

OFFSITE 005E CALCULATION MANUAL (ODCM) 7g ggr Dditie-0EESilE DOSE CALCULATION MANUAL shall contain thegadologyg parameters usedTii'ITItreakulation of of f si te doses 4uc-tb radioactive gaseous A and liquid effluents and in thhICUlstinfuo% 1aseous and liquid effluent monitoring alarmL1 rip-4etpDTids. It shall also diitaima4able and f igure d_elimmycurrent e radiological environmental monitoring sample M1onsx OPERABLE - OPERABIllTY 1.27 A system, subsystem, train, component or device shall be OPERABLE or have OPERABILITY when it is capable of performing its specified function (s) and when all necessary attendant instrumentation, controls, electrical power, cooling or seal water, lubrication or other auxiliary equipment that are required for the system, subsystem, train, component or device to perform its function (s) are also capable of performing their related support function (s).

OPERATIONAL CONDITION - CONDITION 1.28 An OPERATIONAL CONDITION, i.e., CONDITION, shall be any one inclusive combination of mode switch position and average reactor coolant temperature as specified in Table 1.2.

PHYSICS TESTS 1.29 PHYSICS TESTS shall be those tests performed to measure the fundamental nuclear characteristics of the reactor core and related instrumentation and

1) described in Chapter 14 of the FSAR, 2) authorized under the provisions of 10 CFR 50.59, or 3) otherwise approved by the Commission.

PRESSURE BOUNDARY LEAKAGE 1.30 PRESSURE BOUNDARY LEAKAGE shall be leakage through a non-isolable fault in a reactor coolant system component body, pipe wall or vessel wall.

GRAND GULF-UNIT 1 1-5 Amendment Mc-

} PS-91/01

_ Ins _ert to Page_1-5 Insort A:

1.26 Tho 0FI' SITE DOSE cal,CUI.ATION MANUAL. (ODCM) stall cont ain the methodology nnd parnmet ers used in t he calculat ion of of f sit e doses result.ing f rom radionet ive gaseous and liquid ef fluents, in the calculation of gaseous and liquid ef finent monitoring Alarm / Trip -

Set point.s , and in t he conduct of the Environmental Rndiological Monitoring I'rogrnm. The ODCM shnll also cont nin (1) thn i Rndioactive Effluent Controls nnd Radiological Environmental -

Moni tor ing l'rograms req. ired by Section 6.8.3 and (2) doncriptlons of the information that should he includod in the Annunt Rndiological Environmental Operating and Seminnoun) RadianctIvo Effluent Knienne Report,s required by Specificntions 6.9.1.6,

6. 9.1. 7, 6. 9.1. 8 nint 6. 9.1. 9 I

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DfFINITIONS PRIMARY CONTAINMENT INTEGRITY 1.31 PRIMARY CONTAINMENT INTEGRITY shall exist when:

a. All containment penetrations required to be closed during accident conditions are either:

1. Capable of being closed by an OPERABLE containment automatic isolaticn system, or

2. Closed by at least one manual valve, blind flange, or deactivated automatic valve secured in its closed position, except as provided in Table 3.6.4 4 of Specification 3.6.4.

b. The containment equipment hatch is closed and sealed.

c. -Each containment air lock is ia compliance with the requirements of Specification 3.6.1.3.

d. The containme. . leakage rates are within the limits of Specification

3. 6.1. 2.

e. 'he suppression pool is in compliance with the requirements of

'acification 3.6.3.1.

f. ie sealing mecnanism associated with each primary containment penetration; e.g., welds, bellows or 0-rings, is OPERABLE.

PROCESS CONTR3L PROGQAM (PCP) y% DMhekCE55 C0HIROL PROGRAM snali contain the current formul . sampTTiig, M g >7- and analyses, test'l7 sacL eterminations to be made to ensg.e Aha e processing

, packaging of solid ra ice wastes baind-err Temonstrated processing of 4 actual or simulated wet solid was Cl accomplished in such a way as to assure compliance with rt 20, 10 C (FR Fart-61 10 Federal and Slat ations, burial ground requirements

% CFR Part 71 and-ather and require-mge r-genEnng the disposal of the radioactive waste. N_

PURGE - PURGlhi 1.33 PURGE or PURGING is the controlled process of discharging air or gas from a confinement to raintain temperature, pressure, humidity, concentration or other operating condition, in such a manner that replacement air or gas is required to purify the confinement.

RATED THERMAL POWER 1.34 RATED THERMAL POWER shall be a total reactor core heat transfer rate to the reactor coolant of 3833 MWT.

GRAND Gulf-UNIT 1 1-6 AmeadMMt- NO-

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PS-91/01 I, Ins. ort to Pare 1-6 ,

Insert /-

r 1.32 The PROCTSS CONTROL PROGRAM (PCP) shall contain the current !

fermulan, nampling, analyses, tent, ninl determinationn to bn made f to ensurn that proccasing and packnging of solid radionctivn wasten !

based on demount rated proconning of actual or nimulated wet nolid !

waste will be accomplished in Nnch a way as to annure compliance [

with to CFR Parts 20, 61, and 71, Stato regulations, burin) ground !

requirements, and other requiremonta governing tho disponni of I solid radionct. lyn wnstn.

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. 7 5 -98/0i DEFINITIONS _

SHUTDOWN MARGIN 1.39 5HUIDOW ERARGIN shall be the amount of reactivity by which the reactor is.

subtritical or would be subcritical assaming all control rods are fully inserted except for the single control rod of hdghest reactivity worth which is assumed to be fully withdrawn and the reactor is in the shutdown condition; cold, i.e.

68 f; and xenon free.

5ITE BOUNDARY 1.40 The SITE BOUNDARY shall be tnat line beyond which the land is neither owned, nor leased, nor otherwise controlled by the licensee.

60H0!HOAHON-

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-ship)p4ng-and but4e4-geound-twtuleemeetw1. 41 p0H0f HOAHON-she+i-be-the-co

- SOURC-E-fMEC4-D b2AA4MGE-GHMK-+ha44-be-thstua44tet4ve-ewessment-of-t-hannel-vesponse.

whee 4he-Channe4-+ ensee-49-em pos ed-t o-e-t'ed i oeet4 ve--t ourc et STAGGERED TEST BASIS 1,43 A STAGGERED TEST BASIS shall consist of:

a. A test schedule for n systems, subsystems, trains or other designated components obtained by dividing the specified test it,terval into n equal subintervals,

b. The testing of one system, subsystem, train or other designated com-ponent at the beginning of each subinterval.

THERMAL POWER I.44 THERMAL POWER shall be the total reactor core heat transfer rate to the reactor coolant.

UNIDENTIFIED LEAKAGE 1.45 UNIDENilflED LEAKAGE shall be all leakage which is not IDENTiflED LEAKAGE.

UNRESTRICTED AREA 1,46 An UNRESTRICTED AREA shall be any area at or beyond the SITE BOUNDARY ac-cess to which is not controlled by the licensee for purposes of protection of MEMBERS Of THE PUBLIC from exposure to radiation and radioactive materials, or any area within the SITE BOUNDARY used for residential quarters or for indus-trial, commercial, institutional, and/or recreational purposes.

-VENHHHON-EWmuST TREATHENT SY5H44-2ELETE]b

%~. / 1. 47AA-VW4MT4044XHA44-M EATHE41-GV4 TEM-4+-eny-+y+tte-de+49ned-and-4*sta l4ed-l 4o-eedut+-gaseous radiciedine er radicsctive materici in particulate-form-ite effivent5 by pat 3ing ventil6tien er vent esstrst geses threngh cherece4-edsee-ber; and/+r HEPA f i! tees-foe-the-purpose-of-cemov4ng-4edines-oe-paet4eulates from-the gatecus Exh50st-streem prici te the reteese te the-environment-(weh 15-system is act con 3idered te have say effect en ncble gas eff+uents). Eng44 I

meeied Lefety-Feeture (E5f-)-etmospher+e-t+eent4-sytttms-ere-not-contidered-te be-VENMAHON EXHAUST- TREAT"ENT - SYSTEM-components.

GRAND Gulf-UNIT 1 1-8 A rneAcirncCL No.

4 T's ci)/ot bCSTRUMENTATION /

\

RAD 1pACTIVE LIQUID Effluent MONITORING INSTRUMENTATION

/

LIMI NG CONDITION FOR OPERATION /

\

3.3.7.11 Aeradioactiveliquideffluentmonitoringinstrumentation hannels shown in Tablg 3.3.7.11-1 shall.be OPERABLE with their alarm / trip setpoints set to ensure That the limits of Specification 3.11.1.1 are not er eeded. The alarm /tripsetpyntsofthesechannelsshallbedeterminedinac)rdancewith the OFFSITE DOSE ALCULATION MANUAL (ODCH).

APPLICABillTY: At I times.

ACT10N: /'

a. With a radioac e liqidd effluent monitoring strumentation channel alarm / trip setpo qt less conservative than equired by the above specification, immediately suspend the rel a$e of radioactive liquid effluents monitored 4 y the affected chanp 1 or declare the channel inoperable,

b. With less than the mininNm number of adioactive liquid effluent monitoringinstrumentatio\ channels / PERABLE, take the ACTION shown in Table 3,3.7.11-1, Resto(e the OPERABLE status within the time pp/noperable ecified in the ACTION instrumentation and, if to '

unsuccessful, explain why thi'Unoperability was not corrected in a ,

timely manner in the next Semi 6qnual Radioactive Effluent Release !

Report. / \ !

/ i

c. .3 and 3.0 .4 are not applicable. !

The provisions of Specifi 'ations 3. \

SURVEILLANCE REQUIREMENTS I x I 4.3.7.11 Each radioactive. iquid effluent monitoring i strumentation channel shall be demonstrated OPEAABLE by performance of the CH tjNEL CHECK, SOURCE !

CHECK,CHANNELCAllBRAT)DNandCHANNELFUNCTIONALTESTop'erationsatthe j frequencies shown in Table 4.3.7.11-1. F

/

/ x

\

'N !'

\ .

< RANQ_ GULF-UNIT 1 3/3_3-91 N -

1

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

l TABLE 3.3.7.11-1 g (p

i S l

@ RnDI0 ACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION 3 n

I E

', MINIMUM Cl S IN ctUMENT ERABLE ACTION

1. GROSS RADI0 ACTIVITY MON PROVIDING ALARM AND AUTOMATIC TERMINATION OF REts.ASE N

Liquid Radwaste Effluent Line 1 110 a.

l

2. FLOW RATE MEASUREMENT D V ES l

111

a. Liquid Ra wa te Effluent Line Ill

$ b. D' arge Canal or Circulating Water Blowdown 1 Y

n m

/

1

. I P5 c11M [

TABLE 3.3.7.11-1 (Continued)

RADI0 ACTIVE t10V!D EFFLUENT MONITORING INSTRUMENTATION ACTION STATEMENTS I l

?

ACTION 110 - With the number of channels OPERABLE less than requiryd by the !

Minimum Channels OPERABLE requirement, effluent releases from !

this pathway may continue for up to 14 days provid d that prior i o initiating a release: !

i

a. At least two independent samples are unal ed in accordance j with Specification 4.11.1.1.1, and i l

b. A gleast two technically qualified me ers of the Facility l Statf independently verify the releb e rate calculations }

and discharge line valving; j Otherwise, s spend release of radioac ve effluents via this ;

pathway, j ACTION 111 - With the number f channels OPER LE less than required by the l Minimum Channels D ERABLE requi > ment, effluent releases via ;

this pathway may co tinue for p to 30 days provided the flow [

rate is estimated at least o e per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months during actual l releases. Pump curves may used to estimate flow. l i

i f

i I

h I

t t

I t

/ i I

i

, RAND GULF-UNIT 1 3/4 3-93 l,

.__,____~,,]

a dO iD_ N2 L

A -

LN )

EOT NI S 1 .

NTE (

ACT Q Q Q -

HN CU F -

S T

N N E O M LI -

E ET R NA )

I NR 2 U AB (

Q HI A R E CL -

R A .

C .

E C .

N A

L L .

I E E . .

V C R R A. A.

U U P N N .

S OH SC N

O

.I

.T A

T -

1 N

- E L ) )

1 M EK 3 3 .

1 U NC ( (

. R NE D 0 7 T AH S HC 3 N C I n 4 w G o E N d L I w B R o A O l T T A B .

I E N L r O E e M uR t a

T N

I F DO W

E I g U VN e e n L OO n n i F RI i i t F PT L L a E A l SN t t u .

D RI n C . n c I OM e .ue r U TR u i Q I E l E - l C I NT f D f L O f f r MC E T E o E N I

V YT e E e l I TA t M a

.T IM s E n C VO a R a A IT w U C 0 TU d S I CA a A a e g

.D A R E R A 0D M r .

R I N d d a DA i E i h A u T u q

c RM q A R i R i T SA L L N SL OA W

E O M R . L . .

U G a F a b R

T S

N . .

I 1 2 E Eo c)cG d O" ~ wb l

,!Ilj:l {il j! :l 4 . : !$ l

ps -m/m t TABLE 4.3.7.11-1 (Continued) i RADI0ACTIVELIQUIDEFfLUENTMON110 RING ;

INSTRUMENTATION ERVEILLANCE REQUIR RTRTS

[

TABLE NOTATION (1) The CHANNtl isolati FUNCTIONAL TEST shall also demonstrate that autc) atic !

any of t of this pathway and control room alarm annunciatitn occur if following conditions exists: j 1.

Instru .nt indicates measured levels above the al m/ trip setpoint. !

2. Circuit f lure. .

t

3. Instrument dicates a downscale failure.

(

4. Instrument cont is not set in operate m e, (2)

TheinitialCHANNELCA(BRATIONshallbepe(rormedusingoneormoreof the reference standards tertified by the Np fonal Bureau of Standards or i

usingstandardsthathaveyeenobtainedffomsuppliersthatparticipate !

in measurement assurance at ivities wit /NB5. These standards shall permit calibrating the syste over its ntended range of energy and {

measurement range. For subse entCHANELCAllBRATION,sourcesthathave been related to the initial cali ratJon shall be used. l

)

(3) CHANNEL CHECK shall consist of ve 'fying indication of flow during periods of release. CHANNEL CHECK shall/be ade at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months on i i

days which batch releases are 6de. '

I f

1 I

f

[

l N

?

l. ,

RAND GULF-UNIT 1 3/4 3-95 t

es; m/ci ___---

iMNm ebNDENSED. CIT 6A$ TEATHENT - EXPOE m .__% u-v'

!NSTRUMENTATION *sY6Tf

. m~ t Q J

WADIOA0HW-6ASfftMfHtifNT;mMONITORING INSTRUMENTATION LIMITING COND1110N fOR OPERAT10N

%NG

^/ 7

3. 3. 7.12 Albe-eed ioac t ivtMfateous-e4449en t-mon 4 tori ng4ns t eumenta t ion-t henneki

+ %wn-4*4eh4 e-Gr}rA le- 1-+he +44e-GPER ABBE-w i t h-t he4e-of erm/ t e4 p-se t poi nt+-

+et-to-ensure-that-the-Hmit-of - Speci f 4 cation 3.11. 2. l'ere-not-exceeded. The-e let*/4+4 p-s e t po 4 n t s-o f-opp +4eab le-chaf tne4t-s he44-be-de t e rm i ned -4 n-e eto rd a nc e m

INSERT' with-the-Ot%)h i 6 -

APPL 1CABILQ:A 4+hown-4n4eble-3r3r7-10 .

ACTION:

INTR a. With-e-radiosetive gaseous-eff%ent-monitocing-insteumetttat4on-thennel C-eletwAttip-eet point-- l c s s - c o nsette t4te-4 heft-vettu i t+d-by-t he-ebo ve-

+ pee 444 tot 4 cn , i xdiste4y-suspend-the-re4eese-of-tedionet4te geseous-

+f4hent:, monitseed-by-4he-of feeted-channe4-ce-dee4*ee-the-thenneb c Hnoperet %

XMbECT) 1 D V J b. A -With-lest-than-the-minimum-tiumbee-ef-redionet4te-geseous-ef(4uent-

on44ce4*q-4*strumentet4en-thenne4s4FEitABL E , - t eke-the-AOHON-shown-4 n4eble-3-3--7-4 2 1. Res tore-the-i nope rabl e-instettmen te t-ion-to-SPER ABt-E-ste ttts-wi thi n-t he-ti me-s peci ti ed-i n-t he-AGH 0H-e nd;--i f-mnsuccess4 u1, s. pl*+*-why-1h4+-+eopecebi444y-was-not-coeeeeted-4n-a 7

-time 4 -menner >n-the-nett-Semientme4-@edionet4te-ff44uent-Release-4teport.

c. The provisions of Specifications 3,0.3 and 3.0.4 are not applicable.

SURVEILLANCE

- REOUIREMENTS l

! T N SE C.T l

E i -

4. 3. 7.12A4*eh-ead40*ethe geseous-e(44uent-sen4 tee +tig-4**trumentat4<m-@anel sha444sken+1+ated-04E4ABL E by- pet 4eemance o f-4he-fHANNEl-Cif f" S0lMC4i-StfECt-C-tfANNtt-oat-fBRAHON end-C4iANNEt-f-UNOHONAt-4CSI eperatiens-at- the-4+equenc4e&-+hown-4n-4eb4e 4. 3. 7.12- 1.

c-INECT >

! p-AA6ee@ee444eet4co-3-11. 2. C end 3.-H-e--7-4oe-the-Exp4esive-6et-Honitte-and-

-O f4get-P retteoteent-Honi t oe-H m its--

(til GRAND GULF-UNIT 1 3/4 3- T Amend mc61 b30.

i PS 91/01 !

Inaer.t_to.P_aAeJ/,4J i91 i

insert A: -l At_ least one explosivo gas monitoring system instrumentation channn) of I thn main condensor of fgns treatment system shall ho OPERADI.E with it s j alnrm setpoint set to ensure that. the limit. of Specification 3.11.2.6 is i not nxceeded.

6 i

Insert Bt l

During main condensor offgns treatment system operation l Insert C:

t With thn explosivn_ gas monitoring system instrumentation chnnnel nlarm notpoint of _the r.nin condenser of fgns trentment system inns conservntivo f than requirnd by Specificat ion 3.11.2.6, declare the channel inopornble and take the ACTION requirnd below. ;

l Insort D: !

With less than ono nxplosivo gas monitoring system lustrumentation channel of thn main condensor of fgan trentment system OPERABhE, j operation of the main condenser of fgns trnatment system may continun for [

up to 30 days provided grab namplos arn collected at least onco per 4 l hours and annlyr.ed within thn following 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months . Rostorn thn inopernhin l instrumentation to OPERAlthE status within 30 days and, if unsuccessful, preparn and submit n Special Report to thn Commission pursunut to Specification 6.9.2 to nxplain why this inopernbility was not corrected ,

in a timely manner. j i

6 Insert E: [

Each explosive gns. monitoring system instrumentatlon chennn) of the main .[

condenser of fgas treatment system shall bo demonst.rnted OPERABhE by j pnrformnnen of-n CilANNEh CllECK nt least onco per 24 houta, a CilANNEh ;

CAh1 BRAT 10N* nt lonst onco por 92 dnys and n CilANNEh FUNCTIONAh TEST nt. !

least. onco per 31 dnys. j r

Insert F: !

l

Thn CilANNEh CAhlfsRATION shall includo the use of standard gas samples h conta.ining a nominnl: [

1. Ono volume pntcent hydrogen, balance nitrogen, and i

2. Four volume pnrennt hydrogen, balanco nitrogen. }

6 I

M9104241/SN'blCFhR - 8 i

-i N<A+--., . --.-- -----.--.....--~.~-,.--.....---..---+.-.-,.,,---..-...-----,.n-- -

i i

4

l. '

l' -

TABLE 3.3.7.12-1 'g o

-(P l

$ RADI0 ACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION =

5 S

, o %

} E MINIMUM CHANNELS O l T NSTRUMENT

" OPERABLE APPLICABILITY ACTION

e

z-i Z 1. RADWASTE B L1 DING VENTILATION

, - MONITORING 3 STEM

1 l a. Noble Gas Act ity Monitor -

Providing Ala 1

121

b. Iodine Sampler 1

122 l c. Particulate Sampler 1

122

d. Effluent System Flow Rate

i: ' Measuring Device 1

123 Y e. Sampler Flow Rate Measuring Device 1 123

~

O L

2. MAIN CONDENSER OFFGAS TREATMENT SYSJG1 EXPLOSIVEGASMONITORINGSYSTEfV

a. Hydrogen Monitor 1 124

3. CONTAINMENT VENTILATIOff MONITORING SYSTEM i a. Noble Ga Activity Monitor Providing Ala 1

121

b. I dine Sampler 1 122

.. Particulate Sampler'- 1 122

/ d. Effluent System Flow Rate Monitor 1 123

e. Sampler Flow Hate Monitor 1 123

\

4

!,.._,..-_.,.-,,..-,__,-_.-.-.-,.---.---.--,---.-. -4.~---- -- - - -- - -- - - - - - - - - - - - - - ' - ~ ~ - - - ~ = ~ ~ ' - - ~ - - - - - ~ - - ~ ~ - ~ - - " " - " ~ ~ - ' ' " " ~ "

e d

N TABLE 3.3.7.12-1 (Continued) g E (.A RADI0 ACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION E 3 5 %

c MINIMUM CHANNELS

/ 2 INSTRUMENT OPERABLE APPLICABILITJ ACTION

~

4 TURBINE BLDG. VEN 11.ATION MONITORING SYSTEM

a. Noble Gas Activity M i(or 1 121

b. Iodine Sampler 1 122

c. Particulate Sampler -

122

d. Effluent System Flow Rate Monitor 1 123

e. Sampler Flow Rate Monitor 123

5. FUEL HANDLING AREA VENTILATI MONITORING SYS1EM I

a. Noble Gas Actiyit'y Monitor 1 121

b. Iodine Samp r 1 122

c. ate Sampler 1 122 Pap

d. Flow Rate Monitor 1 123

e. Sampler Flow Rate Monitor 1 123

. . ~ . . , - - . - .. .-- .. . - , , . . . . - - -, ,. _.-- . - . - - . . - - - - . ,

E TABLE 3.3.7.12-1 (Continued)

E RA010 ACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION p NO MINIMUM CHANNELS ~

E AF CASILITY ACTION OPERABLE f.

INSTRUMENT \

6. OFFGAS PRE-TREATMENT MONITOR

- - 126

a. Noble Gas Activity Monitor 1

7. OFFGAS POST-TREATMENT MONI10R

a. Noble Gas Activity itor w Providing Al and Automatic ** 125 2 Terminat' of Release 2

$- 8. STANDBY AIAS TREATMENT EXHAUST -

tiONITORING SYSTEM (A&B)

2/

a. Noble Gas Activity Monitor 1/ system N_

i i

i

a x TABLE 3.3.7.12-1 (Continued) 1)

E O o RADI0 ACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION 8 o _D c

G \O

E MINIMUM CHANNELS E

INSTRUMENT OPERABLE AP CABILITY ACTION

-4

6. OFFGAS PRE-TREATMENT MONITOR f

a. Noble Gas Activity Monitor 1 126 7 OFFGAS POST-TREATMENT MONITOR

a. Noble Gas Activity - itor w Providing Al and Automatic 2 Terminat~ of Release 2 **

125

8. STANDB - S TREA1 MENT EXHAUST TORING SYSTEM (A&B)

a. Noble Gas Activity Monitor 1/ system

27 N

t

% ~ Rl/D I TABLE 3. 3. 7.12-1 (Continued) f RADIOACTIVE GASEOUS EfflUEN1 MONITORING INSTRUMENIATION t i

TABLE NOTATION At all times.

" Duri q main condenser offgas treatment system operation. f

'" During operation of the main condenser air ejector.

ACTION 121 - With the number of channels OPERABLE less than requ ed by the {

inmum Char,nels OPERABLE requirement, ef fluent rel ases via this ;

s pd hway may continue for up to 30 days provided 9 ab samples !

are taken at least once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months and these sainples are I anal ed for gross activity within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months . f ACTION 122 - With t . number of channels OPERABLE less tt n required by the l Minimum %hannel5OPERABLErequirement,eff ent releases via this pathway may continue for up to 30 d s provided samples f are contin . usly collected with auxilia sampling equipment as l required by able 4.11.2.1.2 1. j i

ACil0N 123 - With the number of channels OPERABLE less than required by the Minimum Channe1\ OPERABLE requirem> t, effluent release via this ;

pathwaymayconthueforupto30 ays provided the flow rate !

is estimated at letst once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months . ,

r

\

ACTION 124

With the number of channels OP RABLE less than required by the )

MinimumChannelsOPERAQLEre irement, operation of main condenser i offgas treatment syste gmay continue for up to 30 days provided ;

grab samples are collecth at least once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months and analyzed (

within the following 4 rs- l ACTION 125 - a. With one of the uire<1 monitors inoperable, place the ;

inoperable chan 1 in th downscale tripped condition i with'n one hou .

b. With both of he required m 11 tors inoperable, effluent !

releases vi this pathway ma continue for up to 30 days [

provided ab samples are take at least once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months and thes samples are analyzed r gross activity within 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months . j ACTION 126 - With the mber of channels OPERABLE lest than required by the [

Minimum iannels OPERABLE requirement, th' SJAE effluent may be ;

releas to the environment for up to 72 h rs provided: l

a. he offgas system is not bypassed, excep for filtration f system bypass during plant startups, and j b .The offgas delay system noble gas activity hffluent downstream monitor is OPERABLE; ;

i Otherwise, be in at least HOT SHUT 00WN within 12 hou s, and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months . .

ACTION 12 -

With the-number of channels OPERABLE less than require \y the b [

Minimum Channels OPERABLE requirement, effluent releases via l this pathway may continue for up to 30 days provided grab l samples are taken at least once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months and these sampi s i are analyzed for gross activity within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months . (

i

, RAND Gulf-UNIT 1 _

3/4 3-100 f

..l .- _ -,_.._.___._..__._,._._-._,___,,..._,..,_,___._,,.._~,,,_,..,.____m.,_-...--.._ , . .

o N(p i 3 -

I' l if fi !3 ,{& ! I '

H CE I C HND WAE LR NLI

IIU * * * * * * * * *

EQ sVE ERR DU O

M S

T N

E L M A E LN R EOT ) . . ) . ) . ) .

I NIS 2 A 5 2 5 U NTE ( A. ( A. ( A.. A. ( A.

Q ACT Q N. N Q N M N N Q N E HN -

R CU F

E C

N A -

L L N I O E LI V ET ) . . ) ) . .

R NA 3 4 3 A A.

U NR ( A. ( (

S AB A 4 N R R Q A N. N R R N

HI CL /

O A I C T

A T

N 1 E

- M EK 2 U CC . . . . . . . .

1 R RE

. T UH A. A. A. A. A. A. A. A. A.

7 S OC M N N N N N M N N N N N S 3 I /

4 G .

N N E I L

B R

O L

EK \

A T NC T I N

NE AH D W W D D D W W D D O HC M C /

T N

E U

L - G F N F r TI r E o r NR o e r N t o EO t t o S O i t MT i a t U I n i TI n R i O T o n AN o n E A M o EO M w o S L r M RM r o M A I e T N y e l G T m l r e S O t m l F e N i r p o t SA r I i r p t E E va m t a AG o T ta m m a V VM il r a i R G t AM Jl r a e R I tA e S n FE i LE t A e S t T GT c l o w FV n IT c l s w C Ns Ag p e M o OI o TS A p e y o A IY n m t l S M NY n m t S l 0 DS si a a e F RO ES si a a r F I L ad S l t EL n V ad S l t o D IG Gi u a r SP e G Gi u nt r A UN v e c R e NX g TN v c ei e R BI eo n i l p

EE r

o NI eo i t

un l p

R l r i t w D ER l r i l o EO bP d r o m NMM d MO bP d r fM m TT o o a l a OEE y NT o o a f a SI N I P F S CTT H II N I E S T AN SS AN N WO NYY TO E f; M ISS NM M A . . . . . A . O . . . . .

U R a b c d e M a C a b c d e R

T N S N .

N I 1 2 3 N hJ,= {c" [ wD w0S /

TABLE 4.3.7.12-1 (Continued)

RADI0 ACTIVE GAL 10US EIFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS ,

.2

, D k CHANNEL MODES IN WHICH $

L CHANNEL SOURCE CHANNEL SURVEILLANCE S FUNCTIO [N:

}

INSTRUMENT -

CHECK CHECK CALIBRATION TE.5 REQUIRED

4. TURBINE BLDG. VENTIL ON MGNITORING SYSTEM g

a. Noble Gas Activity Monitor D M 3) Q(2)

b. Iodine Sampler W N.A. N.A. N.A.

c. Particulate Sampler N . rL A. N.A.

w d. Flow Rate Monitor D N.A. R Q(5) h

w e. Sampler Flow Rate Monitor N.A. R N. A.

O 2

5. FUEL HANDLING AREA VENTILATIC MONTORING SYSTEM

a. Noble Gas Acti y Monitor D M A(3) Q(2)

b. Iodine .pler W N.A N. A. J.

c. P. ticulate Sampler W. N.A. N.A. N.A.

Flow Rate Monitor D N.A. R Q(5)

e. Sampler Flow Rate Monitor D N.A. R N.A.

TABLE 4.3.7.12-1 (Continued) g x

,E x\ N RADI0 ACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS th S

/

CHANNEL MODES IN WHIC'n h CHANNEL SOURCE CHANNEL /, FUNCTIONAL SURVEILLANCE -

E-INSTRUMENT CHECK CHECK CALIBRAIIC# TEST REQUIRED

}

6. OFFGAS PRE-TREATMENT MONITOR

a. Noble Gas Activity Monitor D 7[ A(3)" Q(2) f

7. OFFGAS POST-TREATMENT MONITOR

a. Noble Gas Activity Moni or 1 j

l Providing Alars an'd Auto-matic TermiWation of Release D M A(3),, Q w . N( 1) g p/

w 8. STANDBY,GA5 TREATMENT EXHAUST 4 PDNG0 RING SYSTEM (A&B)

O A(3) Q(2)

/ a. Noble Gas Activity Mcnitor D M

p$ c; \/(p TABLE 4.3.7.12-1 (Continued)

RADI0 ACTIVE GASEOUS EFFLUENT MONITORING 1RSTRUMENTAT10N SURVEILLANCE REQUIREMENTS ,/

TABLE NOTATION /

At a si times.

- N During tnain condenser of fgas treatment system operation.

- - During op\ eration of the main condenser air ejector.

\ /

/

durationifuna\edeferredtothenextshutdownofgreaterthan8huurs SOURCE CHECK may ble\to be performed at the monthly interval due to inaccessibility bechuse of being in a high radiation area.

N The sensor will be cal brated for mr/hr or cpm f rom t'he /

calibration standard.

The conversion to releas's rate will be performed during subsequent unit-opera-tion, but within one week (1) The CHANNEL FUNCTIONAL TEST shall also demopstrate that automatic isolation of this pathway and control room alarm anr3 d nciation occurs if any of the following conditions o ists: j/

1. Instrument indi;4tes meas ed levpis above the alarm / trip setpoint.

2. Circuit failure. !

/

3. Instrument indicates a downsch e failure.

4. Instrument controls not set /in(operate mode.

/ \

(2) The CHANNEL FUNCTIONAL TEST sh'all also ' demonstrate that control room alarm annuciation occurs if any o the followiftg conditions exists:

1. Instrument indicates easured levels above the alarm setpoint.

2, Circuit failure.

3.

Instrumentindieptesadownscalefailure.

4. Instrumentcon)tolsnotsetinoperatemode.

(3) The initial CHANNEf. CAllBRATION shall be performed ing one or more of the reference sta'ndards certified by the National Bureau of Standards (NBS) orusingstanda/dsthathavebeenobtainedfromsupplikrsthatparticipate

/

I i

in measurement assurance activities with NBS. These standards shall permit calibrating the system over its intended measurement rang'e. For subsequent l CHANNELCA){BRATION,sourcesthathavebeenrelatedtothe nitial calibrati,pn shall be used.

(4) The CHANNEL CAllBRATION shall include the use of standard gas samples

, contajiing a nominal:

1. One voluine percent hyorogen, balance nitrogen, and 2,/ Four volume percent hydrogen, balance nitrogen.

(5)((omparethemeasuredflowratetotheexpecteddesignflowratef existing plant conditions.

/

/2RANDGULF-UNIT 1 3/4 3-104 ~

vs -m/c, 3/4.3.8 PLAN 7 SYSTEMS ACTUATION INSTRUMENTATf0N INSTRUMENTATION I

3/4.3.8 PLANT SY$TEMS ACTUATION INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.8 The plant systems actuation instrumentation channels shown in Table 3.3.81 shall be OPERABLE with their trip setpoints set consistent with the values shown in the Trip Setpoint column of Table 3.3.8-2.

APPLICABILITY: As shown in Table 3.3.8 1.

ACTION:

a. With a plant system actuation instrumentation channel trip setpoint less conservative than the value shown in the Allowable Values column of Table 3.3.8-2, declare the channel inoperable and take the ACTION required by Table 3.3.8-1.

b. With one or more plant systems actuation instrument channels in-operable, take the ACTION required by Table 3.3.8-1.

SURVEILLANCE REQUIREMENTS ._

4.3.8.1 Each plant system actuation instrumentation channsi sn'.11 be demonstrated OPERA 8LE by the performance of the CHANNEL CHECK, CHANNEL FUNCTIONAL TEST and CHANNEL CALIBRATION operations for the OPERATIONAL CONDITIONS and at the frequencies shown in Table 4.3.8.1-1.

4.3.8.2 LOGIC SYSTEM FUNCTIONAL TESTS and simulated automatic operation of all channels shall be performed at least once per 18 months.

l

l. GRAND GULF-UNIT 1 3/4 3-f0$- Amendmed fJo -

l

N LA c) TABLE 3.3.8-1 PLANI SYSTEMS ACTUATION INSTRUMENTATION

@ MINIMUM APPLICA8LE 7,

a TRIP FUNCTION OPERABLE PER TRIP SYSTEM g OPERATIONAL CONDITIONS ACTION 3*

- 1. CONTAINMENT SPRAY SYSTEM w

a. Drywell Pressure-High 2 1,2,3 130

b. Containment Pressure-High 1 1,2,3 131

c. Reactor Vessel Water level-Low Low Low, Level 1 2 1,2,3 130

d. Timers

1) System A I 1, 2, 3 131

2) System B 1 1,2,3 131

2. FEEDWATER SYSTEM / MAIN TUR8INE TRIP SYSTEM

a. Reactor Vessel' Water Level-High, tevel 8 3 1 132

$5I LI 3. SUPPRESSION POOL MAKEUP SYSTEM

a. Drywell Pressure - High (ECCS) 2 1,2,3 135

b. Drywell' Pressure - High (RPS) 2 1,2,3 135

c. Reactor Vessel Water Level - Low Low Low, Level 1 2 1,2,3 135

d. Reactor Vessel Water Level - Low Low, Level 2 2 1,2,3 135 y e. Suppression Pool Water Level - Low Low 1 1,2,3 133 E

g f. Suppression Pool Makeup Timer 1 1,2,3 133 3 g. SPMU Manual Initiation 2 1,2,3 134

.N 8

(a)A channel may be placed in an inoperable status for up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months during periods of required j surveillance provided at least one other OPERABLE channel in the same trip system is moni*oring that parameter.

I

P5 -9 t/of TABLE 3.3.8-1 (Continued)

PLANT SYSTEMS ACTUATION INSTRUMENTATION ACTION i 1

ACTION 130 - a. With the number of OPERABLE channels one less than required by the Minimum OPERABLE Channels per Trip System requirement, place the inoperable channel in the tripped condition within one hour; otherwise, declare the associated containment spray system inoperable and take the action required by Tech-nical Specification 3.6.3.2.

b. With the number of OPERABLE channels two less than required by the Minimum OPERABLE channels per Trip System require-ment, declare the associated containment spray system inoperable and take the action required by Technical Specification 3.6.3.2.

ACTION 131 - With the number of OPERABLE channels less than required by the Minimum OPERABLE Channels per Trip System requirement, restore the inoperable channels to OPERABLE status within one hourt other-wise, declare the associated containment spray system inoperable and take the action required by Technical Specification 3.6.3.2.

ACTION 132 - For the feedwater system / main turbine trip system:

a. With the number of OPERABLE channels one less than required by the Minimum OPERABLE Channels requirement, restore the inoperable channel to OPERABLE status within 7 days or be in at least STARTUP within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months ,

b. With the number of OPERABLE channels two less than required by the Minimum OPERABLE Channels per Trip Systcm require-ment, restore at least one of the inoperable channels to OPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months or be n at least STARTUP within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

ACTION 133 - With the number of OPERABLE channels less than required by the Minimum OPERABLE Channels per Trip System requirement, declare the associated suppression pool makeup system inoperable and take the action required by Specification 3.6.3.4.

ACTION 134 - With the number of OPERABLE channels less than required by the Minimum OPERABLE Channels per Trip System requirement, restore the inoperable channels to OPERACLE status within 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months ; other-wise, declare the associated suppression pool makeup system inoperable and take the action required by Specification 3.6.3.4.

ACTION 135 - With the number of OPERABLE channels less than required by the Minimum OPERABLE Channels per Trip Function requirement:

a. With one channel inoperable, place the inoperable channel in the tripped condition within one hour or declare the associated system (s) inoperable.

b. With more than one channel inoperable, declare the associated system (s) inoperable.

GRAND GULF-UNIT 1 3/4 3-10F Amendment No. 69,

S U

.L o %

5 TALE 3.3.8-2 O._

E E PLANT SYSTEMS ACTUATION INSTRimENTATION SETPOINTS G

E- 1 RIP FUNCTION ALLOWABLE 5 TRIP SE1 POINT VALUE

] 1. CONTA!NNENT SPRAY SYSTEM

a. Drywell Pressure-High

b. 1 1.39 psig i 1.44 psig Containment Pressure-High 1 7.84 psig

c. Reactor Vessel Water Level-tow $ 8.34 psig Low Low, Level 1

d. Timers 1 - 150.3 inches 1 - 152.5 inches

1) System A

2) Systen B 10.85 1 0.10 minutes 10.26 - 0. 00, + 1.18 minutes 10.85 1 0.10 minutes ** 10.26 - 0.00, + 1.18 mi:=utes w 2. FEEDWATER SYSTEM / MAIN TUR8INE TRIP SYSTEM N

y a. Reactor Vessel Water Level-High, Level 8 55 i inches * $ 54.1 inches

3. SUPPRESSION POOL MAKEUP SYSTEM

~

. a. Drywell Pressure - High (ECCS) 1 1.39 psig i 1.44 psig

b. Drywell Pressure - High (RPS) $ 1.23 psig i 1.43 psig

c. Reactor Vessel Water Level - Low Low Low, Level 1 1 -150.3 inches

1 -152.5 inches

d. Reactor Vassel Water Level - Low Low, Level 2 1 -41.6 inches

2 -43.8 inches y e. Suppression Pool Water Level - Low Low 3 17 ft 5 inches 1 17 ft 2 inches S f. Suppression Pool Make p Timer

$ 29.0 minutes < 29.5 minutes k g. SPMU Manual Initiation MA 3 NA E

~ .

See Bases Figure B 3/4 3-1. '

[ **Setpoint for System B is the sum of E12-K0938 plus E12-K116.

E12-Kil6 is not to exceed 10.00 seconds.

a

dv.

_O j TABLE 4.3.8.1-1 O 2

PLANT SYSTEMS ACTUAI!ON INSTRUMENTATION SURVEILLANCE REQUIREMENTS E

5 c CHANNEL OPERATIONAL 35 CHANNEL FUNCTIONAL CHANNEL CONDITIONS IN WICH

] TRIP FUNCTION CHECK TEST CALIBRATION SURVEILLANCE REQUIRED

1. CONTAINNENT SPRAY SYSTEM

a. Drywell Pressure-High 5 M RI *I 1, 2, 3

b. Containment Pressure-High 5 M R(a) 1, 2, 3

c. Reactor Vessel Water Level -

Low Low Low, Level 1 5 M RI ") 1, 2, 3

d. Timers MA M Q 1, 2, 3 M 2. FEEDWATER SY3 TEN / MAIM TUR8INE TRIP

[ SYSTEM h% a. Reactor Vessel Water Level-High, 5 M R 1 Sig Level 8

3. SUPPRESSION POOL MAKEUP SYSTEM

a. Drywell Pressure - High'(ECCS) S M RI *I 1, 2, 3

b. Drywell Pressure - High (RPS) S M RI *) 1, 2, 3

c. Reactor Vessel Water Level - Low Low Low, Level 1 5 M RI *) 1, 2, 3 3I d. Reactor Vessel Water Level - Low

$ Low, Level 2 5 M RI *) 1, 2, 3 a

$ e. Suppression Pool Water Level - 5 M RI *) 1, 2, 3

[ Low Low P .f. ' Suppression Pool Makeup Timer NA M , Q 1, 2, 3

g. SPMU Manual Initiation NA R NA 1, 2, 3 1

(a) Calibrate trip unit at least once per 31 days. j

T35 - 91/01 ]

INSTRUMEN7AT10N 3/4.3.9 TURBlNE OVERSPEED PROTECTION SYSTEM LIMITING CONDITION FOR OPERATION 3.3.9 At least one turbine overspaad protection system shall be OPERABLE.

APPLICABILITY: OPERATIONAL CONDITIONS 1 and 2.

ACTION;

a. With one stop valve or one control valve per high pressure turbine steam line inoperable and/or with one stop valve or one control valve per low pressure turbine steam line inoperable, restore the inoperable valve (s) to OPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months or close at least one valve in the affected steam line. Otherwise isolate the turbine from the steam supply within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

-b. With the above required turbine overspeed protection system otherwise inoperable, within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months isolate the turbine from the steam supply.

l I

SURVEILLANCE REQUIREMENTS .

a.3.9.1 The provisions of Specification 4.0.4 are not applicable.

4.3.9.2 The above required overspeed protection system shall be demon- i strated OPERABLE:

a. At least once per 14 days by cycling each of the following valves through at least one complete cycle from the running position using i the manual test or Automatic Turbine Tester (ATT): [

-1) Four high pressure turbine stop valves, * '

2) Four high pressure turbine control valves. ,

3) Six low pressure turbine stop valves, and

4) Six low pressure turbine control valves. l b.- At least once per 14 days by testing of the two mechanical overspeed !

devices using the Automatic Turbine Tester or manual test. ,

c. At least once per 40 months by disassembling at least one of each of the above valves and performing a visual and surface inspection of i valve seats, disks and stems and verifying no unacceptable flaws. ?

If unacceptable flaws are found,_all other valves of that type shall be inspected.

t b

GRAND GULF-VNIT 1 3/4 3 110- A m e,vi m ewi M D. __ j i

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Pages 3/4 3-111 and'3/4 3-112/Intentiona11y Deleted ~

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GNANDGULF-UNIT 1 3/4 3 -111 Amendment No,'62 m._.-_.__.____ _ ._._...

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w -m/ci -

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N/4.11 RAD 10ACilVE EFFLUENTS !

3 11.1 LIQUID EFFLUENTS CONC TJATION l.

tlMITING NDITION FOR OPERATION ,

i 3.11.1.1 The - ncentration of radioactive material released in iquid i effluentstoUNASTRICTEDAREA5(seefigure5.1.3-1)shallbe/imitedto !

the concentration specified in 10 CFR Part 20, Appendix _0, able !!,

Column 2 for radio yclides other than dissolved or entrain noble gases, for dissolved or entXained noble gases, the conctnt ration hall be limited !

to 2 x 10 4 microcuriks/mi total activity. ;

APPLICABILITY: At all t mes, h

ACTION: !

l With the concentration of radipactive material ry eased in liquid effluents !

to UNRESTRICTED AREAS exceedintjsthe above limitg, immediately restore the I concentration to within the abovh limits, i

l SURVEILLANCE REQUIREMENTS -

y 4.11.1.1.1 The radioactivity cont N

of es h batch of radioactive liquid 3 waste shall be determined prior t release sampling and analysis in accord- i ance with Table 4.11.1.1.1-1. Tjt results of pre-release analyses shall be used !

sure that the concentration at !

with the calculational the point of release is maint methods Jn thethe ined within ODCM l to a(imits of Specification 3.11.1.1.

[

i 4.11.1.1.2 Post-release a lyses of samples compos ed from-batch releases l shall be performed in acc dance with Table 4.11.1. -1. The results of the !

radioactivity analysis 11 be used in accordance wi~ the methodology 3 and parameters in the CM to assure that the concentra ions at the point of release are maintaine 'within the limits of Specificatio 3.11.1.1. l l

L i

k

, RAND GULF-UNIT 1 _

3/4 11-1

. j

?$-91/cl TABLE 4.11.1.1.1-1 f RADI0 ACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAM l

i Minimum Type of LodrLimit i Liquid R lease Sampling Analysis Activity o Detection l Type Frequency Fiequency Analysis (LLD) ;

(pCi/ml),

\

7 A, Batch Waste P P Principa !mma 5x10 Releage Each batch Each Batch Emitters Tanks

-6 1-13 1x10

-5

\ M D olved and 1x10 OneBakh/Mt f trained Gases K /(Gammaemitters)

-5 P M H-3 1x10 Each Batch 'ompos (e b

~7 Gross Alpha 1x10

-8 P

Each Batch Composit Q\ b Sr-89, Sr-90 5x10

-6 Fe-55 1x10

~7 B. SSW Basin (prior to Eac /

/ Each Batch incipafGamma Em'tters 5x10 blowdown) B down 1-131 1x10 r

1

\

3/4 11-2 G AND GULF-UNIT.1

\

i

l P5 - 9 t/or TABLE 4.11.1.1.1-1 (Continued)

RADILACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGRA_M TABLE NOTATION

a. The LLD is the smallest concentration of radioactive material in a ample that .ill yield a n6t count (above system background) that will by detected with . % probability with only 5% probability of f alsely conclucifng that a blank bservation represents a "real" signal.

For a part'cular measurement system (which may include radiothemical separation).

4.66 s b ll0 * - V 2.22 x 10' /

[

exp(-Aat)7 E Y -

J' where ,

[

LLD is the "a 'ori" lower limit of detegtion as defined above (as pCi per unit ass or volume). (Currpnt literature defines the I LLD as the det tion capability for/the instrumentation only, and the MDC, mi. mum detectable cohcentration, as the detection capability for a en instrumenf, procedure, and type of sample.)

s b

is the standard devi tion of t6e background counting rate or of the counting *Jte of blank sample as appropriate (as counts per minute)

/

E isthecountingefficiepcy(ascountsperdisintegration)

V is the sample size ( units of mass or volume) 2.22 x 106 is the number of d% integration per minute per microcurie

/

Y is the fractional radiochemical y1 Id (when applicable)

/

A is the radioac'tive decay constant fo the particular radionuclide At is the elas~/ ped time between sample coll ction (or end of the samplecpilectionperiod)andtimeofcobting The value of sh t>ted in the calculation of the LLD fo a particular measurementsy5/emshouldbebasedontheactualobser d variance of the background couriting rate or of the counting rate of the lank samples (as appropriate)ff ather than on an unverified theoretically edicated variance.

Typical values of E, V, Y and at should be used in the calcu tion.

Itshoy!dberecognizedthattheLLDisdefinedasanapriori before the fa6t) limit representing the capability of a measurement sys em and not as a posteriori (after the fact) limit for a particular measu yment.

/

G ND GULF-UNIT 1 3/4 11-3

PS-9l[Ol-TABLE'4.11.1.1.1-1 (Continued)

RADI0 ACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAM TABLE NOTATION (Continued) i i

i

b. A co osite sample is one in which the quantity of liquid samp ed is pronor ional to the quantity of liquid waste discharged and-i which the i method f sampling employed results in a specimen which is r presentative l

-of the 1 uids released. !

c. A batch rel se is the discharge of liquid wastes of a screte volume. [

Prior to samp ing for analyses, each batch shall be is ated, and then i thoroughly mix to' assure representative sampling. ;

-d. The principal gam a emitters for which the LLD spe ification applies [

exclusively are th following radionuclides: Mn- 4, Fe-59, Co-58, Co-60, i Zn-65, Mo-99, Cs-134 Cs-137, Ce-141, and Ce-14 . This list does not mean that only these clides are to be detec d and reported. Other '

peaks which ar.? measura le and identifiable,f ogether with the above nuclides, shall also be entified and repo ted. !

i 1

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/

I 1

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i t

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3/4 11-4 QNAND GULF-UNI _T 1 \ f

4 T5-9i/ol MDI0ACTIVEEFFLUENTS 005 LIMITIN CONDITION FOR OPERATION 3.11.1,2 materials Th& dose or dose commitment eachtoreactora MEMBER unit, t / af THE PUBL AREAS (seein l' quid effluents released, from Figu 5.1.3-1) shall be limited: UNRESTRICTED

a. During a total boa calendar quarter to less than or equal tp 1,5 mrem to the and to less than or equal to 5 mrem to any organ, and b.

During any ca endar year to.less than or equal 3 mrem to the total body and to less than or equal to 10 mre to any organ.

A PLICABILITY: At all times.

ACTION:

a.

With the calculated dosg from the relgese of radioactive materials submit to the Commission (* thin f 30in liquid effluents exce ding any tion 6.9.2,aSpecialRepo(r exceeding the limit (s) and whict d(efinthe identifies )/ays, pursuant cause(s) for to Spec been taken to reduce the releh jfs the corrective actions that have taken to casure that future ry sses and the corrective actions to be will be in compliance with the above limits. This Special epo of radiological analyses of the d snall also include (1) the results radiological impact on fi shed dri king water source and (2) the to the requirements of 4 CFR Part 1 ing

water supplies with regard

b. The provisions of Spect fication 3.0.3 a not applicable.

SURVEILLANCE REQUIREMENTS 4.11.1.2 Dose Calculat ons. Cumulative dose contributions from liquid effluents for the current caler)dar quarter and the current calendar yea ( shall be determined in accordance with the methodology and parameters of the 00CM et least once per 31 days.

"Applicab'le only if drinking water supply is taken from the receiving wate body thin 3 miles downstream of the plant discharge.

GRAND GULF-UNIT 1 3/4 11-5 Amendment No. 69 \

o P6 -91/01 MOI 0ACTIVFEFFLUENTS LI 10 WASTE TREATMENT LIMITIN CONDITION FOR OPERATION 3.11.1.3 Th liquid radwaste system shall be used to reduce the p dioactive materials in quid wastes prior to their discharge when the profected doses due to the lig (d effluent from each reactor unit to UNRESTRICTED AREAS (see Figure 5.1.3-1) 4 uld exceed 0.06 mrem to the total body or 0 d mrem to any organ, in a 31-da period.

APPLICABILITY: At a times.

ACTION:

a. With radioactive liquid waste being disch ged without treatment and in excess of e above limits, prepa and submit to the Commis-sion, within 30 da pursuanttoSpecifjation6.9.2,a$pecialReport which includes the fallowing informati n:

1. Explanation of wh liquid radwette was being discharged without treatment, identifi s tion of a'ny inoperable equipment or subsystems, which res tedifliquidradwastebeingdischarged without treatment, an h eason for the inoperability, and

, 2. Action (s) taken to resto the inoperable equipment to OPERABLE status, and

3. Summary description f action s) taken to prevent a recurrence,

b. The provisions of Spec"fication 3.0. are not applicable.

SURVEILLANCE REQUIREMENTS

/

4.11.1.3.1 Doses due to liquid releases from each reactgr unit to UNRESTRICTED

\

AREAS shall be projectaid at least once per 31 days, in accordance with method-ology and parameter n the 00CM.

4.11.1.3.2 The irystalled liquid radwaste system shall be dem strated OPERABLE by meet hg Specifications 3.11.1.1 and 3.11.1.2.

/

ARAND GULF-UNIT 1 3/4 11-6 Amendment No. 69 ;

I

- _ _ _ _ - - _ _ _ _ _ _ _ - - - - - _ _ - _ _ - - _ - - - _ _ _ - - - _ _ _ - - - - - - - - ---- - -- A

l g RADI0 ACTIVE EFFLUENTS LIQUID !!0 LOUP TANKS ' Q-LIMITING CONDITION FOR OPERATION 3.11.1.4 The quantity of radioactive material contained in any outside tempo-rary tank, not including liners for shipping radwaste, shall be limited to less than noble gases. or equal to 10 curies, excluding tritium and dissolved or entrained APPLICABILITY: At all times.

ACTION:

a.

With the quantity of radioactive material in any of the above specified tanks exceeding the above limit, immediately suspend all additions of radioactive material to the tanks and within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months reduce the tank contents to within the limit, and describe the events leading to the condition in the next Semiannual Radioactive Effluent Release Report.

b.

The provisions of Specification 3.0.3 are not applicable.

SURVEILLANCE REQUIREMENTS 4.11.1.4 The quantity of radioactive material contained in each of the above specified tanks shall be determined to be within the above limit by analyzing a representative sample of the tank's contents at least once per 7 days when radioactive materials are being added to the tank.

N GRAND GULF-UNIT 1 3/4 11-7 b

Amendment No. 69, __.

I ____________ - - - - - - - - - - - - - - - - -- -

c PS - 91/01 MDI0 ACTIVE-EFFLUENTS 3/ 11.2 GASEOUS EFFLUENTS DOSE ATE LIMITING NDITION FOR OPERATION ,

3.11.2.1 The qse rate due to radioactive materials released i gaseous effluents from the site to areas at and beyond the SITE BOUND Y (see Figure 5.1.3-1) sh 11 be limited to the following: ,

a, For noble ses: Less than or equal to 500 mre yr to the total body and les than or equal to 3000 mrem /yr to he skin, and

b. For all iodine 31, iodine-133, tritium and 11 radionuclides in i particulate form with half lives greater t an 8 days: Less than or .

equal to 1500 mre yr to any organ.

APPLICABILITY: At all times. l ACTION:

\

With the dose rate exceeding the abo e lim s, immediately decrease the release rate to within the above limit (s).

SUREVEILLANCE REQUIREMENTS / ,

4.11.2.1.1 The dose rate due to oble gases i gaseous effluents shall be determined to be within the abo e limits in acc dance with the methodology and t parameters of the ODCM. I 4.11.2.1.2 - The dose rate () e to iodine-131, iodine 33, tritium and to radionuclidesinparticulteformwithhalflivesg%re er than 8 days in gaseous effluents shall e determined to be within the bove limits in accord-ance with the methodol y and parameters of the ODCM by btaining representa- ,

tive samples and perf.rming analyses in accordance with e sampling and anal- l ysis program specifi.d in Table 4.11.2.1.2-1. \

t

/.

, RAND GULF-UNIT 1 3/4 11-8

. vs -m /o u TABLE 4.11.2.1.2-1 s RADI0 ACTIVE GASE0US WASTE SAMPLING AND ANALYSIS PROGRAM N

GaseoushleaseType Sampling Minimum Type of Lowg[ Limit i

Frequency Analysis Activity tetection l Frequency Analysis of[LD)

Q

/(pCi/ml)a A. (1) RadwasthBuilding M M Principa}* gam 1x10'4 Ventilatign Grab Sample Emitters Exhaust \

\ H-3

[ 1x10 (2) Fuel Handling Continuous d yc I-131 1x10

-12 Area Ventila- Charcoal ,

tion Exhaust Sample -10 I ,l[3 1 10 (3) Containment Co' tinuous d yc 'rincipajGamma 1x10'11 Ventilation Particulate Emitters Exhaust Sample (I-131, Others)

(4) Turbine Building Continuo s d M / Gross Alpha 1x10

~11 Ventilation Compos *te Exhaust Parti late Sam e Continuous d

Sr-89, Sr-90 -11 Q 1x10

[hsite om Parttqulate SampleK Continu[us Noble Gas Noble Gases

-6 1x10 Monitor Gross Beta

,/ or Gamma B. (1) Offgas Post Treatment

/M M k'incipa} Gamma 1x10'4 rab Sample Em tters Exhaust, when-ever there is flow (2) Standby Gas TreatmentA Exhaust, hen-ever t e is flow.

(3) Sta by Gas Trfatment B

\

'xhaust, when-

\

ever there is \N flow.

\

Sep/" Table Notation" which follows.

/ GRAND GULF-UNIT 1 3/4 11-9

P5-41/01

TABLE 4.11.2.1.2-1 (Continued) :

RADIOACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS PROGRAM ,

TABLE NOTATION ! i

a. Tne LO is the smallest concentration of radioactive material in a ample t that ill yield a net count (above system background) that will b detected [

with 9 % probability with only 5% probability of falsely concludj g that i a blank bservation represents a "real" signal. /

i for a part ular measurement system (which may include radiog mical -

separation):

4.66 S b l

'LO

E -

V -

2.22 x 10' -

Y -

exp(-Aot)

I where ,

I LLO is the "a pr'ori" lower limit of detect on as defined above (as !

pCi per unit ss or volume). (Currait literature defines the !

LLD as the dete tion capability forffhe instrumentation only, .

and the MDC, min gum detectable colicentration, as the detection capability for a g'ven instrumen , procedure, and type of sample.)

s b

is the standard devi ion of e background counting rate or of '

the counting rate of a blank ample as appropriate (as counts per minute)

E is the counting efficiency (as counts per disintegration) ;

V is the sample size (1 units f mass or volume) ,

2.22 x 106 is the number of d' integrations per minute per microcurie ,

Y is the fractiona radiochemical yi d (when applicable) l

. A is the radi ive decay constant for the particular radionuclide at is the elgsped time between sample colle tion (or end of the !

sample c 11ection period) and time of cou ing ,

The value of s ysed in the calculation of the LLO fo a particular measurement sy em should be based on the actual observ d variance of the background co ting rate or of the counting rate of the lank samples (as ;

appropriate) rather than on an unverified theoretically p dicated -

variance. l Typical lues of E, V, Y and at should be used in the calcul tion.

l It shoy d be recognized that the LLD is defined as an a priori pefore ;

the fact) limit representing the capability of a measurement systqm and r not s a posteriori (after the fact) limit for a particular measurhment. ,

l

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4 RAND GULF-UNIT 1 3/4 11 .'0 l

P6 - 91/o t

\

TABLE 4.11.2.1.2-1 (Continued)

RADI0 ACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS PROGRAM TABLE NOTATION (Continued)

b. Ana yses shall also be performed following startup from cold s tdown, or a THE L POWER within(MALPOWERchangeexceeding15percentoftheRATEDTHER 4 one hour period. This requirement does not apply i (1) routine analysitsrequired by Table 4.4.5-1 shows that the DOSE EQU( ALENT I-131 concentration in the primary cool 3nt has not increased sop 6 than a factor of 3; and Q ) the noble gas monitor

hows that effluent s'ctivity has not increased more than a factor of 3.

c. Semples shall changed at least once per 7 cays an analyses sh'all be completed withirts 44 hours5.092593e-4 days 0.0122 hours 7.275132e-5 weeks 1.6742e-5 months after changing or after risoval from sampler.

Sampling and analy'ses shall also be performed at )6ast once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months for at least 7 days following each shutdown, startup or THERMAL POWER changeexceeding15hercentofRATEDTHERMALPgWERinonenour. When samples collected for\24 hours are analyzed, Jhe corresponding LLD's may be increased by a factor of 10. This requirement does not apply if (1) routine analysis redyired by Table 4.4.,5-1 shows that the DOSE EQUI-VALENT I-131 concentration in the primary toolant has not increased more than a factor of 3; and (2)s the noble gasjmonitor shows that effluent activity has not increased spre than a actor of 3. .

N

d. The ratio of the sample flow rate toj he sampled stress flow rate shall be known for the time period co49tec by each dose or dose rate calcula-cion made in accordance with Spec fications 3.11.2.1 and 3.11.2.3.

e. Tbs principal gamma esitters f 9e wh ch the LLD specification applies exclusively are the following padiondqlides: Kr-87, Kr-88, Xe-133, Xe-133m, Xe 135, and Xe-138 for gasecut emissions and Mn-54, Fe-59, Co-58, Co-60, In-65, Mo-99/Cs-134, Cs-1}7, Ce-141 and Ce-144 for particulate emissions. This list does not mean that only these nuclides +

are to be detected and reported. Other oe'aks which are measurable and identifiable, togetherj4ith the above nuclii$es, shall also be identified and reported. /

/

s

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l ,

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3/4 11-11 Amendment No. 25

/> RAND GULF-UNIT 1

~P$ - cil /O l

/

k4DI0ACTIVEEFFLUENTS 00 - NOBLE GASES

\

LIMITIN , CONDITION FOR OPERATION ...

3.11.2.2 Th air dose due to noble gases released in gaseous efflupnts, from

/

each Figurereactor 5.1.3-1 'ug)it, shall befrom the to limited site thetofollowing:

areas at and beyond the SITE BOUNDARY

a. During aqy calendar quarter: Less than or equal to mrad for gamma radiation \and less than or equal to 10 mrad for be radiation, and

b. - During any\ c lendar year: Less than or equal to 10 mrad for gamma radiation and less than or equal to 20 mrad fo ' beta radiation.

APPLICABILITY: At all times.

ACTION:

a. With the calculated ai dose from th. radioactive noble gases in gaseous effluents exceedipg any of t.he above limits, prepare and tion 6.9.2,aSpecialRepor(gwhichidentifiesthecause(s)forsubmittotheC exceedingthelimit(s)anddyipesthecorrectiveactionstobe taken to ensure that future r eases will be in compliance with Specification 3.11.2.2.

b. The provisions of Specifi tion 3. 3 are not applicable.

SURVEILLANCE REQUIREMENTS 4.11.2.2 DoseCalculations[/ \

Cumulative dose contribytions for noble gases for the current calendar guarter and current calendar y' ear shall be determined in accordance with the methodology and parameters in tha ODCM at least once per 31 days. /

/

NO GULF-UNIT 1 3/4 11-1? Amendment No. 69 I

76 -@ /ot 10 ACTIVE EFFLUENTS 00 - IODINE-131,10 DINE-133. TRITIUM AND RADIONUCLIDES IN PARTICULATE FORM i

LIMITIN CONDITION FOR OPERATION ,

3.11.2.3 \eyosetoaMEMBEROFTHEPUBLICfromiodine Th d -133, tritiumandragionuclidesinparticulateformwithhalf-livesgregterthan 8 days in gaseoo effluents released, from each reactor unit, frp the site to areas at and beyo d the SITE BOUNDARY (see Figure 5.1.3-1) shal be limited to the following:

a. During any alendar quarter: Less than or equal o 7.5 mrem to any organ, and

b. During any cale dar year: Less than or equa to 15 mrem to any organ.

APPLICABILITY: At all times.

ACTION:

a. With the calculated dose rom the re ease of iodine-131, iodine-133, tritium and radionuclides n partidulate form, with half-lives greater than 8 days, in gas uspffluentsexceedinganyoftheabove limits, prepare and submit th tNe Commission within 30 days, pursuant to Specification 6.9.2, a Spe 1 Report which identifies the cause(s) for exceeding the limit and f fines the corrective actions that have been taken to reduce release;s ands the proposed corrective actions to be taken to ensure that f fure relkases will be in compliance with '

Specification 3.11.2.3.

b. The provisions of Spe fication 3.0.3 re not applicable.

I SURVEILLANCE REQUIREMENTS i

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4.11.2.3 Dose Calculat ons. Cumulative dose contributio s from iodine-131, iodine-133, tritium a,nc radionuclides in particulate form w th half-lives greater than 8 days for the current calendar quarter and cu nt calendar year shall be determine in accordance with the methodology and pa ameters in the 00CM at least on per 31 days.

N '

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EkANDGULF-UNIT 1 3/4 11-13 Amendment No. 69

4 1

"P5 -91[ol-M010ACTIVEEFFLUENTS-GA OUS RA0 WASTE TREATMENT LIMITIN\CONDITIONFOROPERATION 3.11.2.4 e GASEOUS _RA0 WASTE TREATMENT (OFFGAS) SYSTEM shall be i operation APPLICABILITY. Whenever the main condenser air ejector system is in operation.

ACTION:

a. With gase us radwaste from the main condenser air jector system being disc rged without treatment for more than consecutive days, prepara and gubmit to the Commission within 30 ays, pursuant to Specification _6.9.2, a Special Report which-i ludes the following

'information:-

1. Explanation f why gaseous radwaste as being discharged without trea nt, identification o the inoperable equipment or subsystems ich resulted in g eous radwaste being discharged without treatmen , and the reaso for inoperability,

2. Action (s) taken to_ estore th inoperable equipment to OPERABLE status, and

3. Summary description of c on(s) taken to prevent a recurrence,

b. The provisions of Specifica o 3.0.3 are not applicable.

SURVEILLANCE REQUIREMENTS \

L 4.11.2.4. The instruments sp ified in the 00CM s 11_be checked every l

i 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months whenever the main ondenser air ejector s em is in operation

-SYSTEM is functioning.

i to ensure that the GASEQU RA0 WASTE TREATMENT (OFFGA l

i L

I 3/4 11-14 Amendment No. 69 GRAND GULF-UNIT 1 _

--- ., v.c- g.e~_- ,,..w-r- y n .-n ,- .c y e -.ww-

P3-9I/OI MDI0ACTIVEEFFLUENTS VE ILATION EXHAUST TREATMENT LIMITI CONDITION FOR OPERATION

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2.11.2.5 Th VENTILATION EXHAUST TREATMENT SYSTEM shall be used reduce radioactive m terials in gaseous waste prior to their discharge en the projected dose ue to gaseous effluent releases from each react r unit to areas at and bey nd the SITE BOUNDARY (see Figure 5.1.3-1) in/d 31 day period would exce 0.3 mrem to any organ. /

APPLICABILITY: Ata1timesotherthanwhentheVENTILAT!NEXHAUSTTREATME SYSTEM is undergoing utine maintenance."

ACTION:

a. Withgaseouswaste,beingdischargedwithg[ttreatmentandinexcess of the above limith prepare and submit to / the Commission within 30 days, pursuant t Specification 6.9 2, a Special Report which includes the followin information:

1. Explanation of why aseous ra aste was being discharged without treatment, i entifig4 tion of any inoperable equipment orsubsystemswhichrkult,edingaseousradwastebeing i discharged without treatment, and the reason for the

, inoperability,

2. Action (s) taken to restore he inoperable equipment to OPERABLE status, and

3. Summary descripti n of action (s taken to prevent a recurrence. .

b. The provisions of 5 ecification 3.0.3 a e not applicable.

SURVEILLANCE REQUIREMENTS _ \ \

4.11.2.5.1 Doses du to gaseous releases from each reactog unit to areas at

\

and beyond the SITE / BOUNDARY shall be projected at least once per 31 days in accordance with tb4 methodology and parameters in the 00CM. '

4.11.2.5.2 The installed VENTILATION EXHAUST TREATMENT SYSTEM all be demonstrated ERABLE by meeting Specifications 3.11.2.1 and 3.1 2.2 or 3.11.2.3.

Not dpplicable to Turbine Building ventilation exhaust unless filtration me a is installed.

[RANDGULF-UNIT 1 3/4 11-15 Amendment No. 69 \ ,

. % -kl[OI-RADI0 ACTIVE EFFLUENTS EFTL CLEhM5 EXPLOSIVE GAS MIXTURE _ - - ---

LIMITING CONDITION FOR OPERATION 3.11.2.6 -The concentration of hydrogen in the main condenser offgas treatment system-shall be limited to less than or equal-to 4% by volume.

APPLICABILITY: Whenever the main condenser ofigas treatment system-is in operation.

ACTION:

a. . With-the concentration of hydrogen in the main condenser offgas treatment system exceeding the limit, restore the concentration to within the limit within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months ,

b. The provisions of Specification 3.0.3 are not applicable.

SURVEILLANCE REQUIREMENTS 4.11.2.6 The concentration of hydrogen in the main condenser offg?s treatment system shall be determined to be within the above limits by monitoring the waste gas in the main condenser off gas treatment system with the hydrogen monitor OPERABLE as required by Table 3.3.7.12-1 cf-Specification 3,3.7.12.

GRAND GULF-UNIT 1 3/4 11- Amendment No. 69, _

, . . . , _. ,m- . ,

i

'M - 91/0)

RADI0 ACTIVE EFFLUENTS MAIN CONDENSER LIMITING CONDITION FOR OPERATION 3.11.2.7 The gross radioactivity'(gamma) rate of the noble gases measured at the offgas recombiner effluent shall be limited to less than or equal to 380 millicuries /second, after 30 minutes decay.

APPLICABILITY: OPERATIONAL CONDITIONS 1, 2,* and 3*

ACTION:

With the gross radioactivity rate of the noble gases at the offgas recombiner effluent exceeding 380 millicuries /second after 30 minutes decay, restore the gross radioactivity release rate to within its limit within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months or be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

SURVEILLANCE REQUIREMENTS 4.11.2.7.1 The radioactivity release rate of noble gases near the outlet of the main condenser air ejector shall be continuously monitored in accordance wi th 4pec4f4 cat 4en-3,3. 7.wlthEE~5MD m _s 4,11.2.7.2 The gross radioactivity release rate of the noble gases from the main condenser air ejector shall be determined to be within the limits of Specification 3.11.2.7 at the following frequencies ** by performing an isotopic analysis of a representative sample of gases taken at the offgas recombiner effluent:

a. At least once per 31 days,

b. Within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months following an increase, as indicated by the Offgas Pretreatment Monitor, of greater than 50%, after factoring cut increases due to changes in THERMAL POWER level, in the nominal steady state fission gas release from the primary coolant.

When the main condenser air ejector is in operation.

- The provisions of Specification 4.0.4 are not applicable.

GRAND GULF-UNIT 1 b

3/4 11-17 Amend m ed No. l

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vs cn/an

' RADIOACTIVE EFFLUENTS 3/\11.3 SOLIO RADIOACTIVE WASTE LIMIT \NGCONDITIDNFOROPERATION

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3,11.3 Th solid radwaste system shall be used in accordance with a ROCESS CONTROL PRO AM to process wet radioactive wastes to meet shipping nd burial ground requir ents.

APPLICABILITY: t all times.

ACTION:

a. With the pr isions of the PROCES:i CONTROL PROG)t M not satisfied, solid radioac(tt'e wastes from the site. suspend shipm nts of defectively processed

b. The provisions of Specification 3.0.3 are at applicable.

SURVEILLANCE REQUIREMENTS 4.11.3 The PROCESS CONTROL PROGRAM sha be used to verify the SOLIDIFICATION

of at least one representative test sp en from at least every tenth batch of each type of wet radioactive waste

a. If any test speciment fa s to ver SOLIDIFICATION *, the SOLIDI-FICATION*ofthebatch.g)ndertests I be suspended until such time as additional test sp imens can be o ained, alternative SOLIDIFI-CATION

parameters c be determined i_ accordance with the PROCESS CONTROL PROGRAM, an a subsequent test v ifies SOLIDIFICATION.*

SOLIDIFICATION

o the-batch may then be (resumed using the alternative SOLIDIFICATION

arameters determined by th PROCESS CONTROL PROGRAM.

b. If the initia} test specimen from a batch of the waste fails to verify SOLIDJfICATION,* the PROCESS CONTROL PRO shall provide for the co st specimens from eachconspc}Jectionandtestingofrepresentativeutive batch of the same type 3 consecgtive initial test specimens demonstrate 50b DIFICATION.*

The PRpCESS CONTROL PROGRAM shall be modified as req red, as provided in Specification 6.13, to assure SOLIDIFICATION

of su equent batc/esofwaste.

Except ewatering.

RAND GULF-UNIT 1 3/4 11-18 Amendment No. 69 , ,

1 ms a/co

)AD10 ACTIVE EFFLUENTS 3/ J1. 4 TOTAL DOSE

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LIMITING CONDITION FOR OPERATION 3.11.4 annual (calendar year) dose or dose commitment to any MEMB R OF THE PUBLIC tue to releases of radioactivity and to radiation from ur4nium fuel cycle sourceh shall be limited to less than or equal to 25 mrem tofthe total body or any o. an, except the thyroid, which shall be limited to ess than or equal to 75 mre..

APPLICABILITY: At all times.

ACTION:

a. With the calc- ted doses from the release of ff'adioactive materials in liquid or g ous effluents exceeding twice the limits of Specifi-cations 3.11.1.2 , 3.11.1. 2. b , 3.11. 2. 2. a /3.11. 2. 2. b , 3.11. 2. 3. a o r 1 i:luding direct radiation 3.11.2.3b,calcugtionsshouldbemade7fromoutsidestoragetanks contributions from e reactor units anct to determine whether f Specification 3.11.4 have been exceeded. If suc heisabove limitsp 9'repare and submit to the Commis-the case, sion within 30 days, pu uant to Spedification 6.9.2, a Special Report that defines the correct ye action f releasestopreventrecurranceof,/ex.obetakentoreducesubsequent ceeding the above limits and includesthescheduleforahbiepngconformancewiththeabovelimits.

This Specia Report, as defiried in 10 CFR Part 20.405c, shall include an analysis that esticates the~ adiation exposure (dose) to a MEMBER ycle sources, including all effluent pathways and direct radiat n, for ythe calendar year that includes OFTHEPUBLICfromuranium[fdel the release (s) covered by,/ this repo t. It shall also describe levels of radiation and concentrations f of (r ioactive material involved, and the cause of the exposurre levels or c centrations. If the estimated dose (s) exceeds the ab'ove limits, and '

the release condition result-ing in violation of 40 CFR Part 190 has at already been corrected, the Special Report hall include a reques xfor a variance in accordance with the provisia s of 40 CFR Part 190. Submittal of the report is considered a tirrelf request, and a variance h granted until staff action on the equest is complete.

b. The provisions of Specification 3.0.3 are not app icable.

SURVEILLANCE REQUIREMENTS

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4.11.4.1 Cur ative dose contributions from liquid and gaseous ef luents shall bedeterminep'inaccordancewithSpecifications 4.11.1.2,4.11.2.2,{gand 4.11.2.3, and in accordar.ce with the methodology and parameters in tha ODCM.

4.11.4.2/ Cumulative dose contributions from directreactor radiation frota the units arid from radwaste storage tanks shall be determined in accordance with tht mef.hodology and parameters in the ODCM. This requirement is applicabid oni under conditions set forth in Specification 3.11.4.a.

/ \

GRAND GULF-UNIT 1 3/4 11-19 Amendment No. 69 \

. m cu/ci k4.12 RADIOLOGICAL ENVIRONMENTAL MONITORING 3/A,12.1 MONITORING PROGRAM LIM!hNGCONDITIONFOROPERATION 3.12.1 Theradiologicalenvironmentalmonitoringprogramshallbeconodcted asspeci(edinTable3.12.1-1.

APPLICABILITY: At all times.

ACTION:

a. With he radiological environmental monitoring prograp not being conduc td as specified in Table 3.12.1-1, prepare arid submit to the Commissib , in the Annual Radiological Environment 41 Operating Report pe Specification 6.9.1.7,adescriptiono[thereasonsfor not condue ng the program as required and the plans for preventing a recurrence.

j/

b. With the level f radioactivity as the result /of plant effluent in anenvironmenta\samplingmediumataspecifiedlocationexceeding the reporting levels of Table 3.12.1-2 when averaged over any calendar quarter, prepare and submit to the Commiyfion within 30 days pursuant to Specification 6.9 A2 a Special Report /that identifies the cause(s) for exceeding the limi s) and defines /the corrective actions to be taken to reduce radios ive effluenty'so that the potential annual dose to a MEMBER OF THE UBLIC is Ipss than the calendar year limits of Specifications 3.11.1.h 3.11.2/2 and 3.11.2.3. When more than one of the radionuclides i abit /3.12.1-2 are detected in the sampling medium, this report h/1 be submitted if:

concentration (1) tration (2) reporting level (1) , conceport 'ng level (2) + * * '> 1.0 When radionuclides other han those n Table 3.12,1-2 are detected and are the result of p) ant effluents this report shall be submitted if the potential annual dose to a HEMB 0F THE PUBLIC is equal to or greater than the caleddar year limits o Specifications 3.11.1.2,

'3.11.2.2 and 3.11.2 3. This report is no required if the measured level of radioacti ity was not the result plant effluents; however, in such an event theconditionshallberep(ortedanddescribedin the Annual RadifogicalEnvironmentalOperati

c. If milk or broad leaf vegetation sampling rol cated fromis one

% or Report, more of the tample locations required by Table 3. 2.1-1, identify new locatipds for obtaining replacement samples an add them to the radiological environmental monitoring program withi g30 days. In addition /reportthecause(s)oftheunavailabilityo samples and the new' locations for obtaining replacement samples-in he next Semi-annua ' Radioactive Effluent Release Report. Include in his report i

the vised 00CM figure (s) and table (s) reflecting the ne'w locations.

Thy specific locations from which samples were unavailablekay then bar deleted from the radiological environmental monitoring program and

' the table (s) in the ODCM, provided the locations from which the replace-

/

/mentsampleswereobtainedareaddedtothetable(s)asreplacem locations.

d. The provisions of Specification 3.0.3 are not applicable.

s 3 RAND GULF-UNIT 1 3/4 12_-_1 Amendment No. 69 i

l I

L

76 -91/01 MDIOLOGICAL2NVIRONMENTALMONITORING SU LLANCE REQUIREMENTS X /

4,12.1 1 radiological environmental monitoring samples shall be col ected i pursuant to Table 3,12,1-1 from the locations given in the table and igures in the ODCM and hall be analyzed pursuant to the requirements of Tabl s 3.12,1-1 and 4,12,1-1, RAND GULF-UNIT 1 3/4 12-2

'b 's s. TABLE 3.12.1-1 a

1 OPERATIONAL RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM 33

-- E a

))' [z Exposure' Pathway Number of Samples Sampling and Type and F quency.

c and/or Sa le and Locations Collection Frequency a of lysis m ,

z E AIRBORNE El Radiciodine and amples from 5 locations: Continuous sampler Radioiodine Cannister:

wa Particulates operation with sampi Analyze weekly for 3 sa. les close to the SITE BOUNDARY collection weekly- r I-131 (in di f rent sectors) having the as required by st highest (cal qulated annual average loading, wh' ever is groundlevel 07 . more fre ent 1 sample from the 'cinity of a Particr: late Sampler:

community having the ighest Gross beta radio-calculated annual avera ground- activity following I'#*I 0#0' filter change,b composite kf (by location) for gamma

(( 1 sample from a control loca 'on C isotopic quarterly-

"f d w di 15-30 km (10-20 miles) / nance DIRECT RADIATION

40 stations with t or more dosime- Qbaberly Gamma dose quarterly tees or one ins ument for measuring and recordin ose rate continuously to be pla in each accessible

sector follows:

1) an inner ring of stations in the general areas of the SITE BOUNDARY

2) an outer ring approximately 3 to 5 miles from the site.

The balance of the stations should be placed in special interest areas such as population centers, nearby residences, schools,.and in 1 or 2 areas to serve as control stations.

/

~

, , . . . . , . - . . . - ~ . ~ . - . . . . + - - + - + - - - - - - - - - - - ~ ~ > '*' " - " " ' * ' * ' - ~ " " * ' ' ~ * ~ " " ~ " ~ ' ' ' " ~ ~ -

TABLE 3.12.1-1 (Continued) l^- a OPERATIONAL RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM a Sampling and Type and F quency a Exposure)3 ay . Number of Samples 3 of, and Locations Collection Frequency lysis s

and/or Samp WATERBORNE N

~ Surface f

1 mple upstream Monthly Gammaigotopicanalysis 1 samp downstream monthly . Composite for tritium analyses quarterly Discharge Basin ComposJt sample over one- nth period Samples from 2 sources Quarterly Gamma isotopic' and Ground tritium analysis quarterly R

Monthly I-131, Gross p and Z Cistern Water 1 sample of the nearest sou e gamma isotopic analyses c

1 that could be affected monthly. Composite for 1 sample from a control location tritium analysis quarterly I sample fom downstream area Semiannually Gamma isotopic analyses Sediment from semiannually Shoreline ,

INGESTION t

Samples from milking animals in 3 Semimonthly when Gamma isotopic and I-131 ,

Milk anal is semimonthly when

/

/ locations within 5 km distant having the highest dose potential. If animals are on pas-ture, monthly at anima 'are on pasture; there are none then, I sample from other times monthly at other times.

,/,

milking animals in each of 3 areas between 5 to 8 km distant where doses are calculated to be greater h

than 1 mrem per year y

/

4

,. ., .- -- m.-. . . . - . ,, n. -v. -..,,.we. ,..m -,-.g -.e.

& ---.. . .,-, v. m. , ~.--w.- ..w- .---....----.-w<. - - , - - .

I o

TABLE 3.12.1-1 (Continued) g \

OPERATIONAL RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM E N Exposure Pathwa a Number of Samples Sampling and

(

l-and/or Sample and Locations Collection Frequency' Typ nd Frequency Analysis

i Milk (cont'd) N'$

l ample from milking animals at

~

" a control l l distant) \ocation N

(15-30 km Fish and 1 sample of one species of commer- Semi ually Gamma isotopic c Invertebrates cially or recreatioiihLly important analysis on edible fish in vicinity of discharge portions point 1 sample of same species in, areas not influenced by plant discharge Food Products Samples of 3 dif inds of Monthly when available Gamma isotopic C

~ broad leaf vege ion grown nearest and I-131 analysis 7

each of twVdif ferent of fsite loca-tions with highest anticipated annual averageground-levelD/Qifmilk dmpling is not performed

/ 1 sample of each of the similar Monthly when available Gamma isotopic' vegetation grown 15-30 km distant and ID 31 analysis if milk sampling is not performed N x ~

x tj u

i D

e IABtt 3.12.1-1 (Continued) o OPERATIONAL RADIOLOGICAL ENVIRONMENTAL HDAlI0 RING PROGRAM M z

TABLE N01AT10N (f6 I

o "As described in the ODCH.

o S

% secific parameters of distance and direction sector from the centerline of one reactor, and add 1 onal descrip-y te where pertinent, shall be provided for each and every sample location in Table 3.12.1-1 ' the table (s) and {O c- figur ) in the ODCH. Refer to NtlREG-0133, " Preparation of Radiological Effluent Technic- Specifications for -

3 Nuclear r Plants," October 1978, and to Radiological Assessment Branch Technical Po ion, Revision 1 November H 1979. Dev Qons are permitted from the required sampling schedule if specimens are nobtainable due to hazardous w conditions, seh onal unavailability, malfunction of automatic sampling equipment other legitimate reasons. If specimens are unobt.ainable due to sampling equipment malfunction, every effort iall be made to complete corrective action prior to the M of the next sampling period. All above deviations om the sampling schedule shall be documented in the Annua Ntadiological Environmental Operating Report pur ant to Technical Specification 6.9.1.6.

It is recognized that, at ti , it may not be possible or practica) e to continue to obtain samples of the media of choice at the most desired I tion or time. In these instanc#s suitable alternative media and locations may be chosen for the particular pathwa in question and appropri e substitutions made within 30 days in the radio-logical environmental Jonitoring progr Identify the c ,e of the unavailability of samples for that pathway and identify the new location (s) for obtaininty replacement sples in the next Semiannual Radioactive Effluent Release Report and also include in the report a revi fig (s) and table (s) for the ODCM reflecting the new locatien(s).

b pss beta 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or more after sampling to allow for radon F Particulate sample filters r

A and thoron daughter decay.should If grossbebeta analyzed)ivity act inYr or water is greater than ten times the yearly mean of control samples for any medium, gamma i (opic analysis uld be performed on the individual samples.

E C Gamma isotopic analysis meansjthe r entification and quantific t'on of gamma emitting radionuclides that may be attributable to the effluents rom the facility.

The purpose of this samp is to obtain background information.

'One or more instruments, such as a pressurized ion chamber, for measuring and cording dose rate continuously may beusedinplac/of,orinadditionto,integratingdosimeters. For the purposes f this table, a thermoluminescent dosimeter may be considered to be one phosphor and two or more phosphors in a packet y be considered as two or more dosi gters. Film badges should not be used for measuring direct radiation.

Ih upstream sample" should be taken at a distance beyond significant influence of tt.e disch. 'e. lhe

" ownstream" sample should be taken in an area beyond but near the mixing zone.

9 Composite santples should be collected with equipment (or equivalent) which is capable of collecting an iguet at time intervals which are very short (e.g., hourly) relative to the compositing period (e.g., monthly).

b lhe dose shall be calculated using methodology contained in the ODCH.

TABLE 3.12.1-2 d.

S -

t} '

REPORTING LEVELS FOR RADI0 ACTIVITY CONCENTRATIONS IN ENVIRONMENTAL SAMPLES '

$ N D E Reporting Levels n h b )htgr Airborne Particulate Fish yd Analysis Food Products (pCi/l( or Gases (pCi/m3 ) (pCi/Kg, wet) / pCi/l) (pCi/Kg, wet)

H-3 2 x 10 4 NA NA NA NA Mo-54 1 x 10 NA x 10 NA NA Fe-59 2 4 x 10 NA 1 x 10 4 flA NA Co-58 3 1 x 10 NA 3 x 10 4 f1A NA Co-60 2

{ 3 x 10 NA 1 x 10 4

f4A NA y Zn-65 3 x 10 2 NA 2 10 4

f4A NA Zr-Nb-95 2 4 x 10 NA NA fiA NA I-131 2 0.9 NA 3 1 x 10 2 Cs-134 30 10 , 1 x 10 3 60 1 x 10 Cs-137 50 20 3 2 x 10 70 2 x 10 2

Ba-La ,140 2 x 10 NA NA 3 x 10 2 for drinking water samples. This is a 40 CFR Part 141 value.

value of 30,000 pCi/1 may be used. r.o drinking water pathway exists, a

/,

4

\ TABLE 4.12.1-1 MAXIMUM VALUES FOR THE LOWER LIMITS OF DETECTION (LLD)a,b y

5 _D Airborne Particulate' Broad Leaf T Water or Gas Fish Milk Vegeta ~ n Sediment -

E Analysis (pCi/l (pCi/m3 ) (pCi/kg, wet) (pCi/1) (pCip , wet) (pCi/kg, dry)

Gross beta 4 1 x 10 -2 NA NA NA NA d NA H-3 2000 NA NA N NA Mn-54 15 NA 130 NA NA NA Fe-59 30 NA 260 NA NA NA Co-58,60 15 NA 0 NA NA 'NA

$ Zn-65 30 NA 260 NA NA NA h

m Zr-95 30 NA NA 4A NA NA Nb-95 15 NA NA NA NA I-131 1 c 7 x 10 -2 NA 1 60 NA Cs-134 15 5 x 10 -2 130 15 150 Cs-137 8 6 x 10 -2 150 18 80 180 Ba-140 60 NA NA 60 NA NA 14 0 15 NA t4A 15 NA N N

J

P5 - 91/01 TABLE 4.12.1-1 (Continued)

MAXIMUM VALUES FOR THE LOWER LIMITS OF DETECTION (LLD)

TABLE NOTATION "Acceptabl detection capabilities for thermoluminescent dosimeters sed for environmental measurements are given in Regulatory Guide 4.13.

b Table 4.12-1 odicates acceptable detection capabilities for adioactive materialsinenKronmentalsamples. These detection capabil ties are tabulated in terms of the ibyer limits of detection (LLDs). The LLD s defined, for purposesofthisg4de,asthesmallestconcentrationof adioactive material in a sample that wilk yield a net count (above system b4 kground) that will be detected with 95% pr,obability with only 5% probabil'ty of falsely concluding that a blank observatio epresents a "real" signal.

For a particular measurement system (which may inc)ude radiochemical separation): j' LLD = 4.66sh /

E -

V 2.22 -

Y - exp(-Aat) where

/

LLD is the "a priori" lower limit of detection as defined above (as pCi per unit mass or volume).

the detection capability for(C'ur ent literature the instrumentation defines only, and thethe MDC,LLD as minimum detectable concent' ration, ys the datection capability for a given instrument, procedore, and ty of sample.)

s b is the standard deviat on of the backg und cot.nting rate or of the counting rate of a ank sample as appr priate (as counts per minute)

E is the counting efficiency f

(as counts per isintegration)

V is the sample s'ize (in units of mass or volume 2.22 icocurie is the numbpr of disintegrations per minute per p\

Y is the fpe/ctionalradiochemicalyield(whenapplica(le)

A is the/ radioactive decay constant for the particular \eqdionuclide at is e elasped time between sample collection (or end o ' he sample cpilectionperiod)andtimeofcounting The value'of s used in the calculation of the LLD for a particular measurementsyItemshouldbebasedontheactualobservedvarianceofte backgybundcountingrateorofthecountingrateoftheblanksamples($

apppApriate) rather than on an unverified theoretically predicated variance.

/ 'N GkANDGULF-UNIT 1 3/ 12-9 \

-- =

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

76 -91/Ol TABLE 4.12.1-1 (Continued)

MAXIMUM VALUES FOR THE LOWER LIMITS OF DETECTION (LLO)

TABLE NOTATION (Continued)

Typical va ues of E, V, Y and at should be used in the calculation.

It should be ecognized that the'LLD is defined as an a priori (b fore the nd not as a fact) limit re resenting the capability of a measurement system OccasionalTy posteriori (aft r the fact) limit for a particular measurementesence of inter-background fluct tions, unavoidable small sample size, the nder these LLDs fering nuclides, o other uncontrollable circumstances may unachievable. In 5 ch cases, the contributing factors sho ld be identified and described in th nnual Radiological Environmental 0 rating Report pursuant to Specifica on 6.9,1.6.

" LLD for drinking water s ples. If no drinking wate pathway exists, the LLD of gamma isotopic may be u ed.

If no drinking water pathway .ists, a value of 000 pCi/l may be used.

f I

4 RAND GULF-UNIT 1 3/4 12-10

]% -91/o f

\A0!0LOGICALENVIRONMENTALMONITORING 3/ 12.2 LAND USE CENSUS LIMIT NG CONDITION FOR OPERATION /

3 ' 12.2 A land use census shall be conducted and shall identify wit a

aistance o s8 km (5 miles) the location in each of the 16 meteorol ical sectors of f e nearest milk animal, the nearest residence and the earest garoen of gre ter than 50 m2 (500 f t2) producing broad leaf vegetation. Broad leaf vegetatio sampling of at least three different kinds of v4getation may be performed athhe SITE BOUNDARY in each of two different direction sectors with the highest 'p(edicted 0/Qs in lieu of the garden census / Specifications for broad leaf vegegation sampling in Table 3.12.1-1 shall e followed, including analysis of ontrol samples.

APPLICABILITY: At all es.

ACTION:

a. Withalandusecenpusidentifyingalop$ tion (s)whichyieldsa calculated dose or dose commitment greater than the values currently being calculated in S'pecification 4.11.2.3, identify the new location (s) in the nex Semiannual Kadioactive Effluent Release L

Report,pursuanttoSp(c\fication e . 9.1. 9.

b.

With a land calculated dose use census or dose ide'ng{ify)ng comm tment (via the sameaexposure location (s) which yields pathway)

. 20 percent greater than at a locatfan from which samples are currently being obtained in ckrdancewithSpecification3.12.1, add the new location (s) to the adiological environmental monitoring programwithin30 days,jfhesamphnglocation(s),excludingthe control station locatiop, having the lowest calculated dose or dose commitment (s),viaths)/sameexposurebathway,maybedeletedfrom this monitoring pro am after October \31 of the year in which this land use census was onducted. Identify the new location (s) in thenextSemiannualRadioactiveEffluenty)eleaseReportandalso include in the rpport a revised figure (s and table (s) for the OOCH reflecting the ew location (s).

c. The provisions of Specification 3.0.3 are not a plicable.

SURVEILLANCE REQUIREMENTS

/

l 4.12.2 Thelan!usecensusshallbeconductedduringthegrow g season at least once per/12 months using that information that will provide \the best results, sucp as by a door-to-door survey, aerial survey, or by consulting local agriculture authorities. The results of the land use census sqall be included-jn the Annual Radiological Environmental Operating Report punsuant to Specification 6.9.1.7.

/

\\

\

GRAND GULF-UNIT 1 3/4 12-11 Amendment No. 69

. w en/o, NADf 0 LOGICAL ENVIRONMENTAL MON 10 RING 1 3 , 12,3 INTERLABORATORY COMPAR! SON ekOGRAM lLIMITI 00N0!T!0N F00 OPERATION 4

3.12.3 Analyses shall be performed on radioactive materials that orrespond to sampler required by Table 3.12.1-1. These materials are sup ied as part of an Interlab' oratory Comparison Program which has been approve by the Commission.

APPLICABILITY: At All times.

A0! TON: .

a. With analyses ,ot being performed as required above, report the corrective actions taken to prevent a recurrence to the Commission in the Annual Rr ,-Niogical Environmental 4perating Report pursuant to Specificat' /* C s.l.7.

/

b. The provisions a Specification 3.0.} re not applicable.

\

SURVEILLANCJ REQUIREMENTS \ ,

3 4.12.3 A summarv of the results obtal d as part of the above required Interlaboratory ' Comparison Program s ll'he included in the Annual Radiological Environmental Operating Report purs ant to Specification 6.9.1.7.

\

/ \

/

j' .

\

GRAND GULF-UNIT 1 3/4 12-12 Amendment No. 69 '\

4 y w a, a , a,v - ,-no--,n ,y-,e,a w s --. m_ --,-,,mv ..scw-rw,vme----, , - , , , - . -

e T'S A/ot INS?aVMENTATION BASES 3/4.3.7.10 LOOSE-PART DETECTION SYSTEM 4 The OPEkA8!LITY of the loose part detection system ensures that sufficient capability is available to detect loose teetallic parts in the primary system and avoid or mitigate damage to primary system components. The systes consists of 16 sensors, of which only 8 are selected and need to be OPERABLE at a time, to preside the inputs to the 8 monitoring channels. The remaining 8 sensors may be used as replacement sensor inputs for failed sensors or to provide a change in location of the area being monitored. The allowable out of service times and surveillance requirements are consistent with the recommendationr of Regulatory Guide 1.133, " Loose Part Detection Program for the Primary System of Light Water-Cooled Reactors," May_1981. ,

'3/4,3.7.11 RADI0 ACTIVE LIQUIU EFFLUENT MONITORING INSTRUMENTATION The radioactive liquid effluent monitoring instrumentation is prov monitors and4'ontrol, as applicable, the releases of radioactivelsmaterfa,id(d in to liquid effluehts,during actual or potential releases of liquid eff1'uents. The alars/ trip setpoints for these instruments shall be calculated'ln accordance with the procedures 'insthe 00CM to ensure that the alarm / trip will occur prior to exceeding the limits of 10s CFR Part 20. The OPERASILITY and use of this instrumentation is consistehtqith the requirements-6f General Design Criteria 60, 63 and 64 of Appendix A to 10 CFR 50. ,/

1/4.3.7.12 RADIDACTIVE CASE 0VS EFFLUENT MONITORING INSTRLMENTATION IQl monitorThe radioactive A/ tial releases.

and control, gaseous effluentionltatin as applicable, instrumentation is provided to gaseous off pents during actual or poten-Those instruments that monitor th'e 9ctivity of gaseous efflu-alam ents being released to the-snvironment shall have their\o ensu/ trip the re that setpoints alarm /

calculated in accordance'with ths methods in the 00CM t trip will occur pr,for to exceeding the limits of 10 CFR Part'20 Other instru-ments that monitor offgas processing, (i.e., the Explosive Gas Monitor, Offgas Pre Treatme.nt' Monitor, and Offgas Post Treatment Monitor) are calibtsted accordc ing to pli7it prececures. The OPERA 8ILITY and use of this instrumentation is con 31 stent with the requirements of General Design Criteria 60, 63 and 64'of Appendix A to 10 CFR Part 50.

l 3/4.3.8 PLAN 1SYQEMSACTUATIONINSTillMNTATION i The plant syst(e3 actuation instrumentation is provided to initiate action

! to sitigate the consequences of accidents that are beyond the ability of the operator to control. The LPCI mode of the kHR system is automatically initiated on a high drywell pressure signal and/or a low reactor water level, level 1, signal. The containment spray system wt.. then actuate automatically following high drywell and high containment pressure signals. Negative barometric pres-sure fluctuations are accounted for in the trip setpoints and allowable values specified for drywell and containment pressure high. A 10-minute minimum, t

13-minute maximum time delay exir.ts bc' ween initiation of LPCI and containment i

spray actuation. A high reactor water level, level 8, signal will actuate the feedwater systen/ main turbine trip system. The suppression pool makeup system is automatically initiated on a low low suppression pool water level signal with l

a concurrent LOCA signal or following a specified time delay after receipt of a i LOCA signal. The low low suppression pool water level Trip Setpoint and l Allowable Value are relative to the surface floor of the suppression pool *

(93'0%" above mean sea level).

GRAND GULF UNIT 1 B 3/4 3-6 Amendment so. 60, ._

j l

PS-91/01 Irisert, to Page _D 3/4_316 Insart A:

3L4al.7.12 fjAJN_CONDlf.NSJiR OFFGAS TREATH.ENT SYSTf31, _. Xi'LOSIVE GAS HONIf0RJ NG, SYSTIUi_ I NSTR_UMENTATIO.N Thn explonive gan monitoritig nyntem f ristrumentntion of th s mnin cotulenner of fgas trentment system in provided to monitor t in concentrations of potentially explonive gna mixturen in tia main condennor offgan treatmelit. system. Tliin itintrumentation in calibrated in accordance Wit.h plant procedures.

l.

i l'

M9104241/SNLICFI.R - 9 n

Ts -m/ci 3/4.11 RADIDACTIVE EFFLUENTS BASES 3/4.11.1 L10U10 EFFLUENTS M4.11.1.1 CONCENTRATION his specification is provided to ensure that the concentration of radio- :

active '

be less aterials an the released concentration in liquidlevelswaste specified of fluents in 10 CFR to UNRESTRICTED Part 20, Appendijt AREAS wl Table !!, olumn 2. This limitation provides additional assurance thatJfie .

levelsofrkioactivematerialsinbodiesofwaterinUNRESTRICTEDAREp5will resultinexp0(ureswithin(1)theSectionll.Adesignobjectivesof ppendix 1, '

10 CFR $0, to a EMBER OF THE PUBLIC, and (2) the limits of 10 CFR .106(e) to the population. The concentration limit for dissolved or entr ined noble gases is based upon the assumption that Xe*135 is tne controlli radioisotope '

and its MPC in' air (submersion) was converted to an equivalen concentration in water using the methqds described in International Commi ion on Radiological Protection (!CRF) Publichtion 2.

The required detection pabilities for radioactlyt> materals in liquid !

waste samples are tabulated i terms of the lower lirpits of detection (LLDs). :

Detailed discussion of the LLD, nd other dntectiory' limits, can be found in:

(1) HASL Procedures Manual, \ HASL-300 sed (rev /

annually).

t (2) Currie, L. A. , " Limits for Q\ality ive Detection and Quantitative f Determination-Applicationtolddiochemistry," Anal. Chem.40, 586-93 (1968).

(3) Hartwell, J. K., "Detectio Limits a Radioisotopic Counting Techniques," [

Atlantic Richfield Hanfo- Company Re(purt ARH-2537 (June 22, 1972).

3/4.11.1.2 DOSE This specification is !

Ill. A and IV. A of Appendf'provided i 1, 10 CFR Part 50. toTheLimitkgConditionfor implement the requirements of S Operation implements thp guides set forth in Section II.A d' Appendix 1. The '

ACTION statements provide the required operating flexibility nd at the same time implement the I which assure ,

thatthereleases/gd' ides'setforthinSectionIV.AofAppendi f radioactive material in liquid effluents to UNRESTRICTED :

AREAS will be kept "as low as is reasonably achievable." Also, f fresh water sites with drijiiling water supplies which can be potentially af fecte sby plant l operations, jfiere is reasonable assurance that the operation of the f ility I w'll not r fuit in radionuclide concentrations in the finished drinking water that are n excess of the requirements of 40 CFR 141. The dose calculat. ns in thef CM implement the requirements in Section !!!. A of Appendix I that\ .

conforfnance with the guides of Appendix ! be shown by calculational procedurb bas on models and data, such that the actual exposure of a MEMBER OF THE P LIC through appropriate pathways is unlikely to be substantially

,inderestimated. The e.guations specified in the 00CM for calculating the doses GRAND GULF-UNIT 1 B 3/4 11-1 Ame* A mewt- wcx _ I L

'T'S - 9 t/01 .

-RA010AC-HVE-EffteEN&

-ilASE+

3/4.11.1.2 DOSE (Continued) i due the actual release rates of radioactive materials in liquid efflue ts are conshtent with the methodology provided in Regulatory Guide 1.109 al- :

culation of' Annual Doses to Man from Routine Releases of Reactor Eff" d nts for l the Purpose ofivaluating Compliance with 10 CFR Part 50, Appendi ,

Revision 1, October 1977 and Regulatory Guide 1.113, "Estimati3g quatic Dis- -

persion of Effluent 4 rom Accidental and Routine Reactor Rele ses for the Purpose i of Implementing Appendix I," April 1977. !

N !

This specification apM{es to the release of liquid ef fluents from each reactor at the site. For units with shared radwayitf treatment systems, the liquideffluentsfromtheshared stem are pro rtioned among the units sharing that system. ;

~

3/4.11.1.3 LIOulD WASTE TREATMENT

?

The requirement that the appro iate port j specifiedprovidesassurancethpt'thereleases(onsofthissystembeusedw ofyradioactive materials in '

liquid ef fluents will be kepV as low as is reasonetly t achievable." This speci- i fication implements the re girements of 10 CFR Part S0 36a, y General Design Criterion 60 of AppendivA to 10 CFR Part 50 and the des 4gn objective given in ,

Section II.D of Apperjdfx I to 10 CFR Part 50. The specif fe(limit governing the !

use of appropriate fortions f of the liquid radwaste treatmentNystem were speci-dfractionofthedosedesignobjectivessetfothin l fled as aII.A Section suita) f Appendix I, 10 CFR Part 50, for liquid effluents. .

i Thi specification applies to the release of liquid ef fluents f roiittach i reacto( at the site. For units with shared radwaste treatment systems, th-liguTd effluents from the shared system are proportioned among the units pharing the system. l 3 . H

-The tanks listed in this specification include all those tanks containing radioactive material that are not surrounded by liners, dikes, or walls capable of holding the contents and that do not have overflows and surrounding area drains connected to the liquid radwaste treatment system. Restricting the I !

quantity of radioactive material contained in the specified tanks provides ,

assurance that in the event of an uncontrolled release of the tanks' contents, the resulting concentrations would be less than the limits of 10 CFR Part 20, Appendix B, Table II, Column 2, at the nearest potable water supply and the !

nearest surface water supply in an UNRESTRICTED AREA. i M cN e_ i n ,

6.

't3 3/4 11 - 1 i

l l -SRAN019tMNIH -04/4-1-1+ AmcadmeSt A l

t

~P6 cil/01 RADIDACTIVE EFFLUENTS BASES 3/4.11.2 GASE0US EFFLUENTS h/4.11.2.1 DOSE RATE beyon Thisspecificationisprovidedtoensurethatthedoseanytimeatanp the SITE BOUNDARY from gaseous effluents from all units on the site will be with n the annual dose limits of 10 CFR Part 20 for UNRESTRICTED ARE 6. The annual d (e limits are the doses associated with the concentrations o 0 CFR Part 20, Ahpendix B Table 11, Column 1. These limits provide reasop ble assur-ance that ra,' ioactive material discharged in gaseous ef fluents wi1Vnot result in the exposu of a MEMBER OF THE PUBLIC in an UNRESTRICTED ARE/Voutside the SITE BOUNDARY t annual average concentrations exceeding the I ts specified in Appendix B, Table II of 10 CFR Part 20 (10 CfR Part 20.106(b for MEMBERS Of THE PUBLIC who may' times be within the SITE BOUNDARY, th occupancy of the MEMBER OF THE PUBLIC ill be sufficiently low to compensaty for any increase in theatmosphericdiffuinfactorabovethatfortheSITE/0VNDARY. The speci-fied release rate limit estrict, at all times, the c responding gamma and beta dose rates above bac ground to a MEMBER Of THE P LIC at or beyond the SITE BOUNDARY tc less than b( equal to ")0 mrem /ye to the total body or to less than or equal to 3000 mrep/ year ti he skin, hese release rate limits also restrict, at all times, th > corres, inding roid dose rate above back-ground to a child via the inhala on pathway t less than or equal to 1500 mrem / year.

This specification applies to th gre ase of gaseous effluents from all reactors at the site. Foramorecomplh)ediscussionoftheLLD,andother detection limits, see the following:

-(1) HASL Procedures Manual, ((Ati-300 ( . vised annually).

(2) Currie, L. A., " Limit for Qualitativt Detection and Quantitative Determination - Appi cation to Radioche istry," Anal. Chem. 40, 586-93 (1968).

(3) Hartwell,J.K.,"DetectionLimitsforRadio]otopicCounting Techniques," A lantic Richfield Hanford Company Report ARH-2537 (June 22, 1972).

3/4.11.2.2 DOSE -_#0BLE GASES This spec} cation is provided to implement the requirements of_

Sections 11.B The imiting Conditionfpr/Ill.AandIV.AofAppendixI,10CFRPart50.

Operation implements the guides set forth in Section .B of Appendix /. The ACT10N statements provide the required operating fle ibility and at e same time implement the guides set forth in Section IV.A of pendix !

to ass e that the releases of radioactive material in gaseous effluents o UNRE MRICTED AREAS will be kept "as low as is reasonably achievable." The Sur eillance' Requirements implement the requirements in Section Ill.A of A endix 1 that conformance with the guides of Appendix I be shown by calcu-ational procedures based on models and data such that the actual exposure of GRAND GULF-UNIT 1 B 3/4 11 Amend med Mo. -

, 75 - 9 l/ol O!0 ACTIVE EFFLUENTS BAS 3 3_/4.1 .2 DOSE - NOBLE GASES (Continued) a MEMBER - TliE PUBLIC through appropriate pathways is unlikely to b substantial y underestimated. The dose calculations established in the ODCM for calculat ig the doses due to the actual release rates of radi .ctive noble gases in gase{dys effluents are consistent with the methodology vided in Regulatory Guid( 1.109, " Calculation of Annual Doses to Man fr Routine Releases of Reactgr Effluents for the Purpose of Evaluating C'.pliance with 10 Cf R Part 50, Appendix 1," Revision 1, October 1977 and Re latory Guide 1.111, "Metho s for Estimating Atmospheric Transport nd Olspersion of Gaseous Effluents in Coutine Releases from Light-Water Co9 ed Reactors," Revi-sion 1, July 1977. Th\ ODCM equations provided for dete inining the air doses at and beyond the SITE UNDARY are based upot, the hist rical average atmos-pheric conditions.

Thisspecificationapp\estothereleaseof seous offluents from each reactor at the site. For un s with shared radwa e treatment systems, the gaseous effluents from the sha).d system are pro ortioned among the units sharing that system.

3/4.11.2.3 DOSE - 10 DINE-131, IOD NE-133, T,IllUM AND RADIONUCLIOES IN PARTICULATE FORM This specification is provided to plement the requirements of Sections 11.C,III.AandIV.AofAppenp4I,10CfRPart50. The Limiting Conditions for Operation are the guid s set forth in Section II.C of Appendix 1.

The ACTION statements provide the re utred perating flexibility and at the same time implement the guides set orth in 'ection IV.A of Appendix ! to assure that the releases of radio ctive mater 15 in gaseous offluents to UNRESTRICIED AREAS will be kept as-low as is asonably achievable." The ODCM calculational methods spe fied in the Surv illance Requirements imple-ment the requirements in Sect on Ill.A. of Append- I that conformance with the guides of Appendix 1 be shown by calculational rocedures based on models and data, such that the ac al exposure of a MEMBER THE PUBLIC through appropriate pathways is t likely to be substantially derestimated. The ODCM calculational methods f calculating the doses due to he actual release rates of the subject materia s are consistent with the methodo gy provided in Regu-latory Guide 1.109, " alculation of. Annual Doses to Man fr m Routine Releases of Reactor Effluent for the Purpose of Evaluating Complian with 10 CFR Part 50, Appendix ," Revision 1, October 1977 and Regulator Guide 1.111,

" Methods for Est ating Atmospheric Transport and Dispersion o Gaseous Effluents in Ro ine Releases from Light-Water-Cooled Reactors, Revision 1, July 1977. T se equations also provide for determining the act al doses based upon tt historical average atmospheric conditions. The relhase rate specificati ns for iodine-131, iodine-133, tritium and radionuclide in particula form are dependent on the existing radionuclide pathway t man in the a}>as at and beyond the SITE BOUNDACY. The pathways which were examinef in the development of these calculations were: (1) individual 'nha-latio of airborne radionuclides, (2) deposition of radionuclides onto gr>en leaf vegetation with subsequent consumption by man, (3) deposition onto g ssy RAND GULF-UNIT 1 B 3/4 11-4

i

. T)S-99/OI !

l E(A010ACTIVEEFFLUENTS /

BAS N

3/4.11.2.3 DOSE - 10 DINE-131, 100lNE-133, TRITIUM AND RAD 10NUCLlD IN !

PARTICULATE FORM (Continued) /

areas where milk als and meat producing animals graze,v6 consumption of the milk and meat by min and (4) deposition on the ground with subsequent exposure of man.

This specification applie to the release pf gaseous effluents from each ,

reactor at the site. For units w Q shared pdwaste treatment systems, the gaseous effluents from the shared sy(tem aye proportioned among the units sharing that system. ,

i 3/4.11.2.4 and 3/4.11.2.6 GASCOUS JA'0 WAST REATMENT AND VENTILATION EXHAUST TREATMENT The OPERABILITY of the ASE0VSRADWASTETREATfqi(OFFGAS)SYSTEMandthe VENTILATION EXHAUST TREAT T SYSTEM ensures that theNystem will be avaliable for use whenever gascoy effluents require treatment prlet s to release to the environment. The re used,whenspecifJet,quirementthattheappropriateportionNofthesystembe '

, provides reasonable assurance that the releases of radioactive materials in gaseous effluents will be kent "as lown s is reason-ably achievab fe." This specification implements the requirementsN 10 CFR

+

Part 50.3 ( General Design Criterion 60 of Appendix A to 10 CFR Pa 0, and the des objectives given in Section 11.0 cf Appendix ! to 10 CFR P 50. ,

The s fled limits governing the use of appropriate portions of the systqm wece'specified as a suitable fraction of the dose design objectives set fortf(

jff Sections 11.8 and II.C of_ Appendix 1,10 CFR Part 50. for caseous ef fluentsk 3/4.11.2.6 EXPLOSIVE GAS MIXTURE _

This specification is provided to ensure that the concentration of -

potentially explosive gas mixtures contained in the offgas holdup piping is

maintained below the flammability limits of hydrogen. . Maintaining the concentra-tion of hydrogen below its flammability limit provides assurance that the releases of radioactive materials will be controlled in conformance with the ,

requirements of General Design Criterion 60 of Appendix A to 10 CFR Part 50.

L 3/4.11.2.7 MAIN CONDENSER

-Restricting the gross radioactivity rate of noble gases from the main !

condenser provides reasonable assurance that the total body exposure to a MEMBER OF-THE PUBLIC at and beyond the SITE BOUNDARY will not exceed a small fraction of the limits of 10 CFR Part 100 in the event this effluent is inad-vertently discharged directly to the environment without treatment. This specification implements the requirements of General Design Criteria 60 and 64 of Appendix A to 10 CFR Part 50.

AAv-NCNL %

P%e b 3/4 //-L

-GRAND GULF UNIT 1 0 3/4 11 L i

l

. - . . - _ , _ _ _ _ , . _ . . . . - - _ . . . . _ _ . _ _ _ . _ , . - . - . . - - _ . _ . ~ . _ _ . - _ _ - - . . _-._ ,-. ,, - -- - ,.

__m---,.-...

_ . _ . _ . _ _ _ . ~ . _ _ _ . __-__.____ _ _ _ _._.

vs-m/m M010ACTIVEEFFLUENTS BA S 3/4.1 SOLIO RADIDACTIVE WASTE I

This specification implements the requirements of 10 CFR Part 5 .36a and '

General De gn Criterion 60 of Appendix A to 10 CFR Part 50. The p cess parameters cluded in establishing the PROCESS CONTROL PROGRAM ma include, but are not I ited to waste type, waste pH, waste / liquid / solid ication j agent / catalyst tios, waste oil content, waste principal chemi i constituents, i mixing and curi times. j 3/4.11.4 TOTAL 00 (

This specificati.1 is provided to meet the dose lim ations of 40 CFR i Part 190. The specific tion requires the preparation a d submittal of a i 5pecial Report whenever ye calculated doses from pla generated radioactive I effluents and direct radia on exceed 25 mrems to th total body or any organ, i except the thyroid, which 11 be limited to less tan or equal to 75 mrems. j for sites containing up to 4 eactors, it is highl unlikely that the resultant dose to a MEMBER OF THE *dBLI ill exceed the d :e limits of 40 CFR Part 190 if the individual reactors rema () within twice .e dose design objectives of Appendix 1, and if direct radiatt doses fro the reactor units and outside storage tanks are kept small. Th pecial R ort will describe a course of action that should result in the li itation. of the annual dose to a MEMBER OF :

THE PUBLIC to within the 40 CFR Part 901 nits. For the purposes of the '

Special Report, it may be assumed that t . dose commitment to the MEMBER OF j THE PUBLIC f rom other uranium fuel cH:1 sources is negligible, with the ;

exception that dose contributions fro o r nuclear fuel cycle facil_ities at j the same site or within a radius of km m t be considered. If the dose to ;

any MEMBER OF THE PUBLIC is estima d to ex d the requirements of 40 CFR ,

Part 190, the Special Report with request f r a variance (provided the release conditions resulting in iolation of 4 CFR Part 190 have not already been corrected), in accordance ith the provisio s of 40 CFR Part 190.11 and 10 CFR Part 20.405c, is consi red to be a timely equest and fulfills the ,

requirements of 40 CFR Part 90 until NRC staff act on is completed. The !

variance only relates to t a limits of 40 CFR Part 1 0, and does not apply in !

any way to the other requ rements for dose limitation f 10 CFR Part 20, as !

addressed in Specificati ns 3.11.1.1 and 3.11.2.1. An dividual is not I considered a MEMBER OF HE PUBLIC during any period in ch he/she is engaged i in carryin( out any o eration that is part of the nuclear uel cycle. !

l S

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RAND GULF-UNIT 1 B 3/4 11-6 , i s

T)$ Cil/Cl 3/4.12 RADIOLOGICAL EWIRONMENTAL MONITORING BASE x 3/4.12. HONITORING PROGRAM The ra logical monitoring program required by this specific Lion provides measurements o radiation and of radioactive materials in those posure pathways and fe those radionuclides, which lead to tr.1 highest olential radiation exposures of MEMBERS Of THE PUBLIC resulting from ti station operation .

This monitoring prbgram implementsSection IV.B.2 of Appendi - I to 10 CfR ,

Part 50 and thereby Nupplements the radiological effluent itoring program by verifying that the easurable concentrations of radicaptive materials and levels of radiation art not higher than expected on the (asis of the offluent measurements and modelin .of the environmental exposur pathways. The initially specified monitoring progham will be effective for at east the first three years of commercial operat .

Following this perio , program changes may be initiated based on operation experience.

ThedetectioncapabilitiestequiredbyTab 4.12.1-1 are state-of-the-art for routine environmental measure nts in indu rial laboratories. It shou 1L be recognized that the LLD is defi d as an " priori" (before the fact) limit representing the capability of a me uremen system and not as "a posteriori" (af ter the fact) limit for a particulk me surement. Analyses shall be performed in such a manner that the stated LLDs a be achieved under routte anditions.

Occasionally background fluctuations, u oidably small sample sizes, the '

presence of interfering nuclides, or .he incontrollable circumstances may render these LLDs unachievcble. In ich c s, the contributing factors will ,

be identified and described in the nnual Ra ological Environmental Operating Report.

For a more complete discu ion of the LLD, a d other detection limits, see the following:

(1) HASL Procedure H nual, HASL-300 (reviseo an ally).

(2) Currie, L. A. " Limits for Qualitative Detecti and Quantitative Determinatio - Application to Radiochemistry," nal. Chem. 40, 586-93 (1968).

l (3) Hartwel , J. K. , " Detection Limits for Radioisotopic Counting ,

Techni ues," Atlantic Richficld Hanford Company Repor ARH-2537 (Jun 22, 1972).

i sRAND GULF-UNIT 1 B 3/4 12-1 I

, . - . . - . ~ - , - . . - - - . - - . . - . , - - - . . . - - . - - . - . , . . .~ _ . . - . . . . - , . - - - - , . - . . - -

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

Ps cii/ci !

NDIOLOGICALENVIRONMENTALMONITORING BA 5 i

3/4.1 x LAND USE CENSUS -

N !

This specification is provided to ensure that changes in the ue. of areas :

at and beyon'q the SITE BOUNDARY a.ae identified and that modificati s to the j radiolo0ical b Qvironmental monitoring program are made if require by the results of the Nensus. The best information from door-to-door } rvey, visual (

or aerial survey \or from consulting with local agricultural au horities shall ;

be used. This ceh us satisfies the requirements of Section 1 .B.3 of Appendix ! !

to 10 CFR Part 50.

provides assurance t Restricting the census to gardens of gry ter than 50 m2 tsignificantexposurepathwaysvia)eafyvegetables i will be identified andsmonitored since a garden of this 42e is the minimum required to produce the\ quantity egetables assumed in '

Regulatory Guide l.109 fbt consump(26 kg/ayear) tion by child.of leafy To determine this i minimum garden size, the following assumptions were de: (1) 20% of the garden was used for growing \proad leaf vegetation .e., similar to lettuce and cabbage), and (2) a vegetation yield of 2 kg/n . 4 3/4.12.3 INTERLABORATORY COMP SON PROGRAM The requirement for particip fon in an anproved Interlaboratory Comparison [

Program is provided to ensure that It! depen nt checks on the precision and accu- <

racy of the measures of radioactive m'a.ter) 1 in environmental sample matrices are performed as part of the quality als france program for environmental .

monitoring in order to demonstrate tha t,he results are valid for the !

purposes of Section IV.B.2 of Appendi !' 10 CFR Part 50. '

}

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t MRANDGULF-UNIT 1 B 3/4.12-2 wv.- - . . . - - .,r - ,-,-.m. - = .e.-,.. _.,--m , . . . , , - - . .

v~

T>$ <o/ol For .Inermdim A ADMINISTRATIVE CONTROLS SAFETY LIMIT VIOLATION (Continued)

c. The Safety Limit Violation Report shall be submitted to the Commitsion, the SRC and the Vice President, Operations GGNS within 14 days of the violation. lt ,

d.

_byCritical operation of the unit shall not be resumed until authorized the Commission.

6.8 PROCEDURES AND PROGRAMS 6.8.1 Written procedures shall be established, implemented and maintained

-covering the 1ctivities referenced below:

a.

The applicable procedures recommended in Appendix "A" of Regulatory Guide 1.33, Revision 2, February 1978. '

b. Refueling operations.

c. Surveillance and test activities of safety related equipment.

d. Security Plan implementation.

e. Emergency Plan implementation,

f. Fire Protection Program implementa' tion.

g. PROCESS CONTROL PROGRAM implementation.

h. 0FFSITE DOSE CALCULATION MANUAL implementation.

i. Quality Assurance Program for effluent and environmental monitoring, using the guidance in Regulatory Guide 4.15, February 1979.

6.8.2 Each procedure of 6.8.1 above, and changes thereto, shall be reviewed as required by 6.5, above, prior to implementation and shall be reviewed periodically _as set forth in administrative procedures. -

6.8.3 The following programs shall be established, implemented, and maintained:

a. Primary Coolant Sources Outside Containment A program to reduce leakage from those portions of systems outside containment that.could contain highly radioactive fluids during a serious transient or accident to as low as practical levels. The systems include tha: !

1. RCIC system outside containment containing steam or water, except.the drain line to the main conder.ser.

2. RHR system outside containment containing steam or water, except the line to the LRW system and headers that are isolated by i manual valves.

3. HPCS system.

4. LPCS system.

5. Hydrogen ~ analyzers of the combustible gas control system. !

t L GRAND GULF-UNIT 1 6-14 Amendment No. 74 I

P6 - A l/of ADMINISTRATIVE CONTROLS PROCEDURES AND PROGRAMS (Continued)

6. Feedwater leakage control system.

7. Post-accident sampling syst a

8. Suppression pool level detection portion of the suppression pool makeup system.

The program shall include the following:

1. Preventive maintenance and periodic visual inspection requirements, and

2. Integrated leak test requirements for each system at refueling cycle intervals or less,

b. In-Plant Radiation Monitoring A program which will ensure the capability to accurately determine the airborne iodine concentration in vital areas under accident conditions. This program shall include the following:

1. Training of personnel,

2. Procedures for monitoring, and

3. Provisions for maintenance of sampling and analysis equipment.

c. Post-accident Sampling A program which will ensure the capability to obtain and analyze reactor-coolant, radioactive iodines and particulates in plant gaseous effluents, and containment atmosphere samples under accident conditions. The program shall include the following:

ggg7 1. Training of personnel,

2. Procedures'for sampling and analysis, A s3. Provisions for maintenance of sampling and analysis equipment.

6.9 REPORTING REQUIREMENTS ROUTINE REPORTS 6.9.1 In addition to the applicable reporting requirements of Title.10, Code of Federal Regulations, the following reports shall be submitted to the Regional Administrator of the Regional Office, unless otherwise noted.

STARTUP REPORTS 6.9.1.1 A_tummary report of plant startup-and power escalation testing shall l

be submitted following (1) receipt of an operating license, (2) amendment to the license involving a planned increase in power level, (3) installation of i fuel that:has a different design or has been manufactured by a different fuel 1 supplier, and (4) modifications that may have significantly altered the nuclear, L

-thermal, or hydraulic performance-of the unit.

GRAND GULF-UNIT 1 6-15 A m e4dm ealt MD. --.

i e w.. - , .,, .w* ,-..-,.-r a. - < .-.---n+,.-- ,w-y ,.---. - <,,.- -,,y, ..w m m 9., ,,- _.. ,,-w,ec--r. - - - ,- ,-y .-g--c %,-m--r,,.---g.w- ,=p,e,--.es.

.i I

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PS-91/01 Insert _to_Page 6-15 l l

Insert A I

d. Radim etiv5L lHfluent_Contrals_ Program A program shall bo provided conforming with 10 CPR 50.36a for the control of radionctivo offluents and for maintaining thn donnn to HEHilERS OP-Tile PUBhlC from radionctivo offluents as low as reasonnbly achievnhin. Thn program (1) shall bn contained in thn ODCM, (2) shall be implemented by operating procndurns,- nnd (3) shall includo remedial act lons to bn taken whennver the program limits arn exceednd. Thn program shn11 Includn the following elements:

1. Limitations on _ the opornbility of radionctivo liquid and gaseous monitoring inst rumnntation including surveillance insts and set. point determination in accordance with the methodology in t he ODCH,

2. Limitations on thn concentrations of radioactivn mat erial talensed in liquid ef fluents to UNRESTRICTED AREAS conforming to 10 CFR Part 20, Appendix 11 Tnhin 11, Column 2,

3. Monitoring, sampling, and analysis of radionctivo liquid and gaseous ef fluents in accordance with 10 CFR 20.106 and with the methodology and parameters in thn ODCM,

4. Limitations on the annuni and quarterly doses or doso commitment to a MEMBER OF Tile PUBLIC from radioactive materints In liquid of flunnts rninnsed from thn unit to UNRESTRICTED' AREAS conforming to Appendix 1 to 10 CFR Part. 50, S. Determinntion of cumulative and projected doso contributions from radionetivo offluents for thn curtnut calendar quarter-and current calendar year in accordance with the mothmlology and pornmetets in the ODCM nt. least nvory 31 days,

6. ,1. imitations on the operability and use of the liquid and gaseous efflunut treatment systems to ensurn that. the approprinto portions of ~ thesn cystems are used to reduco relenses of. radioactivity when thn projected-doses in a 31-dny porlod would oxceed 2 percent of the guidnlines for the annual--

dose or dose commitment coniorming to Appendix 1 to 10 CFR Part 50,

7. Limitations ou the dose rate result.ing from radioactivo mntorin1 releasud in gaseous offluents to arens beyond the SITE BOUNDARY conforming to the doses associated with 10 CFR Part 20, Appendix 11, Tablo II, Column 1, M9104241/SNLICFLR - 1

-PS-91/01 Insert _to_Page 6-15

d. continued

8. I,lmitations on thn antmn) and quarterly air doses result ing f rom nohin gases rniensed in gaseous ef flunnts fiom the unit

-to areas beyond tho SITE It00NDARY conforming to Appnndix 1 to 10 CI'R Pa r t .'O ,

9. himitations on t he nnoual and quarterly doses to n HfHitCR OP Tile PUllh10-from iodinn-131, lodinn-133, tritium, and all

-radionuclides in porticulatn form with half-lives granter than 8 days -in gaseous of fluents released f rom thn unit to ornns beyond the 81TC lt00NDARY conforming to Appendix 1 to 10 CPR Part. So, and

10. himitations on the annual dosn or doan commitment to any MtHilER OF Tile PUIII,10 due to relensos of radianctivity nnd to radiation from urnnium fuct cycin pources conforming to 40 CFR Part 190.

n. Radiological _ Envit:onmonta 1 Hon {loring, Program A program shnll hn provided to monitor t hn radiation and radionuclidos in thn environn of the plant. The program shall provido (1) representativo measurements of radianctivity in the highest polontial exposurn pathways, and (2) verification of the accuracy of thn of fluent monitoring-program and modeling of environmental exposurn pathways. The program shall (1) he contained in the ODCH, (2) conform to the guidance of Appendix ! to 10 CFR Part 50, and_(3) include the following:

1. lionitoring, sampling, nun tysis. nnd tcport ing= of radiat ion and radionoclides in the environment in accordanco with the methodology and pornmeters in thn ODCH,

2. A 1.nnd Uso Cnnsus to ensurn that changer. In the use of nrens at and bnyond thn SITE It0UNDARY arn identifind and t.hnt modificalions t.o the monitoring program nrn made if. required by thn rennits of this census, and

3. - Part.icipation in an Interinboratory Comparison Program to ensure that independent. checks on the precision and occuracy -

of the monsnrements of.radioactivn materials in environmental snmplo mat ricos -nrn performed as part of thn quality assuranco pregram for environment al monitoring.

l M9104241/SNh1CFhR - 2

, T5 Al/OI ADMINISTRATIVE CONTROLS ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORTM

.TNMRT h(.1. 6 Routine radiological environmental operating reports covering the A operation of the unit during the previous calendar year shall be submitted,pfior

/

to Ma\y of each year. The initial report shall be submitted prior to Mpy 1 ofthey(ea(followinginitialcriticality. f N /

6. 9.1. 7 The anttual radiological environmental operating reports stiall include !

summaries. interpretations, and an analysis of trends of the res,ults of the radiological enviroinaptal surveillance activities for the ryp6rt period, iocludingacomparisotNithpreopera6.onalstudies,opergtfonalcontrols(as appropriate), and previothsenvirorrental surveillance riports and an assess-ment of the observed impactb4f the plant operatio,n,o,n the environment. The reports shall also include theN ?sults-of land use censuses required by '

Specification 3.12.2.

are detected by the monitoring, the(report shsli provide an analysis of theIf '

problem and a planned course of action D 411eviate the problem.

The annual radiological environmental Tag reports shall include summarized '

Guide 4.8, December 197: of '

all and radiological tabulated environmental,4 resultsmples taken format' in the duri th9 report of Regulat' period. Devia- dry'hg.h tionsfromthesamplingprjoramidentifiedinTechn l Specification 3.12.1 shall be reported. IntpeeventthatsomeresultsareNqtavailableforinclu-sion with the report. ,tne report shall be submitted notinb and explaining the reasons for the misping results. Themissingdatashallbehbmittedassoon as possible in a f;pplementary report. ;

The reportsA all also include the following: a summary description'Nf the radiologJr'al environmental monitoring program; a map of all sampling ldqtions keyed f tt a table giving distances and directions from one reactor; and tht>

, resufts of licensee participation in the Interlaboratory Comparison Program, pequired by_Soecification 3.12.3.

SEM1 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPOR JTN6EPT 9py Routine radioactive release icports covering the eperation of thynf t i

3 during the h lgnd July 1 of each year.arevious after Janua 6 months The period of operation of the fir t'rTportshallshallbe submitte begin with the dal'e'of s initial criticality, s N /

3/

/

A single submj.LtaT',may be made f or a multiple unit ' station. The submittal

/><N N s should combine those sections that are common to all unttb at s the tation;

howeve6 for units with separate radwaste systems, the submittal all

,,A fecify the releases of radioactive material for each unit. ,

GRAND GULF-UNIT 1 6-17 hylendmegh fJb. . _ _ . l

h l

l PS-91/01 I l

Insert to Paga_6-17 !

Insort A 6.9.1.6 1hn Atuiun! Radiological Envitonmental Opernting Report j covering thn operation of thn unit during the previoun :

calendnr yont shnll hn submitted before May 1 of each year. f 6.9.1.7 Thn report 8hn11 include summnraen, int erpret at ionn, ntut !

nnalysis of tresuln of the renults of the Rndiological l Environmental Monitoring Program for the report inn per lod. >

The mot nrint provided ahn11 he consist ent wit h thn object tven outlined in (1) thn Dix:H niul (2) noct f ann IV.H.2 IV.II.3, and IV.C of Appendix ! to 10 CPR Patc 50 insert II: ;

I 6.9.1.8 Thn Semintinunt Radioactive Effluent Relennn Report covering ;

thn operation of t hn unit during thn prnviona 6 monthN of f oporation ahn11 ho nuhmit Led within 60 dnyn nf tnr Janunry 1 '

and July 1 of enth yonr.

6.9.1.9 The report shall includo a summary of thn quantit ton of radionctivo liquid and gnNeouM PffluentR and Molid WHHln [

roinnned f rom t he unit. The mat erint provided ahn11 he (1) !

consistent with the objectiven outlined in the ODCH niul PCP ,

niul (2) in conformnnen with 10 CPR 50.36n and Section IV.H.1 ;

of Appendix 1 to.10 CFR Part 30.

I 1

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i Ir1104241/SNI.lCFI,R - 3

.' 75-41/61 ADMINISTRATIVE CONTROLS SEMIANNUAL RADI0 ACTIVE EFFLUEhi _ a ASE REPORT (Continued)

%. 9.1. 9 The radioactive effluent release reports shall include a summary of h3 tr quantities of radioactive liquid and gaseous effluents and solid waste rel ed from the unit as outlined in Regulatory Guide 1.21, " Measuring, Eval ing, and Reporting Radioactivity in Solid Wastes and Releases of Radio.

active terialsinLiquidandGaseousEffluentsfromLightWaterCooledNudear Power P1 qts," Revision 1, June 1974, with data summarized on a quarterly ' asis following the format of Appendix B thereof.

The radioacti\ effluent release report to be submitted within 60 days after January 1 of e year shall include an annual summary of hourly me orological data collected o r the previous year. This annual summary may b ither in the form of an hou -by-hour listing ~of wind speed, wind directioj , and atmos-pheric stability, an precipitation (if measured) on magnetic tpe, or in the fcrm of joint frequen distributions of wind speed, wind di tion, and atmos-pheric stability. Thishame report shall include an assess nt of the radiation doses due to the radioact) e liquid and gaseous effluents released from the unit or station during the evious calendar year. Thi same report shall also include an assessment of the adiation doses from rad active liquid and gaseous ef fluents to MEMBERS OF THE PUB IC due to their acti ities inside the SITE BOUNDARY (Figure 5.1.3-1) during he report period All assumptions used in making these assessments, i.e., sp .ific activit , exposure time and location, shall be included in these reports. The meteor logical conditions concurrent with the time of release of radioacti q mater als in gaseous effluents (as determined by sampling frequency and meh ur ent) shall be used for determining the gaseous pathway doses. The assessmen of radiation doses shall be performed inaccordancewiththeOFFSITEDOSECAl%L 10N MANUAL (ODCM).

The Semiannual Radioactive Effluent Rrfease R. ort shall identify those radiological environmental sample ppf f ameters an locations where it is not possibleorpracticabletocontiny(toobtainsamlesofthemediaofchoice at the most desired location or ime. In addition, the cause of the unavail-ability of samples for the pat ay and the new locat n(s) for obtaining replacement samples should b identified. The report pould also include a revised figure (s) and tabl 5) for the'00CM reflecting t e new location (s).

The radioactive effluent release report to be submitted wi in 60 days after January 1 of each year hall also include an assessment of r lation doses to the likely most expo d MEMBER OF THE PUBLIC from reactor rele ses and other nearby uranium fue cycle sources (including doses from primary ffluent path-ways and direct r diation) for the previous 12 consecutive months .o show conformance. wit 40 CFR 190, Environmental Radiation Protection Sta ards for Nuclear Power peration. Acceptable methods for calculating the dose contribu-tion from i uid and gaseous effluents are given in Regulatory Guide 1. 09, Rev. 1.

The radio tive effluents release shall include the following information or each ty of solid waste shipped offsite during the report period:

. Container volume,

b. Total curie quantity (specify whether determined by measurement or estimate),

GRAND GULF UNIT 1 6-18 Amendmed 90.

~P6 - 91/01 ADMINISTRATIVE CONTROLS SEMIANNUAL RADICACTIVE EFFLUENT RELEASE REPORT-(Continued)

Principal radionuclide (specify whether determined by measuremen ar [

m timate),

N

d. Type ofw te (e.g., spent resin, compact dry waste 4 aporator

-bottoms),

e. Type of container (e. %LSA, Type A yp 8. Large Quantity), and

f. Solidification agent (e.g , urea formaldehyde).

The radioactive effluent release-f6 ports shal nc ude unplanned releases from thesitetotheUNRESTRICIED'fREAofradioactivem(ateHa(singaseousandliquid effluents on a quar M7 basis.

TheradioacMy effluent release reports shall include any changes o4he PROCES$ {0f4 TROL PROGRAM (PCP), 0FFSITE DOSE CALCULATION MANUAL (00CM) o Nradio-3ctive waste systems made during the reporting _ period. N HONTHLY OPERATING REPORTS 6.9.1.10 Routine reports of operating statistics and shutdown experience, including documentation of all challenges to main steam system safety / relief valves, shall be submitted on a monthly basis to the Director, Office of Management and Program Analysis, U.S. Nuclear Regulatory Commission.

Washington, D.C. 20555, with a copy to the Regional Administrator of the Regional Office no later than the 15th of each month following the calendar month covered by the report.

SPECIAL REPORTS 6.9.2 Special reports shall be submitted to the Regional Administrator of the Regional Office within the time period specified for each report.

6.10 RECORD RETENTION In addition to the applicable record retention requirements of Title 10, Code of Federal Regulations, the following records shall be retained for at least the minimum period indicated.

6.10.1 The following records-shall be retained for at least five years:

a. Records and logs of unit operation covering time interval at each power level.

b. Records and logs of principal maintenance activities, inspections, repair and replacement of principal items of equipment related to nuclear safety,

c. All REPORTABLE EVENTS.

l l GRAND GULF-UNIT 1 6-19 AnVndMett MO.

l T>$ - A I /O l 4 ADMIN!5fAAT!vt teNTa0L5 l 6.10 Rif040 MTDffl0N (Cent 1Ause) ,

d. inspections and calibrations !

Recd required 18e of Technical by these surveillance specif activitiesItations. j

e. Records of changes made to the procedures requi md by Specification i 6.8.1. ,

f. Records of radianctive shipmenta.

g. Records of sealed swece and fission detector luk tests and results.

h. Records of annual physical inventary of all maled source estarial of Mcord.

6.10.2 The following records shall be retained for the duration of the Unit Operating License: ,

s. Records and drawing changes Mflecting unit design modificattens made ,

to systems and equipment described in the Final Mfety Analysis Report,

b. Rect,res of new and irradiated fuel inventary, fuel trenefers and ;

assensly burne histories. ;

c. Records of radiation egesum for all individuals entering radiatten t control areas,

d. Records of gaseous and liquio radioactive ester 181 released to the !

environs. ;

e. Records of transient or operational cycles for these unit components l 1eentified in Table 5.7.1-1. j

f. Records of reacter tests and experiments,

g. Records of training and qualification for current seaters of the unit staff.

/

h. Records of in service inspections perfereed pursuant to these Technical Specifications.

i

1. Records of Quality Assurance activities requind by the Operational Quality Assurance Manual not listed in Section 6.10.1. j

j. Records of reviews perfomed for changes made to procedures or equipment ,

or reviews of taats one uperiments pureuant to 10 CFR 50.59.

k. Secorda of meetings of the P5RC and the SRC. j i

1. Records of the service lives of all hydraulic and mechanical snubbers including the date at which the service life commences and ass: ciated l

installation and eatntenance records.

l s. Records of analyses required by the radiological environmental !

monitoring program, l 1%EC7 '

l As >

GRAND GULF UNIT 1 E 20 Amen:ssent No.21, r

f l

PS-31/01 1ns.arLto_P_ age _6 20 Insert A:

n. Records of rovjewn perforsned for changes inndo to the OITSITE DOSE CAI,CUI,ATION MANUA! and the PROCESS CONTROI. PROGRAM.

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I t19104241/SNI,1CFI.R - 4 ol - - _ . . _ _ . - . _ , , _ . _ . _ _ . , , _ , , _ _ _ . . , _ _ . . . . , _ , _ _ _ _ . _ , _ _ , _ _ _ _ . _ _

-. 'P6 - 9 I/O I ADMINISTRATIVE CONTROLS 6 12 -HIGH RADIATION AREA (Continued) excess of 1000 mrem

that are located within large areas, such as the contain-ment, where no enclosure exists for purposes of locking, and no enclosure can be reasonably constructed around the individual areas, then that area shall be roped off, conspicuously posted and a flashing light shall be activated as a warning device. In lieu of the stay time specification of the RWP, continuous surveillance, direct or retnote, such as use of closed circuit TV cameras, may be made by personnel qualified in radiation protection procedures to provide positive exposure control over the activities within the area.

6.13 PROCESS CONTROL PROGRAM (PCP)

D 3 s1- The PCP shall be approved by the Commission prior to implementation.

O- 6.13.7 cc see initiated changes to the PCP:

? 1NSERT I

1. -Shall be ubmitted to the Commission in the Semianpi Radioactive 1

A Ef fluent Rehne Report for the period in whic he change (s) was made. This submittal shall contain:

\

a. Suf ficicntly detail'eddnformJia n to totally support the rationale for the change without btylefit of additional or supplemental informationi N

b. A determinati t at the change diD n q reduce the overall conforman of the solidified waste produc_t

existing criteria for s d wastes; and

c. ocumentation of the fact that the change has reviewed and

..found acceptable by the PSRC.

2. Shall become effective upon review and acceptance by the PSRC. \.

6.14 0FFSITE DOSE CALCULATION MANUAL (00CM)

D 4 ( The' ODCM shall be approved by the Commission prior to implement tlon Ita$ERT 6.14.2 License binjtiated changes to the 00CM:

3-

1. Shall be submitte os the Commissio p -tie Semiannual. Radioactive l.' Effluent Release Report forsthp period in which the change (s) was made.

ThissubmittalfaWcohtaint

a. Suf fijc anthtailed information to tataLQ support the pat 45nale for the change without benefit of addi Qonal or l supplemental information. Information submitted sh"Out onsist l-y [ of a package of those pages of the 00CM to be changed-wt hwAc Measurement made at 18" f rom source o.f radioactivity.

GRAND GULF-UNIT 1 6-22 Arvica2mett - 63c>. _ . _ _ .

..-..,~..-L.-

fi PS-91/01 l Insert _to.Page 6-22 Insert A

-Changes to the PCpt

a. Shall_be documented and records of reviews performed shall be retained.ns required by Specification 6.10.2n. This documentat.fon shall contain:

-l"

1) Sufficient informatJon to support the change together with the approprinto analyses or ev91untions justifying thn changn(s) and ,

2) A determination that the chnngo will maintain the overall conformance of thn solidified wanto product to exist. lug ,

requirement s of Federal, St at o, or other applicabin i regulations. ;

b. Shill becomo effectivo after review and . .:eptance by the pSRC_nnd i the approval of the General Manogor, plant Opnrations.

Insert B: f Changer, to thn ODCMt

a. Shall be documented and records of reviews performed shall be retained as required by Specification 6.10.2n. This documentation

'shall-containt

1) Suf ficient information to support the change- together with thn ;

appropriato analyson' or evnluations justifying the change (s) ,

and

2) . A determination that the change will maintain the invol of radioactive offluent. control required by 10 CFR 20.106, 40 CFR ,

part 190, 10 CPR 50.36n, and Appendix I to 10 CFR part 50 and not adversely impact the accuracy or relinhility of of fluent, ;

dose, or antpoint. calculat. ions.

l h.- Shn11 become offnctivo af ter review 'and acceptanco by the PSRC and the approval of the General Managor, plant Operations. ,

i

c. Shall be surmitt ed to the Commission in the form of a complete, [

legibic copy of the entiro ODCH as a part of or concurrent with the !

Semiannual Relionctivo Effluent Release Report for the period of the report in which any change to the ODCM was mado. Each chango-shall be identified by markings in the margin of the the affected ;

pages, clearly indicating the area of the page that was changed, }

and shall indicato the datn (e.g., month / year) the chnuge was !

i

.impicmented. l l' l M9104241/SNh1CFLR - 5 [

l p5-Wo i l ADMINISTRATIVE CONTROLS 6.14 0FFSITE DOSE CALCULATION MANUAL (00CM) (Continued) page numbered and provided with an approval and data box, t,o. o gal.htT' ith appropriate analyses or eval m tions justifying t a 4 ange(s);

Dh-~~ b. A Nt t the change will n e uce the accuracy or reliability of d a ulation- Mistpoint determinations; and

c. Documentat the fact that the chang been reviewed and fou ceptable by the PSRC.

Shall become effective upon review and acceptance by the PSRC.

1 15 MAJOR CHANGES TO RADIDACTIVE WASTE TREATMENT SYSTEMS

6.15. Licensee initiated major changes to the radioactive waste systems, liquid, aseous and solid:

1. S all be reported to the Commission in the Semiannual Radio- tive Eff) ent Release Report for the perf7d in which the eval ion was review d by the PSRC. The discussion of each change s I contain: -

a. A sum ry of the evaluation that led to the dp ermination that the cha e could be made in accordance wth 4 CFR 50.59; b, Sufficien tailed information to tot J y support the reason for the change ithout benefit of ad i ional or supplemental information;

c. A detailed descripti of the uipment, components and processes involved and ei erfaces with other plant systems;

d. An evaluation of the ch ge hich shows the predicted releases of radioactive materip s in 1 uid and gaseous effluents and/or quantity of solid wpfte that di er from those previously predicted in the cense applicati and amendments thereto;

e. An evaluatio of the change which show the expected maximum exposuces MEMBERS OF THE PUBLIC in th UNRESTRICTED AREA and to t general population that differ - om those previously estimaA d in the license application and amen ents-thereto;

f. A ompar.ison of the predicted releases of radioac ve materials,-

n liquid and gaseous ef fluents and in solid waste (, n the actual releases for the period prior to when the changes are o be made;

L[enseemaychoosetosubmittheinformationcalledforinthisSpecificatio.

As part of the annual FSAR update.

GRAND GULF-UNIT 1 6-23 Amend mett Mo ,

h M -9l[Of I r

A0MINISTRATIVECONTROLS_

_i 6.1 . MAJOR CHANGES TO RADI0 ACTIVE WASTE TREATMENT SYSTEMS (Continued)

g. An estimate of the exposure to plant operating personnel as a j result of the change; and !

h' Documentation of the fact that the change was review d and found ;

acceptable by the PSRC. l

2. Shall become effective upon review and acceptance by - le PSRC. ;

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i Atiacliment 4 to GNRO-91/00084 l

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I I

I l'R0l'OSEI) REVISION OP Tile OPPSITE 1)DSE cal,CUI.ATION HAN(IAI.

l GRANI) GUI F NOCI. EAR STATION 1-l (For information Only)

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i-Offs 11E DOSE CALCULATION MANUAL i

GRAND GULF NilCLEAR STATION i-

\

Draft GRAND GVl.F.-UNIT 1 ErMT5719.48/5NLICFLR

INTRODUCT10N The Offsite Dose Calculation Manual (ODCM) describes the methodology and parameters used in the calculation of offsite doses resulting from radioactive liquid and gaseous effluents, in the calculation of liquid and gaseous effluent monitoring Alarm / Trip Setpoints, and in the conduct of the Radiological Environmental Monitoring Program. The ODCM also contains (1) the Radioactive Effluent Controls and Radiological Environmental Monitoring Programs required by Technical Specification (TS) 6.8.3 (2) descriptions of the information that is included in the Annual Radiological Environmental Operating and Semiannual Radioactive Effluent Release Reports required by TS 6.9.1.6, 6.9.1.7, 6.9.1.8 and 6.9.1.9 (3) a list and graphical description of the specific sample locations'for the Radiological Environmental Monitoring program, and (4) diagrams of the liquid and gaseous radwaste treatment systems.

Procedural details not associated with solid radioactive wastes which were previously located in the TS have been relocated to the ODCM. All the chenges are made to provide conformance with the guidance of Generic Letter 89-01,

" Implementation of Programmatic Controls for Radiological Effluent Technical Specifications in the Administrative Controls Section of the Technical Specifications and the Relocation of Procedural Details of RETS to the Offsite Dose Calculation Manual or to the Process Control Program", January 31, 1989.

The ODCM will be maintained at the station for use as a reference guide and training document of accepted methodologies and calculations. Changes in the calculational methods or parameters will be incorporated into the ODCM in order to assure that the ODCM represents the present methodology in all applicable areas. Computer software to perform the described calculations will be maintained current with this-00CM.

Changes to the ODCM shall be accomplished as specified in TS 6.14. Records of reviews performed for changes made to the ODCM shall be retained for the duration of the Unit Operating License as specified in TS 6.10.2.

ii Draft GRAND GULF, UNIT 1

__ EFMTS719._48/SNLICFLR

a QQLB IABLE OF CONTENTS Page MANUAL APPROVAL SHEET .......................................... i 1NTR00ucTiON ....................................... ii TABLE OF CONTENTS ...-.......................................... iii-iiic LIST OF FIGURES ................................................ iv LIST OF TABLES ................................................. v LIST OF REFERENCES-............. ............................... vi LIST OF EFFECflVE PAGES ........................................ vii 1.0 LIQUID EFFLUENTS 1.1 Liquid Effluent Monitor Setpoints 1.1.1 Liquid Radwaste Ef fluent Line Monitors . . . . . . . . . 1.0-1 1.2 Oose' Calculations -for Liquid Ef fluents 3.2.1 Maximum ~ Exposed Individual liodel .............. 1.0-7 1i2.2 Dose Projection ................................ 1.0-8 1.3- Liquid:Radwaste-Treatment System ......................... 1.0-15 ;

-2.0 GASE0VS' EFFLUENTS 2.1 Gaseous Effluent Monitor Setpoints 2.1.1 Continuo'- V'"' f l a ti on Mon i tor s . . . . . . . . . . . . . . . .

. 2. 0 2.1.2 Text Deleted-............... ................... 2.0-3 2.1._ Gaseous Effluent Dose Calculations-

2. 2.1- ~ : Unrestricted' Area-Boundary Dose ....... ........ 2.0-7 2.2.2 : Unrestricted Area Dose to Individual ........... 2.0-9 1

2.2.3 Dose! Projection ................................ 2.0-10b. l 12.3 N(teorological Model 2.3.1 Atmospheric Dispersion ......................... 2.0-24 2.3.2 -Deposition-..................................... 2.0-25 2.4 Definit ions- of Gaseous Ef fluents Parameters . . . . . . . . . . . . . . 2.0-27 12.5 Ga seous Padwa ste Treatment Sy stem . . . . . . . . . . . . . . . . . c . . . . . . 2. 0 < 75 2.6' Annual Dose Commitment ..-.................................

2.0-36 2.6.1 Direct Radiation Dose Measurement................-2.0 3.0 RADIOLOGICAL' ENVIRONMENTAL MONITORING-t3 3.1 .Samoling Locations ....................................... 3.0-1 iii Draft GRAND GULF, UNIT 1 EFMT5719.48/SNLICFLR

_ODCM TABLE OF CONTENTS Page APPENDIX A - RAD..I.OL.OGIC.AL EFFLUENT C6HTP01.S AND A-0

_ RAD _I OL..O_G_I cal _E_ N__VI R.O. N. ME_N T AL_M. O_N.I_TO._R I NG.. _PR_OGR.A_MS..

DEFINITION}

1.1 'CTION ...........................

.................... A-1 1.2= CHANNEL CALIBRATION ............ ................... A-1 1,3 CHANNEL CHECK ....... ................................. A-1 1.4 CHANNEL FUNCTIONAL CHECK .................................. A-1 1.5- DOSE EQUIVALENT l-131 ..................................... A-1 1.6 FPEQUENCY NOTATION ............ ........................... ,*-1 1.7 GASEOUS RADWASTE TREA1 MENT (OFFGAS) SYSTFM . . . . . . . . . . . . . . . . A-2 1.8 MEMBER (s) 0F=THE PUBLIC ................................... A-2 1.9 0FFSITE DOSE CALCULATION MANUAL (00CM) .................... A-2 1.10 OP ERABLE - - OPER ABI LI TY . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . A-2 1.11 OPERATIDHAL CONDITION - CONDITION ....................,..... A-2 1.12 PROCESS CON 1ROL PROGRAM (PCP) ............................. A-2 1.13 R AT ED TH E RMAL POWER . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . A- 3 1.14 SITE BOUNDARY ............................................. A-3 1.15 SOURCE CHEC% ....................... ................... A-3 1.16 tiler MA L POW E R . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . A - 3 1.17 UNRESTRICIED AREA .......................................... A-3 1.18 VENTILATION EXHAUST TREATMENT SYSTEM ...................... A-3 TABLE 1.], SURVEILLANCE FREQUENCY NOTAT10N ...................., A-4 TABLE 1.2, OPERATIONAL CONDITIONS .............................. A-5 liia Draft GRAND GULF, UNIT 1 EFMT5719.48/SNLICFLR

ODCM

. TABLE _OF_ CONTENTS Page LIMITiljG_ CONDITIONS FOR_0P. ERAT _I_0N AND_SU.RVEILLANCE_ RE_QUIREMENT S . . . . . A-6 3/4.0 APPLICABILITY ............................................. A-7 3/4.3 INSTRUMENTAT10N 3/4.3.7 MONITORING INSTRUMENTAL 10N Radioactive Liquid Effluent Monitoring Instrumentation ............................... A-9 Radioactive Gaseous Effluent Monitoring Instrumentation ............................... A-14 3/4.11 RADIDACTIVE EFFLUENTS 3/4.11.1 LIQUID EFFLUENTS Concentration ................................... A-23 Dose ............................................ A-27 -

Liquid Waste Treatment .......................... A-28 3/4.11.2 GASEOUS EFFLUENTS Dose Rate ....................................... A-29 Dose - Noble Gases .............................. A-13 Dose - iodine-131. lodine-133, Tritium, and Radionuclides in Particalate Form ............. A-34 Gaseous Radwaste Treatmerr ...................... A-35 Ventilation Exhaust Treatment ..... ............. A-36 3/4.11.4 TOTAL DOSE ...................................... A-37 3/4.12 RADIOLOGICAL ENVIRONMENTAL MONITORING 3/4.12.1 MONITORING PROGRAM .............................. A-38 3/4.12.2 LAND USE CENSUS ................................. A-48 3/4.12.3 INTERLABORATORY COMPARISON PROGRAM .............. A-49 iiib Draft GRAND GUI,F, UNIT 1 EFMT5719.48/SNLICFLR

ODCM TABLE OF CONTENTS Page

BASES...............................................................A-50 3/4.3 - INSTRUMENTATION 3/4.3.7 MONITORING INSTRUMENTATION-Radioactive Liquid Effluent Monitoring Instrumentation ,..._........................... A-51 Radioactive Gaseous Effluent Monitoring Instrumentation ............................... A-51 3/4.11 RADIDACTI'!E EFFLUENTS 3/4.11.1 LIQL'ID EFFLUENTS C o n c e r. t r a t i o n . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . A- 5 2 Dose ............................................ A-52 Liquid Waste Treatment ... ...................... A-53 3/4.11.2 . GASEOUS EFFLUENTS Dose-Rate ....................................... A-54 Dose - Noble Gases .............................. A-54

-Dose - Iodine-131, Iodine-133, Tritium and Radionuclides in Particulate Form ............. A-55 Gaseous-Radwaste-Treatment and Ventilation Ex h a u s t T re a tme n t . . . . . . . . . . . . . . . . . . . . . . . . . . . . . - A- 5 6 3/4.11.4 Total Dose-...................................... A-57 3/4.12- RADIOLOGICAL 1 ENVIRONMENTAL MONITORING 3/4.12.1 MONITORING PROGRAM .............................. A-58 3/4.12.2 LAND USE CENSUS ................................. A-59 3/4.12.3 -!NTERLABORATORY COMPARISON PROGRAM .............. A-59 ADMINISTRATIVE CONTROLS ............................................. A-60

'6.9.1.6 Land 6.9.1.7 Annual Radiological Environmental Operating Report ................. .............. A G.9.1.8 and 6.9.1.9 Semiannual Radioactive: Ef fluent Release Report . . A-61' 6.15 MAJOR CHANGES TO RADI0 ACTIVE WASTE TREATMENT SYSTEMS ........... A-64 iiic ' Draft

-GRAND GULF, UNIT 1 EFMT5719.48/SNLICFLR

ti DDCd LIST OF FIGURES Figure Title . Page___

l.0 Example Calibration. Curve for Liquid Effluent Monitor..... 1.0-6 1.3-1 Liquid Radwaste Treatment System.......................... 1.0-16 2.3-1 Plume Depletion Effect for Ground-Level Releases.......... 2.0-31 2.3-2 Vertical Standard Deviation of Material in a Plume. . . . . . . . 2.0-32 2.3-3 Relative Deposition for Ground-Level Releases. . . . . . . . . . . . . 2.0-33 2.3-4. Open Terrain Recirculation Factor......................... 2.0-34 2.5-1 Gaseous Radwaste Treatment System......................... 2.0-35a 3.0-1 Collection Site Locations, 0-5 Mile Area Map.............. 3.0-7 3.0-2 Collec tion Site Lcca tions, General Area Map. . . . . . . . . . . . . . . 3.0-8 3.0-3' ' Collection Site Locations, 0-10 Mile Area Map............. 3.0-9 3.0 Deleted................................................... 3.0-10 i

iv Draft GRAND GULF, UNIT 1 EFMI5719.48/SNLICFLR

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

P i

OD..C_M LIST DE IABLES i

Table Title - Page 1.2-1 Bioaccumulation Factors................................... 1.0-9 ;

1.2-2 Ingestion Dose Conversion Factors Fot Adults.............. 1.0-10 f

.1. 2 Site Related Ingestion Dose Commitment Factor...... ...... 1.0-13 i 2.1-1 Dose Factors for Exposure to a Semi-infinite '

Cloud of Noble Gases...................................... 2.0-6

{

i 2.2-la Pathway Dose Factors for Appendix A Requirement t

3.11. 2.1 a nd Sec t i on 2. 2.1. b (I n f a n t) . ., . . . . . . . . . . . . . . . . . . . . 2. 0- 11 -

2.2-1b. Pathway Dose Factors for Appendix A Requirement :

-i

-3.11.2.1 and Section 2.2.1.b (Child)....................... 2.0-13 i

2.2-2a Pathway Dose Factors for Appendix A Requirement !

4.11.2.3 and Section 2.2.2.b (Infant)...................... 2.0-15 2.222b Pathway Dose Factors for Appendix A Requirement I i

-4.11.2.3-and Section-2.2.2.b (Child)....................... 2.0-17 2.2-2c Pathway Dose Factors for Appendix-A Requirement ;

4.11.2.3 and Section 2.2.2.b-(Teenager).................... 2.0-19 F

2.2-2d Pathway DosefFactors for Appendix A Requirement !

4.11.2.3 and Section 2.2.2.b (Adult)....................... 2.0-21 l

'2.2-3 Controlling Receptors, locations and-Pathways............. 2.0-23 !

2.3-1 Atmospheric Dispersion Parameters for Appendix A Requirements 4.11.2.1.1. 4.11.2.2. 4.11.2.3, 4.11.2.5.1................. 2.0-26 3.0-1 Air Sampler Collection Sites.............................. 3.0-2 !

3.0-2 Miscellaneous Collection Sites........................ . . . . 3.0-3 !

3.0-3 TLD Locations............................................. 3.0-4.

3.0-4 Vege ta tion Sample Sources. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3.0-10 3.0-5 Fish Sample Sources........ ................ . . . . . . . . . . . . . . 3.0-11 ;

1 4

v Draft-l GRAND GULF, UNIT 1 EFMT5719.48/SNLICFLR v..

0D2 LIST _OF REFERENCES

1. Boegli, T. S., R. R. Bellamy, W. L. Britz, and R. L. Waterfield,

" Preparation of Radiological Effluent Technical Specifications for Nuclear Power Plants," NUREG-0133 (October 1978).

2. Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents.for the Purpose of Evaluating Compliance with 10CFR50, Appendix I, U.S. NRC Regulato* 'uide 1.109 (March 1976).

3. Calculation of Ann- Joses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10CFR50, Appendix 1, U.S. NRC Regulatory Guide 1.109, Rev. 1 (October 1977).

4. ' Environmental Report,d Mississippi Power and Light Company, Grand Gulf

'Juclear Station, Units 1 and 2.

5. " Final Safety Analysis Report," Mississippi Power and Light Company, Grand Gulf Nuclear Station.

6. Methods for Estimating Atmospheric Transport and Dispersion of Gaseous-Effluents in Routine Releases from Light - Water - Cooled Reactors, U.S.

NRC Regulatory Guide 1.111 (March 1976).

7'. Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Ef fluents in Routine Releases from Light - Water - Cooled Reactors, U.S.

NRC: Regulatory Guide 1.'111, Rev. 1 (July 1977).

8. Age-Specific Radiation Dose Commitment Factors for a One-Year Chronic Intake, NUREG-0172, November 1977.

vi Rev. 11 - 06/88 GRAND GULF, UNIT 1 EfMT5719.48/SNLICFLR

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1.0 L100ID EFFLUENTS 1.1 -Li_ quid Effluent Monitot1Suetpoints 1.1.1 Liquid Radwaste Effluent Line Monitors Liquid Radwaste Ef fluent Line Monitors provide alarm and automatic termination of release prior to exceeding the concentration limits specified in 10CFR20, Appendix B,-Table II, Column i at the release point to the unrestricted area.

To meet this specification and for the purpose of implementation-of Appendix A Requirement 3.3.7.11, the alarm / trip setpoints for liquid effluent monitors and flow measurement devices are set to assure that the following ,

equation is satisfied: 4 cf s C -!

F+f (1) {

where:

[

C= the effluent concentration limit (Appendix A Requirement 3.11.1.1) implementing 10CFR20 for the- !

site, in pCi/ml.

{

c= The setroint, representative of a radioactivity. t concentration in.pCi/ml, of the radioactivity monitor i

measuring the radioactivity in the waste tank effluent I

line prior to dilution and subsequent release; the i

setpoint,.which is inversely proportional to the j i

volumetric flow of the effluent line and directly .

proportional to the volumetric-flow of-the dilution [

1- stream plus the waste tank effluent stream, represents i a-value which, if exceeded, would result in "I concentrations exceeding the limits of 10CFR20 in the unrestricted area. f l 1.0-1 Dra f t ,

l: $

l GRAND GULF, UNIT 1 EFMI5719.48/SNLICFLR !

r

i f= the waste tank effluent flow setpoint as measured at the radiation monitor location, in volume per unit time, but in the same units as F, below.

F= the dilution water flow setpoint as measured prior-to the release point, in volume per unit time.

At Grand Gulf Unit 1, the available dilution water flow (F) should be constant for a given release, and the waste tank flow (f) and monitor setpoint (c) are set to meet the condition of ' equation 1 for a given ef fluent concentration, C. The method by which this is accomplished is as follows:

Step 1) The isotopic concentration for a waste tank.to be released is obtained from the sem of the measured concentrations as determined by the analysis required in Appendix A Table 4.11.1.1.1-1: H IC , = IC +-C + ICq + C +C (2) 7 I E 8 ;

where:

gCg = the sum of concentrations-C of g

each measured gamma emitter observed by gamma-ray spectroscopy of the waste sample.

C, = the concentration C a f. gross alpha emitters in liquid waste as measured in the monthly composite sample.

[C 3

= the measured concentrations of Sr-89 and Sr-90 in liquid waste as observed in the quarterly composite sample, i

l 1.0-2 Draft

[ GRAND GULF, UNIT 1 EFMT5719.48/SNLICFLR t

C g =.the measured concentration of H-3 in liquid waste as determined from analysis of the monthly composite sample.

Cf = the concentration of Fe-55 in liquid waste as measured in the quarterly composite sample.

The C g terr. will be included in the analysis of each waste tank batch to be released; terms for alpha, strontiums, tritium and iron may be included if analysis of reactor water has shown the presence of these isotopes.

Step 2) The. measured radionuclide concentrations are used to calculate a Dilution Factor, D.F., which is the ratio of total dilution flow rate to waste tank ef fluent flow rate required to assure that the limiting concentration of 10LFR20, Appendix B, Table II, Column 2 are met at the point of discharge.

C D.F. = [ ] x S.F.

i C C C

= [I 9+ a7 3+ t. f] x S.F. (3) g MPC g

MPC s MPC 3

MPC t

where:

C4 = Cg , C,,.C 3 , C t and Cf ; measured concentrations as dyfined in Step 1. Terms C,, C3 , Cg and Cf will be-included in the calculation as-appropriate.

l 1.0.3 Rev. 10 - 12/86 l

l GRANO-G'JLF, UNIT 1 EFMT5719.48/SNLICFLR

MPC$ = MPC g , MPC,, MPC 3

, MPCg and MPC 7

are limiting concentrations of the appropriate radionuclide from 10CFR20, Appendix B. Table II, Column 2. For dissolved or entrained noble gases,-the concentration shall be limited to 2.0E-4 pCi/mi total activity.

S.F. = an administrative safety factor normally applied at Grand Gulf which causes the calculated Dilution Factor to be two (2) times larger than the dilution factor required for compliance with 10CFR20 limits.

Step 3) The maximum permissible waste tank effluent flow rate prior t to dilution, f , is calculated based on a fixed frr.ction of d

the dilution flow rate, F d

F d

+ Id E d

fd s D.F. D.F.

fr Fd "Id (4) where:

F d

= 0.9 x minimum expected dilution flow rate f

d

= maximum permissible waste tank effluent flow rate D.F. = Dilution Factor from Step 2.

NOTE: Equation 4 is valid only for D.F.>1; for D.F.51, the waste tank effluent concentration meets the limits of-10CFR20 without dilution, and f may take on any desired value.

d Step 4) The dilution flow rate setpoint for minimum dilution flow rate, F, and waste tank flow rate setpoint for maximum waste tank effluent flow rate, f, are calculated as follows:

F= Fd = 0.9 x minimum expected dilutien flow rate (5) f=

0.9 x fd = 0.9 x calculated maximum vaste tank flow l

rate for the stated release conditions. (6) 1.0-4 Draft GRAND GULF, UNIT 1 EFMf5719.48/SNLICFLR

Thus, if instrumentation indicates the dilution flow rate falls below the assumed flow rate of 90 percent of the actual dilution flow, or if the waste tank effluent flow rate exceeds 90 percent of the calculated maximum waste tank ef fluent flow rate, the release is terminated (manually or automatically).

Step 5) The radioactivity monitor setpoint may now be specified basedonthevaluesofjC,F,andfwhichwerespecifiedto provide compliance with the limits of 10CFR20, Appendix B, Table II, Column 2. The monitor response is primarily to gamma radiation; therefore, the actual setpoint is based on gC.g The setpoint cora.entration, C,, is determined as follows:

Cm =_ ICq (pCi/ml) (7) fa 9' where f, is the actual (or maximum expected) waste tank ef fluent flow rate. The value of Cm (pCi/mli is used to determine the monitor setpoint (cpm) from a calibration curve similar to Figure 1.0-1.

NOTE: The setpoint contains a factor of conservatism, even if the calculated maximum waste tank flow rate is attainable, since the calculated rate contains the safety factor margin, waste tank ef fluer,t flow rate margin, and the dilution flow rate margin. In practice, the actual waste tank efflueit flow rate normally is many times less than the calculated tank flow rate, thus providing an additional conservatism during release.

1.0-5 Draft !

GRAND GULF, UNIT 1 EFMI5719.48/SNLICFLR

Figure 1.0-1 Example Calibrat. ion Curve for Liquid Effluent Mo_ni_t_o_r 10-2

, s

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~-

i .- , - - - - .. r ,. ..:; . .

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1 if# [. l?ME 4 4'

a. N'-M._M.' -- . =La. ~. 3 --* C:=. . -,En.5. ,*nr' '.- ;.75@31 g

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.m u.: m.=.--. . ._.g.,. m_._. '_-a eos, m . .__, . --- w.m v emn __

s e: r.- w.1 __.w_.in u :2 u w----.x -

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1 =

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10-8:

10 1

10 2

10 3

10' 105 10 1

Count Rate (Counts per Minute) 1 1.0-6 Draft 1

1 GRAND GULF, UNIT 1 l EFMT5719.48/SNLICFLR

k. .

1.2 Dng_ Calc.ulatio_ns for Liauid Effluents 1.2.1 Maximum Exposed Individual _Model The dose contribution to the maximum exposed individual from all radionuclides identified .in waste tank liquid effluents released to unrestricted areas is calculated for the purpose of implementing Appendix A Requirements 1.11.1.f, 4.11.1.2, 4.11.1.3.1, and 6.9.1.9 using the following expression:

m (1)

DTau

iI E^iTau E At t C fg Fg ] (millirem) (8) t=1 where:

AiTau = Site-related ingestion dose commitment factor for radionuclide 1, in millirem /hr per pCi/ml.

=K n Up BF DF 4 4 Atg= length of the time period over which C gg and Fg are averaged for all waste tank liquid releases, in hours.

.C$g = average concentration of radionuclide i observed in the undiluted waste tank liquid ef fluent during tioe period at g from any liquid release from the -

waste tank, in pCi/ml. Concentrations are datermined primarily from a gamma isotopic analysis of toe waste tant liquid effluent sample. For Sr-89, Sr-90, H-3, the last measured value from the most recent monthly and. quarterly composite samples will be used in the dose calculation. Note: LLD 1 values are not used in dose calculations.

1.0-7 Draft I

GRAND GULF, UNIT 1-EFMT5719.48/SNL1CFLR.

F, = near field average dilution factor for Cit during any liquid effluent release. Defined as the ratio of the average undiluted liquid waste flow during release to the product of the average flow from the site discharge structure to unrestricted receiving waters times the applicable factor of 2(5) ,

= Lynage___undilyled liauid wule flow _

average flow from site discharge x 2 5

Kg = units conversion factor 1.14 x 10 6 3

= 10 pLi x 10 al + 8766 hr pCi kg yr Up = adult fish consumption (21 kg/yr) O) ,

BF$ = Bioaccumulation factor for each nuclide, i, in fish, in pCi/kg per pCi/1 from Table 1.2-1 (taken from Reference 3, Table A-1).

DFj = Dose conversion factor for each nuclide, i, for adults in preselected organ, Tau, in mrem /pCi, from Table 1.2-2 (taken from Reference 3, Table E-11).

Calculated values of A iTau f r radionuclides which might be observed in liquid effluents are given in Table 1.2-3.

1.2.2 D_o s e_ P r_oj ec ti o_n Doses from liquid offluents to UNRESTRICTED AREAS are projected at least every 31 days as required by Appendix A Requirement 4.11.1.3.1. These projections are made by averaging the doses (DTau) from previous operating history (normally the previous six months) which is indicative of expected future operations.

1.0-8 Draft GRAND GULF, UNIT 1 EFMT5719.48/SNLICFLR -- --

IABLE_l,1-1 _

B10ACC.UMUL&110N_fAC10R1, (BF )

(pCi/kg per pCi/ liter)* g ERESUWAIER ELEMENI EISU INVERIEBRAIE H 9.0E-01 9.0E-01 C 4.6E*03 9.lE403 NA 1.0E602 2.0E+02 P 1.0E405 2.0E+04 CR 2.0EiO2 2.0E'03 MN 4.0E*02 9,0E+04 FE 1.0E402 3.2E+03 CO 5.0E401 2.0E4 02 NI 1.0E402 1.0E402 CU 5.0E+01 4.0E402 ZN 2.0E403 1.0E+04 BR 4.2E402 3.3E402 RB 2.0E403 1.0E+03 SR 3.0E+01 1.0E+02 Y 2.5E401 1.0E403 ZR 3.3E400 6.7E400 NB 3.0E+04 1.0E+02 MO 1.0E401 1.0E+01 TC 1.5E+01 5.0E+00 RU 1.CE401 3.0E+02 RH 1.0E+01 3.0E402 SB 1.0E400 1.0E+01 TE 4.0E+02 6.lE403 I 1.5E*01 5.0E+00 CS 2.0E*03 1.0E*03 BA 4.0E+00 2.0E*02 LA 2.5E+01 1.0E+03 CE 1.0EiOO 1.0E+03 PR 2.5E601 1.0E403 ND 2.5E401 1.0Et03 W l.2EiO3 1.0EiOI NP 1.0E401 4.0E402

Values in Table 1.2-1 are taken from Reference 3, Table A-1, except for SB which was taken from Reference 2, Table A-8.

1.0-9 Draft GRAND GULF, UNIT 1 EfMI5719.48/SNLICFLR

IABl.Ll a 2 IMGE1110R_DOSLCOHVERSJON FACTORS FOR_AQVilS, (DFg )

(mrem per pCi ingested)

Page 1 of 3 NUCLIDE BONE LIVER T. BODY THYR 01D K10NEY LUNG ul-LLI H 3 NO DATA 1.05E-07 1.05E-07 1.05E-07 1.05E-07 1.05E-07 1.05E.07 C 14 2.84E-06 5.68E-07 5.68E-07 5.68E-07 5.68E-07 5.68E-07 5.68E.07 NA 24 1.70E-06 1.70E-06 1.70E-06 1.70E-06 1.70E-06 1.70E-06 1.70E-06 P .32 1.93E-04 1.20E-05 7.46E-06 NO DATA NO DATA NO DATA 2.17E-05 CR 51 NO DATA NO DATA 2.66E-09 1.59E-09 5.86E-10 3.53E-09 6.69E-07 MN 54 NO DATA 4.57E-06 8.72E-07 NO DATA 1.36E.06 NO DATA 1.40E-05 MN 56 NO DATA 1.15E-07 2.04E-08 NO DATA 1.46E-07 NO DATA 3.67E-06 FE 55 2.75E-06 1.90E-06 4.43E-07 NO DATA NO DATA 1.06E-06 1.09E-06 FE 59 4.34E-06 1.02E-05 3.91E-06 NO DATA NO DATA 2.85E-06 3.40E-05 CO 58 NO DATA 7.45E-07 -1,67E-06 NO DATA NO DATA NO DATA 1.51E-05 CO 60 NO DATA 2.14E-06 4.72E-06 NO DATA NO DATA NO DATA 4.02E-05 NI 63 1.30E-04 9.01E-06 4.36E-06 NO DATA NO DATA NO DATA 1.88E-06 NI- 65 5.28E-07 6.86E-08 3.13E-08 NO DATA NO DATA NO DATA 1.74E-06 CU 64 NO DATA 8.33E-08 3.91E-08 NO DATA 2.10E-07 NO DATA 7.10E-06 ZN 65 4.84E-06 1.54E-05 6.96E-06 NO DATA 1.03E-05 NO DATA 9.70E-06 ZN 69 1.03E-08 1.97E-08 1.37E-09 NO DATA 1.28E-08 NO DATA 2.96E-09 BR 83 NO-DATA NO DATA 4.02E-08 NO DATA NO DATA NO DATA 5.75E-08 BR 84 NO DATA NO DATA 5.21E-08 NO DATA NO DATA NO DATA 4.09E-13

-BR 85 Nbbkhk Nbbkhk h 4h b9 Nbbkkk bbbkhk Nbbkhk Lkh5h4 RB 86 NO DATA 2.11E-05 9.83E NO DATA -NO DATA NO DATA 4.16E-06 RB 88 NO DATA 6.05E-08 3.21E-08 NO DATA NO DATA NO DATA 8.36E-19 RB 89 UO DATA 4.01E-08 2.82E-08 NO DATA NO DATA NO DATA 2.33E-21 SR -89 3.08E-04 NO DATA- 8.84E-06 'O DATA NO DATA NO DATA 4.94E-05 SR 90 7.58E-03 NO DATA 1.86E-03 NO DATA NO DATA NO DATA 2.19E-04 bR 9 b 6hh bb bb bk k hhhhbh bbbkhk bbbkhk bbbkhk hhbhbb SR 92 2.15E-06 NO DATA 9.30E-08 NO DATA NO DATA NO DATA 4.26E-05 Y 90 9.62E-09 NO DATA 2.58E-10 NO DATA NO DATA NO DATA 1.02E-04 Y 9iM 9 bhh kk Nb bkkk bShhih Nbbkhk Nbbkkk Nbbkkk h6hhkb Y 91 1.4]E-07 NO DATA 3.77E-09 NO DATA NO DATA NO DATA 7.76E-05 Y 92 8.45E-10 NO DATA 2.47E-11 NO DATA NO DATA NO DATA 1.48E-05

Values taken from Reference 3, Table E-11.

1.0-10 Draft GRAND GULF, UNIT 1 EFMT5719.48/SNLICFLR

IAD1LL2-P Enn.tinuedl INGES110LD01E_t0gEnION FAC1QRLf_0LADD11S, (DF )

4 (mrem per pCi ingested)

Page 2 of 3 NUCLIDE BONE LIVER T BODY THYROID KIDNEY LUNG GI-LL1 Y 93 2. 68E-09 NO DATA 7.40E.11 NO DATA NO DATA NO DATA 8.50E-05 ZR 95 3.04E-08 9.75E 09 6.60E-09 NO DATA 1.53E-08 NO DATA 3.09E-05 ZR 97 1.68E-09 3.39E-10 1.55E-10 NO DATA 5.12E-10 NO DATA -1.05E-04 NB 95 6.22E-09 3.46E-09 1.86E-09 NO DATA 3.42E-09 NO DATA 2.10E-05 MO 99 NO DATA 4.31E.06 8.20E-07 !!O DATA 9.76E-06 NO DATA 9.99E-06 TC 99M 2.47E-10 6.98E.10 8.89E-09 NO DATA 1.06E-08 3.42E-10 4.13E-07 TC101 2.54E-10 3.66E-10 3.59E-09 NO-DATA 6.59E-09 1.87E-10 1.10E-21 RU103 1.85E-07 NO DATA- 7.97E-08 NO DATA 7.06E-07 NO DATA 2.16E-05 RU105 1.54E-08 NO DATA 6.08E-09 NO DATA 1.99E-07 NO DATA 9.42E-66 RU106 2.75E-06 NO DATA 3.48E-07 NO DATA 5.31E-06 NO DATA 1.78E-04 AG110M 1.60E-07 1.48E-07 8.79E-08 NO DATA 2.91E-07 NO DATA 6.04E-05 SB124 2.80E-06 5.29E-08 1.11E-06 6.79E-09 0.0 2.18E-06 7.95E-05 5B1254D- 1.79E-06 2.00E-03 4.26E-07 1.82E-09 0.0 1.38E-06 1.97E-05 SB126 1.15E-06 2.34E-08 4.15E-07 7.04E-09 0.0 7.05E-07 9. 40E-05 SB127 2.58E-07 5.65E-09 9.90E-08 3.10E-09 0.0 1.53E-07 5.90E-05 TE125M 2.68E-06 9.71E-07 3.59E-07 8.06E-07 1.09E-05 NO DATA 1.07E-05

~lE127M 6.77E-06 -2.42E-06 8.25E-07 1.73E-06 2.75E-05 NO DATA 2.27E-05 TE127 1.10E-07 3.95E-08 2.38E-08 8.15E 4.48E-07 NO DATA 8.68E-06 TE129M- 1.15E-05 4.29E-06 1.82E-06 3.95E-06 4.80E-05 NO DATA 5.79E-05 TE129 3.14E-08 1.18E-08 7.65E-09 2.41E-08 1.32E-07 NO DATA 2.37E TE131M- 1.73E-06 8.46E-07 7.05E-07 1.34E-06 8.57E-06 NO DATA -8.40E.05 TE131 1.97E-08 8.23E-09 6.22E-09 1.62E 8.63E-08 NO DATA 2.79E-09 TE132 2.52E-06 1,63E-06 1.53E-06 1.80E-06 1.57E-05 NO DATA 7.71E.05 1 130 7.56E-07 2.23E-06 8.80E-07 1.89E-04 3.48E-06 NO DATA 1.92E-06 1 131 4.16E-06 5.95E-06 3.41E-06 1.95E-03 1,02E-05 NO DATA 1.57E-06 I 132 2.03E-07 5.43E-07 1.90E-07 1.90E-05 8.65E-07 NO DATA 1.02E-07 1.133 1.42E-06 2.47E-06 7.53E-07 3.63E-04 4.31E-06 NO DATA 2.22E-06 I 134 1.06E-07 2.88E-07 1,03E-07 4.99E-06 4. 58E-07 NO DATA 2.51E-10

~

1 135 4.43E-07 1.16E-06 4.28E-07 7.65E-05 1.86E-06 NO DATA 1.31E-06 CS134 6.22E-05 1.48E-04 1.21E-04 NO DATA 4.79E-05 1.59E-05 2.59E-06 CS136 6.51E-06 2.57E-05 1.85E-05 NO DATA 1.43E-05 1.96E-06 2.92E-06

Values taken from Reference 3. Table E-11, except for SB values which were taken from Reference 8,' Table 4.

1.0-11 Draft GRAND GULF, UNIT 1 EFMT5719.48/SNLICFLR

IABLLLhL(Conunndl INGES110lLDOSE_ColiVERS10N FAC10RSl0fLADHLIS, (DFg )

(mrem per pCi ingested)

Page 3 of 3 NUCLIDE BONE LIVER T. BODY THYROID KIDNEY LUNG GI-LLI C5137 7.97E-05 1.09E-04 7.14E-05 NO DATA 3.70E-05 1.23E-05 2.llE-06 CS138 5.52E-08 1.09E-07 5.40E-08 NO DATA 8.01E-08 7.91E-09 4.65E-13 BA139 9.70E-08 6.91E-ll 2.84E-09 NO DATA 6.46E-11 3.92E-11 1.72E-07 BA140 2.03E-05 2.55E-08 1.33E-06 NO DATA 8.67E-09 1.46E-08 4.18E-05 BA141 4.71E-08 3.56E-Il 1.59E-09 NO DATA 3.31E-11 2.02E-Il 2.22E-17 BA142 2.13E-08 2,19E-11 1.34E-09 NO DATA 1.85E-ll 1.24E-11 3.00E-26 LA140 2.50E-09 1.26E-09 3.33E-10 NO DATA NO DATA NO DATA 9.25E-05 LA142 1.28E-10 5.82E-11 1.45E-Il NO DATA NO DATA NO DATA 4.25E-07 CE141 9.36E-09 6.33E-09 7.18E-10 NO DATA 2.94E-09 NO DATA 2.42E-05 CE143 1.65E-09 1.2?E-06 1.35E-10 NO DATA 5.37E-10 NO DATA 4.56E-05 CE144 4.88E-07 2.04E-07 2.62E-08 NO DA1A 1.21E-07 NO DATA 1.65E-04 PR143 9.20E-09 3.69E-09 4.56E-10 NO DATA 2.13E-09 NO DATA 4.03E-05 PR144 3.01E-Il 1.25E-11 1.53E-12 NO DATA 7.05E-12 NO DATA 4.33E-18 ND147 6.29E-09 7.27E-09 4.35E-10 NO DATA 4.25E-09 NO DATA 3.49E-05 W 187 1.03E-07 8.61E-08 3.01E-08 NO DATA NO DATA NO DATA 2.82E-05 NP239 1.19E-09 1.17E-10 6.45E-11 NO DATA 3.65E-10 NO DATA 2.40E-05

Values taken from Reference 3, Table E-11 1.0-12 Draft GRAND GULF, UNIT 1 EFMI5719.48/SNLICFLR

i i

i IbELLL-3 I SITE RELATED INGESTION DOSE COMMITMENT FACTOR, (Am u)

(mrem /hrperpC1/ml)*

Page 1 of 2 NUCLIDE BONE LIVER T. BODY THYROID K1DNEY LUNG GI-LLI H-3 0.00E400 2.26E-01 2.26E-01 2.26E-01 2.26E-01 2.26E-01 2.26E-01 ;

C-14 3.13E+04 6.26E+03 6.26E403 6.26E403 6.26E+03 6.26E403 6.26E+03 !

Na-24 4.07E+02 4.07E402 4.07E402 4.07E402 4.07E402 4.07E+02 4.07E+02

P 4.62E+07 -2.87E406 1.79E406 0.00E400 0.00E+00 0.00E400 5.19E+06 4 Cr-51 0.00E400 0.00E400 1.27E+00 7.61E.01 2.81E-01 1.69E400 3.20E402 :

Mn'54 0.00E400 4.38E403 8.35E+02 0.00E+00 1,30E+03 0.00E+00 1.34E+04 .

Mn-E5 0.00E+00 1.10E+02 1.95E401 0.00E400 1.40E402 0.00E400 3.51E403 !

Fe-55 6.58E402 -4.55E402 1.06E402 0.00E400 0.00E+00 2.54E402 2.61E402 :

Fe-59 1.04E+03 2.44E+03 9.36E+02 0.00E400 0.00E+00 6.82E402 8.14E+03 Co-58 0.00E400 8.92E4 01 2.00E402 0.00E+00 0.00E400 0.00E400 1.81E+03 l Co 0.00E+00 2-.56E+02 5. 65E4 02 0.00E+00 0.00E+00 0.00E+00 4.81E+03 )

Ni-63 3.11E404 2.16E+03 1.04E+03 0.00E+00 0.00E+00 0.00E+00 4.50E+02 Ni-65 1.26E402. -1.64E+01 7.49E400 0.00E400 0.00E400 0.00E400 4.17E+02 l Cu-64 0.00E+00 9.97E+00 4.68E400 0.00E+00 2.51E401 0.00E+00 8.50E402 Zn-65 2.32E404 7.37E+04 3. 33E404 0.00E400 4.93E+04 0.00E+00 4,64E+04 l Zn-69 f.93E+01 9.43E4 01 6.56E+00 0.00E+00 6.13E+ 01 0.00E+00 1.42E+01 i Br-83 0.00E400 0.00E+00 4.04E+01 0.00F+00 0.00E+00 0.00E+00 5.82E+01 ,

Br-84 0,00E+00 0.00E+00 5.24E+01 0.00E+00 0.00E400 0.00E+00 4.11E-04 ,

Br-85 0.00E+00 0.00E400 2.15E+00 0.00E+00 0. 00E4 00 0.00E+00 1.01E-15 !

Rb-86 0.00E400 1.01E+05 4.71E404 0.00E+00 0.00E+00 0.00E+00 1.99E+04 .

Rb-88 0.00E+00 2.90E+02 1.54E+02 0.00E+00 0.00E+00 0.00E+00 - 4.00E-09 Rb-89 9,00E+00 1.92E+02 1.35E+02 0.00E+00 0.00E400 0.00E4 00 1.12E-11 i Sr-89 2.21E404 0.00E+00 6,35E+02 0.00E400 0.00E+00 0.00E+00 3.56E+03 l Sr-90 5.44E+05 0.00E400 1.34E+05 0.00E+00 0.00E400 0.00E+00 1.57E+04 Sr-91 4.07E+02 0.00E400 1.64E401 0.00Et00 -0.00E400 0.00E400 l'.94E+03 ,

Sr-92~ 1.54E+02 0.00E+00- 6.68E+00 0.00E+00 0.00E+00 0.00E+00- 3.06E+03 ,

Y-90 5.76E-01 0.00E400' 1.54E-02 0.00E+00 0.00E+00 0.00E+00 6.10E+03 r Y-91m 5.44E-03 0.00E+00 2.11E-04 0.00E+00 0.00E+00 0.00E+00 1.60E-02 Y-91 8.44E400- 0.00E400 2.26E-01 0.00E+00 0.00E+00 0.00E+00 4.64E+03 }

Y-92 5.06E-02 0.00E400 1.48E-03 ~0.00Et00 0.00E+00 0.00E+00 8.86E+02 ,

Y-93 1.60E-01 0.00E400 4. 43 E- 03 0.00E400- 0.00E+00 0.00E400 5.09E+03 '

Z r-95 2.40E-01 .7.70E-02 5.21E-02 0.00E+00 1.21E-01 0.00E+00 2.44E+02 Zr-97 1.33E-02 2.08E-03 li22E-03 0.00E400- 4.04E-03 0.00E+00 8.30E+02 j Nb-95 4.47E402 2.4 8E402 - 1.34E402 0.00E+00 2.46E+02 0.00E+00 1.51E+06 :

I Mo-99 0.00E+00 1.C 3E402 1.96E+01 0.00E+00 2.34E402 0.00E400 2.39E+02 Tc-99m 8.87E-03 2.!1E-02 3.19E-01 0.00E+00 3.81E-01 1.23E-02 1,48E+01 i l Tc-101- 9.12E-03 1.31E-02 1.29E-01 0.00E+00 2.37E-01 6.72E-03 3.95E-14 ;

Ru-103 4.43E+00- 0.00E400 1.91E+00 0.00E+00 1.69E+01 0.00E+00 5.17E+02 +

RL-105 3.69E-01 0.00E+00- 1.46E-01 0.00E+00 4.76E+00 0.00E+00 2.26E+02

Calculated from Equation 8. i i

1.0-13 9raf !

GRAND GULF, UNIT 1 ~

^

l EFMT5719.48/SNLICFLR

JAD1LL2-3 (Continnd)

SJTE RELATEDjNGESTI,0N_00SE30MllMENTlACT.OR, (A (mrem /hr per pCi/ml)* iTau)

Page 2 of 2 NUCLIDE BONE LIVER T. BODY THYR 010 KIONEY LUNG GI-LLI Ru-106- 6.58E+01 0.00E+00 8.33E+00 0.00E+00 1.27E402 0.00E+00 4.26E+03 Ag-110m 8.81E 8.15E-01 4.84E-01 0.00E+00 -1. 60E4 00_ _0.00E+00 3.30E+02 Sb-124 6.70E+00 1.27E-01 2.66E+00 1. 63 E-02 0.00E+00 5.22E+00 1.90E+02 Sb-125 4.29E+00~ 4.79E-02 1.02E+00 4 . 36E-03 0.00E400 3.30E+00 4.72E401 Sb-126 2.75E400 5.60E-02 9.94E-01 1.69E-02 0.00E400 1.69E+00 2.25E402 Sb-127 6.18E-01 1.35E-02 2.37E-01 7.42E-03 0.00E400 3.66E-01 1.41E+02 Te 125m 2.57E+03 9.30E+02 3.44E+02 7.72E+02 1.04E404 0.00E400 1.02E&O4 Te-127m 6. 48E4 03 2.32E+03 7.90E-02 1.66E403 2.63E+04 0.00E400 2.17E404 Te-127 1.05E+02 3.78E401 2.28E401 7.80E+01 4.29E402 0.00E400 8.31E+03 Te-129m 1.10E4 04 4.14E+03 1. 74 E4 03 3.78E+03 4.60E404 0.00E+00 5. 54 E4 04

-Te-129 3.01E+01 - 1.13E+01 7.33E+00 2.31E+01 1.26E+02 0.00E400 2.27E401 Te-131m 1.66E403 - 8.10E+02 6.75E402 1.28E+03 8.21E+03 0.00E+00 8.04E+04 Te-131 1.89E+01 7.88E+00 5.96E+00 1.55E+01 8.26E401 0.00E+00 2.67E+00 Te-132 2.41E+03 1.56E+03- 1.47E+03 1.72E+03 1.50E404 0.00E+00 7.38E+04

'30 2.71E401 8.01E+01 3.16E+01 6.79E+03 1.25E+02 0.00E+00 6.89E+01 2 .31 1.49E402 2.14E+02 1.22E+02 7.00E+04 3.66E402- 0.00E+00 5.64E+01 ',

1-132 7.29E+00 . 1.95E+01 6.82E400 6.82E+02 3.11E401 0.00E400 3.66E+00 I-133 5.10E401 8.87E401 2.70E+01 1.30E+04 1.55E+02 0.00E400 7.97E401 I-134 3.81E+00 1.03E+01 3.70E+00 1.79E+02 1.64E+01 0.00E+00 9.01E-03 1-135 1.59E+01 4.17E+01 1.54E+01 2.75E+03 6.68E+01 0.00E+00 4.70E+01 Cs-134 2.98E+05 7.09E+05 5.79E+05 0.00E400 2.29E+05 7.61E+04 1.24E+04 .

.C s- 136' 3.12E404 1.23E405 8.86E404 0.00E400 6.85E404 9.38E+03 1.40E+04 Cs-137- 3.82E405 5.22E+05- 3.42E405- 0.00E+00 1.77E405 - 5.89E404 1.01E+04 *

, Cs-138 2.64E+02 5.22E+02 2.59E402 0.00E+00 3.84E402 3.79E401 2.23E-03 Ba-139 9.29E-01-- 6.62E-04 2.72E-02 0. 00E400 6.19E-04 3.75E-04 1.65E+00 :

Ba-140 1.94E+02 2.44E-01 1.27E401 0.00E+00 8.30E-02 1.40E-01 4.00E+02 I Ba-141 4.51E 3.41E-04 1. 52E- 02 0.00E+00 3.17E-04 1.93E-04 '2.13E-10 i Da-142 2.04E-01 2.10E-04 1.28E-02 0.00E+00- 1.77E-04 1.19E-04 2.87E-19 ,'

La-140 1.50E-01 7.54E-02 1.99E 0. 00E+ 00 0.00E+00 0.00E+00 5.54E+03 La-142 7.66E-03 3.48E-03 8.68E-04 0.00Et00 0. 00E+ 00 0.00E+00 2.54E+01 Ce-141 2.24E-02 1.52E-02 1.72E-03 0.00E400 7.04E-03 0.00E400 5.79E401 Ce-143 -3.95E 2.92E400 3.23E-04 0.00E400 1.29E-03 0.00E+00 1.09E+02 Ce-144 1.175+00 4.88E-01 6.27E-02 0.00E400 2.90E-01 0.00E+00 3.95E+02 Pr-143 5.51E-01 2. 21 E-01 2.73E-02 0.00E+00 1.27E-01' O.00E+00 2.41E+03 Pr-144 1.80E-03 7.48E-04 9.16E-05 0.00E+00 4.22E-04 0.00E+00 2.59E-10 ;

Nd-147_ 3.76E-01 4.35E-01 2.60E-02 0.00E400 2.54E-01 0.00E+00 '2.09E+03 l W-187 2.96E+02 2.47E+02 8.65E+01 0.00E400 0.00E*00 0.00E+00 8.10E+04 l Np-239 2.85E-02 2.80E-03 1.54E-03 0.00E+00 8. 74 E-03 0.00E+00 5.75E+02 l'

l -* Calculated from Equation 8.

1.0-14 Draft :

l GRAND GULF, UNIT 1 EFMT5719.48/SNLICFLR i

, - - - - . . - ,-n.,,--n, . , , -

-- , ,, e , e , , - - - .

1.3 ' Liquid _RadtuteJ10AlmRRLSSilem The essential components of the liquid radwaste treatment system are indicated on the following page by an asterisk _(*).

HQlES for Figute_LJ-1 (1) The essential components outlined on the following page are those necessary to collect, process and ~ sample liquid radwaste prior to discharge to the environment.

(2) Only one of the following is required in order to process liquid waste.

]

a. Equipment drain filter

b. Floor drain-filter

c. Equipment drain domineralizer

d. Floor drain demineralizer (3) - One of the Waste Surge Tanks may be used to replace the Floor Drain Waste Collection Tank.

l l

1.0-15 Rev. 8 - 08/86 GRAND GULF, UNIT 1 l1 EFMT5719.48/SNLICFLR-

-Ficure 1.3-1 '

Liouid Radvaste Treatment System I macTm ; ; _ = -

jL I Ik I f

"" f b

- eser. as cesemarE 1 Q - Tasst I sementI2st stonneE Tafet 1I I

m et n a m uns u 4L cuatrie

s. encuaronano Tenet A. CsNTAlsterf 8 WM EM

s. nrumrsum - emenert museu - "c8*'" "runse , -

mN -.d j (q

e. Tuerm Sue - umsn M IZER - Um c a l m:TIst Taget j( FRM "

p D. AaenasTE RDe

2. jf 3.

Depenaten DISTILLAM OpenesaTE nunnassmas11mm ADM jf -

j (

4. lestaf SEtaser FILTet CaslE TW eLID IIASTE -

3 m

' ' w

)h -

um amm msm -

nme sanas a 1 7 1 r ,

s. FLeon anaru essis

" F TER - 258 Y I U

een a stTime Taps .

C. TWWINE Ras D. httRtaffE R ag SISTRATE ft MI f4stITY angM M SIL3s taasm J L DEMital maATE IES D8 fE m p e gniles SEup eintles i a L

'I fESIN NTIst OWGCsLB E tus a eriles 7 sEL1pTIas "'gyapetATatl TAset Im mtaLI2ER Taset j (

MtmILLaaEms maalt T3 WLID m4STE nrem i asone u pescatsmans C cse e m nastt -

Tasst Garm inun STATitse - sleesse DIN MISSISSIPPI RIVER 1.0-16 Draft GRAND GULF, UNIT I EFMT5719.48/5NLICFLR

2.0 GA K0US EFFluENL$.

'2.1- Gaseous _Ef_ fluent _MonitoL Setpoints 2.1.1 _Co n_t i n uo u s_Ve n_t i l a t i o n Mo n i_t o r s For the purpose of implementation of Appendix-A Requirement 3.3.7.12, the alarm setpoint level for continuous ventilation noble gas monitors will be calculated as follows:

Sy = Count rate (cpm) above background of vent noble gas monitor at the alarm setroint level PF x gR x0 7g

= the lesser of or "5 55 where-PF = product of allocation factor (AF) and safety factor (SF), normally set at 0.1 AF = allocation factor allowing for a total of four normal ef fluent release points, normally set at 0.25 SF n safety factor allowing for cumulative uncertainties- i of measurements, normally set at 0.4

-D1B = Dose re,te limit to the total body of an individual at the SITE BOUNDARY or at UNRESTRICTED AREAS inside the SITE BOUNDARY required to limit dose to 500 mrem L in one year

= 500 mrem /yr D = Dose rate limit to the skin of the body of an 33 individual at the SITE BOUNDARY or at UNRESTRICTED AREAS inside the SITE BOUNDARY required to limit--dose i to 3000 mrem in one year i = 3000 mrem /yr l

l. 2.0-1 DrafL l

GRAND GULF, UNIT 1

-EFMT5719.48/SNLICFLR

Rt = count rate (cpm) per mrem /yr to the total body

= C + [ X/Q IK $ Q'j]

i where:

C = count rate (cpm) above background of the vent monitor correspoading to grab sample radionuclide concentrations X/Q = highest sector annual average atmospheric dispersion at the SITE BOUNDARY or at UNRESTRICTED AREAS inside the SITE BOUNDARY

-6* 3

= A d3WQ sec/m in the WhW sector K4 = total . body dose factor due to gamma emissions from each noble gas radionuclide 1 (mrem /yr per pCi/m3) from Table 2.1-1 Q'4 = rate of release of noble gas radionuclide 1 (pCi/sec) from the release point-R, = count rate (cpm) per mrem /yr to the skin

=C+X/Q[{(Lg + 1.1 M g) Q'4]

Lg = skin dose factor due to beta emissions from isotope 1 3

(mrem /yr per pCi/m ) from Table 2.1-1 1.1 = mrem skin dose per mrad air dose My n-air dose factor due to gamma emissions from isotope 1 (mrad /yr per pCi/m3 ) from Table 2.1-1 The highest-annual average X/Q for the GGNS SITE BOUNDARY or UNRESTRICTED AREAS inside the Si1E BOUNDARY is llamilton Lake (WNW, 0 75 miles). This value is taken from the Grand Gulf Nuclear Station Final Environmental Report, Table 6.1.28.

2.0-2 Draft GRAND GULF, UNIT 1 EFMT5719.48/SNLICFLR _ ________ _____ _________

2.1.2 TEXT DELELEQ .

9

+

i r

e i

I t

5 t

L I

i i

2.0-3 Rev. 2 - 05/84 l i

GRAND GULF, UNIT 1

_. EFMT5719.48/SNLICFLR

140lL5_.Lorlectiert2,lt1

1) The calculated setpoint vtloes will determine *.he allowable bounds for the actual setpoint adjustments. That is, setpoint adjustments are not required to i nerformed if the existing setpoint level corresponos to a count rat a- is less the, or equal to 4 25% of the calculated value. If radionuclides are not detecter' in the grab sample, then the previously calculated *tpoint may remain as the valid setpoint.

2) A *no re < ,4 ,orvative setpoint may be calculated u-ing the conservative Kr 89 total body Jose factor. This method may ne ut 4 shen there are no valid isosopics available, The conservative setroint will be calculated as follows:

Sy = count rate (cpm) aoove background of vent noble gas monitor at the alarm setpoint leval*

= PFi xDTB

Rt "

where:

PF = product of allocation f actor ( AF) and saf ety actor (SF'), normally set at 0.2 Af = allocation factor allowing for a total of four normal effluent release points, normally set at 0.25 SF' = safety factor allowing for cumulative uncertainties of measurements, normally set at 0.8 R " = conservative count rate per mrem /yr t o the total body (Xe-133 t

detection, Kr-89 dose)

= L3J3E-3LM03

~

X[Q(X)(V)(K)

The setpoint calculation based on a Kr-89 skin dose is not required because ae setpcint based on a Kr-89 total body dose will always be more conservative.

2.0-4 Draft GRAND GULF, UNIT 1 EFM15719.48/SNllEFLR 1

t where:

X = Xe-133 volume efficiency factor of the detector system in I

pCi/cc/ cpm as determ!ned by the primary calibration * !

t Vn maximum designed ventilation flow rate in cubic feet per minute j i

(cfm) !

i 3.53E-5 = conversion factor, ft3 per cc-5 l

t 60 = conversion f actor, seconds per minute !

K = total body dose factor for Kr-89, the most restrictive isotope, from Table 2.1-1 {

= 1. f>6E 4 04 mrem /yr per pC1/m'3

~

l s

4 Other variables as defined in Section 2.1.1 1

1 1

t i

f i

i i

i The instrument calibration procedures will include checks to ensure that f the detector efficiency does not vary by more than i 25%. :

i i

2.0-5 Draft {

GRAND GULF, UNIT 1 !

EFMT5719.48/SNLICFLR- ;

- . ~ . , . _ . . . _ . . _

_ _ _ . _ . __ .._.__ _ __ . _ _ _ _ m IADLE l l:1 001LEAC10RSl0fLLXt01VRL10_A_5 EBL- 1EIMllLC LOVD_0fJiOBLLGAS LS Huc.11de Y:Boh* *(Kli- D:1Lin**(Lli EMr* W11 B:Ait*Wll Kr-85m 1.17E4 03"

1.46E403 1.23E403 1.97E403 Kr-85 1.61E401 1.34E403 1.72E401 1.95E403 Kr-87 5.92E403 9.73E403 6.17E403 1.03E404 Kr-88 1.47E404 2.37E403 1.52E404 2.93E403 Kr-89 1.66E404 1.01E404 1.73E*04 1.06E404 Kr-90 1.56E404 7.29E403 1.63E+04 7.83E403 Xe-131m -9.15E401 4.76E402 1.56E402 1.11E403 Xe-133m 2.51E402 9.94E402- 3.27E402 1,48E403 Xe-133 2.94E402- 3.06E402 3.53E402 1.05E403 Xc-135m 3.12E403 7.11E402 3.36E403 7.39E402 Xo-135 1.8]E403 1.86E403 1.92E+03 2.46E403 Xe-137 1,42E*03 1. 2.? E

04 1.51E403 1.27E404 Xe-138 8.83E403 4.13E403 9. 21 E4 03 4.75E493 1

Ar 41 S 84E403

~

2.69E403 0.30E403 3.28E403 Values taken from Reference 3, Table B-1 i mrad - m' iifi ~ ~~iF~ !

i mrem .m'_ !

pCi - ) i

"* 1.17E4 03 = 1.17 x 10' i

\^ !

l b 2.0-6 Draft GRAND Gulr. UNIT 1 EFMI5719.48/SNLIC.'LR -;

Id . _ . _ _ _ _ .:. w._ . . . . .__ _ . _ - . . _ _ . _ . _ . _ _ _ _ _ . _ _ _ . . _ _ _ _ _ _ _ . _ . . . _ . _ . . . _ . . _ .

,_ _ . ., _.. _ .. _ . .i.. i

I 2.2 GaletuLELLintLLQgielakulAlions 2.2.1 Unrestricted Area B.oundary_ Dose.

a. For the purpose-of implementation of Appendix A Requirement 3.ll.2.1.a. the dose at the SITE BOUNDARY or at UNRESTRICIED AREAS within the Si1E BOUNDARY due to noble gases shall be calculated as follows:

l)tb a average total body dose rate in current year (mrem /yr)

=

I/6 I K, Q'i D, = overage skin dose rate in current year (mrem /yr)

=

X/Q I (L 4 +

1.lMg) Q'4

b. Organ doses due to tritium, 1-131, 1-133 and all radioactive materials in pirticulate form, with half-lives greater than eight days will be calculated for the purpose of implementation of Appendix A Requirement 3.11.2.1.b as follows:

Do = average organ dose rate in current year (mrem /yr)

= IW P4 UI'j i

where:

2.0-7 Draft GRAND GULF, UNIT 1 '

EFMT5719.48/SNLICFLR

W = controlling sector annual average atmospheric dispersion at the SITE BOUNDARY or UNRES1RICTED AREAS inside the S11E BOUNDARY for the appropriate pathway 5/Q = 4.537 x 10-6* 3,cj,3 for inhalation and all tritium pathways in the WNW sector or E/6 - 1.301 x 10-8" g -2 for food and grauld plane pathways in the SSE secto-p4 = the total dose parameter for radionuclide i, 3

(mrem /yr per pCi/m ) for inhalation and all tritium pathways and (m2 . mrem /yr per pCi/sec) for food and ground plane pathways, from Tables 2.2-la-b Q'4 = rate of release of noble gas radionuclide i (pCi/sec) from the release point The highest annual average X/Q for the GGNS SITE BOUNDARY or UNRESTRICIED AREAS insido the S'1E BOUNDARY is Hamilton Lake (WNW, 0.75 miles). This value is taken.from the Grand Gulf Nuclear Station Fir.a1 Environmental Report, Tablo 6.1.28

" Value taken from Reference 4, Table 6.1.26 2.0-8 Draft GRAND GULF, UNIT-1 EFM15719.48/SNLICFLR

{=averagereleaserateofisotopeioftritium, 1-131, 1-133 or other radionuclide in particulate form, with' half-lives greater than eight (8) cays in the current year (pCi/sec) 2.2.2 Unrestricted Area _ Dose to_. Individual.

a. For the purpose of implementat'on of Appendix A Requirement 3.11.F.?, the air doso at the SITE BOUNDARY or at UNRES1RIC1ED AREAS inside the S11E BOUNDARY shall be determined as follows:

Dr = air dose due to gamma emissions from noble gas radionuclide i (mrad)

3.17 x 10'8 EM j X/Q' Qg i

where:

M/Q' = relative concentration for the SITE BOUNDARY or '

UNRESTRICTED AREAS inside the SITE DOUNDARY

= 4.537 X 10-6* sec/m3 , in the WNW sector Mj = air dose factor due to gamma emissions from noble gas radionuclide 1 (mrad /yr per pCi/m3 )

from Table 2.1-1 The highest annual average X/Q for U,o MNS SITE BOUNDARY or UNRESTRICTED AREAS inside the SITE BOUNDARY is Hamilton Lake (WNW,0.75 miles). This value is taken from the Grand Gulf Nuclear Station Final Environmental Report, Table 6.1.28.

2.0-9 Draft GRAND GULF, UNIT 1

-EFMT5719.48/SNLICFLR

Qq = cumulative release of radionuclide i of noble gas, tritium, 1-131, 1-133, or material in j particulate form over the period of interest (pC1)

Note: 3.17 x 10-8 is the inverse of the number of seconds per year, and 06= air dose due to beta emissions from noble gas ;

radionuclide 1 (mrad) !

l

= 3.17 x 10'O IN 3570'Qg i [

where: i N4 = air dose factor due to beta emissions from noble I gas radionuclide 1 (mrad /yr per pCi/m3 ) from l Table 2.1-1 !

I V = relative concentration for the SITE BOUNDARY or UNRESTRICIED AREAS inside the SITE B0UNDARY

= 4.537 x 10-6* sec/m', in the WNW sector Q, e cumulative release of radionuclide i of noble gas, tritium, 1-131, 1-133, or material in particulate form over the period of interest (pCi)

The highest annual: average X/Q for the GGNS SITE BOUNDARY-or UNRESTRICTED AREAS inside the SITE DOUNDARY-is Hemilton Lake (WNW, 0.75 miles). This value is taken from the Grand Gulf Nucicar Station Final-Environmental Report -Table 6.1.28, 2.0-10 D" aft GRAND GULF,; UNIT 1 EfMT5719.48/SNLICFLR

b. Dose to an individual frora tritium, 1-13), 1-133 and radioactive materials in particulate form, with half-lives greater than eight (8) days will be calculated for the purpore of implementation of Appendix A Requirement 3.11.2.3 as follows:

Dp = dose to an individual from tritium, 1-131,.1-133 and radioruclides in particulate form, with half-life greater than eight days (mrem)

= 3.17 x 10*8 IR j W' Qj i

where:

W' = relative concentration at a controllirg location for an individual X/Q' = 4.057 x 10'" sec/m3 for inhalation and alt tRTIum pathways in the 5 sector or L. IQS x 107 ] ,-2 for food and

= 8 D/Q' ground plane pathways in the

$ Sector Rj = the. total dose factor for radionuclide i, 3

(mrem /yr per pCi/m ) for inhalation and all tritiumpathwaysand(m 2 . mrem /yr per pCi/sec) for food and ground plane pathways fron Tables-2.2-2a - d

This conservative approach utilizes values _for_the onsite GGNS gardens-(Tables 2,2-3 and 2.3-1). As an alternative GGNS may use

-the most conservative offsite controlling locations-identified in the above referenced tables.

2.0-10a Draft GRAND GULF, UNIT 1 EFMI5719.48/$NLICFLR L-

l. }

l i

04 = cumulative release of radionuclide i of noble gas, tritium, I-131, 1-133, or material in l 5

particulate form over the period of interest !

(pCi) l

c. For the purpose of implementing Technical !

Specification 6.9.), dose calculations will be performed using the above equations or with the substitution of average meteorological parameters (most limiting parameters will be used) which prevailed for ;

the period of the report, i 2.2.3 Dose Projection ,

Doses from gaseous effluents to UNRESTRICTED AREAS are projected at least every 31 days as required by Appendix A Requirement 4.11.2.5.1. These projections are made by averaging the doses (D y ,D g

, Dp) from previous operating hdstory (normally the previous six months) which is indicative of future expected operations.

1 i

i 2.0-10b Draft

- GRAND GULF, UNIT 1

___- , _ - - _ . _ - EFM. T 5719. 48/.S_NLI.CFLR -~. .-.-.._ _-_ _ _ . _ . . _ . _ . _ , . . _ . . _ . - _ . . - _ . _ . . _ _ .._ . _ . _ _ . _

i r

LADLL2J-la l

EA11fWALDOSLEA010RLE0fLAEEDil!1LLREQU1B WWL3mlh21 Land SEC1101L2Alu, (Py l Page 1 of 2

~

AGLGBDVI i1NfRD l._ L.jf1A. il GifEAtiD___ ;

_11010EE 111HALA110fL _ DR0VliDJLANE F000 i H3 6.468E402 0.000E400- 2.382E403 C-14 2.646E404 0.000E400 2.340E409 :

NA-24 1.056E404 1.979E407 1.542E407 P-32 2.030E406 0.000E+00 1.602E411 CR-51 1.284E404 7.864E406 4. 700E4 06 l

'MN-54 9.996E405 1.287E409 3.900E407 r MN-56 7.168E404 1.525E+06 2.862E400 TE-55 8.694E404 0.000E400 1.351E408 TE 1.015E406 4.562E408 3.919E408 i C0-58 7.770E405 6.194E408 6.055E407 i E0-60 4.508E406 5.172E409 2.098E408 i NI-63 3. 388E405 0.000E+00 3.493E+10 t

NI-65 5.012E404- 4.930E405 3.020E401 CV-64 1.498E404 9.823E405 3.807E406 i 7N-65 6.468E405 7.907E408 1.904E410 i ZN-69 1.322E404 0.000E400 3.855E-09 i BR-83 3.808E402 1.01]E404 9.339E BR-84 4.004E402 3.376E405 1.256E-22 i-BR-85 2.044E401 0.000E400 0.000E400 ;

RB 1.904E405 1.478E407 2.234E410 -

RB-88 5.572E402 5.399E404 1.874E-44 .

RB-89 3.206E402 2.075E405 4.193E-53 l SR-89 2.030E406 3.560E404 1.258E+10: !

SR -4.088E407 0.000E400 1.216E411 i SR 7.336EiO4 3. 587E4 06 3.215E405 ;

SR-92 1.400E405 1.233E406 5.005E401- l Y-90 2.688E405 7.583E403 9.406E405 Y-91M 2,786E403 1.658E405 1.876E-15 i Y-91 2.450E406 1.702E406 5.251E406 :!

Y 1.266E405 3.060E+05 1.026E401 ,

Y-93 1.666E505 3.620E405 1.776E404 l 2R-95 1.150E406- 3.975E408 8.25/E405- !

ZR-97 1.400D05 4.921E*06 .4.446E404 :

NO-95 4,788E40$ 2.291E*68 2.062E408 ,

-MO 1.348E405 6.608E406 3.108E408-TC-99M 2.030E403 3.013E405 1.646E404 i

-TC-101 8.442E402 3.253E404 1.423E-56 .

RU-103 .5.516E+05' 1.804E+08 1.055E405 i RV-105 4.844E+04 1.030E406 3.204E400 RV-10G' 1.156E407 3.590E408 1.445E406 AG-110M 3.668E406 3.649E409 1.461E+10 l

t f

2.0-11 Draft GRAND GULF,' UNIT 1 !

EfMI5719.48/SNLIEfLR ,

.i 1_ _ _._ . _ . _ _ _ . _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ -

V3LElblt.(Catttinuedl

-PAT

_H.WAY. DOSE. FACTORS FOR APPENDIX A. REQUIREMENT _3.1.1.2.1.and

-- - - -. --~

Page 2 of 2

~

AGLGRQUP flitiEAtiD_.- f LA. L - (IffEAliU__

._11010EE ___llfuALA110N GR0_Ul!D PLANE FQQD TE-125M 4.466E405 3.001E406 1.508E408 TE-127M 1.312E406 1.395E405 1.037E409 TE-127 2.436E404 4.704E403 1.359E405 TE-129M 1.680E406 3.290E407 1.392E409-TE-129 2.632E404 4.395E404 1.678E-07 TE-131M 1.988E405 1.351E407 2.288E407 TE-131 8.218E493 4.929E407 1.384E-30 TE-132 3.402E405 7.098E406 6.513E407 1-130 1.596E406 -9.560E406 e.754E408 1-131 1.484E407 2.985E407 1.053E412 1-132 1.694E+05 2.015E406 1.186E402 1-133 3.556E406 4.259E+06 9.601E409 I-134 4.452E404 7.578E405 8.40?E-10 1-135 6.958E405- 4.210E406 2.002E+07 CS-134 7.028E405 3.282E409 6.801E410 CS-136 1.345E405 2.432E408 5.795E+09

.CS-137 6.118E405 1.337E409 6.024E+10 C5-138 8.764E402 5.860E405 2.180E-22 BA-139 5.096E404 1.705E405 2.874E-05 BA-140 1.596E406 3.352E+07 2.410E408 BA-141 4. 746E4 03 6.762E404 3.141E-44 BA-142 1.554E403 7.234E404 0.000E400 LA-140 1.680E405 3.114E407 1.880E405 LA-142 5.950E+04 1.269E406 6.019E-06 CE-141 5.166E405 2.199E407 1.366E407-CE-143 1.162E405 3.753E406 1. 536E4 06 CE-144 9.842E406 6.761E407- 1.334E408

.PR-143 4.326E405 0.000E400 7.845E405 PR-144 4.284E403 3.017E403 1.171E-48 ND-147 3.220E4 05 - 1.441E407- 5.743E405 W-187 3.962E404 3.915E*06 2.501E606

i. NP-239 5.950E404 2.823E406 9.400E404

'lln i t s : Inhalation 2and all- tritium pathways - mrem /yr per pCi/m 3 Others - m , mrem /yr per_ pCi/sec

' Values based-on standard NUREG-0133, Section 5.2.1 assumptions unless otherwise indicated.

2.0-12 Draft ORAND GULF, UNIT 1 EFMI5719.48/SNLICFLR

IABLL2 Alb PATHWAY ____D05LEAC10RS_IOR_AEEERO.1X A REQUIREFENT 3.dl 2 Dad 1EC.UQtL24L.b. (Pp

-Page 1 of 2 AGE _ GROUP ( CHJLD 1 ( N. A. ) ( Cd1LQ__1_

.15010EL_. It4BALA110N -GRQWQ_.ELA!E GB1/AliLIMEAI I H-3 1.125E403 0.000E400 1.826E402 C-14 3.589E404 0.000E400 2.991E408 NA-24 1.610E404 1.385E407 1.345E-03 P-32 2.605E+06- 0.000E400 5.781E409 CR-51 1.698E*04 5.506E406 3.636E405 MN-54 .1.576E+06- 1.625E409 6.249E+06 MN-56 1.232E405 1.068E406 1.901E-51 FE-55 1.110E405 0.000E400 3.566E408 FE-59 1. 269E406 3.204E408 4.943E408 C0-58 1.106E406 4.464E408 7.48:E+07 C0-60 7.067E406 2.532E410 2.993E408 NI-63 8.214E405 0.000E400 2.272E+10 NI-65 8.399E404 3.451E405 3.167E-51 CU-64 3.670E404 6.876E+05 1.087E-05 ZN-65 9.953E405 8.583E408 7.801E408 ZN-69 1.018E404 0.000E400 0.000E400 BR-83 4.736E402 7.079E403 7.425E-57 BR-84 5.476E+02 2.363E405 0.000E400 BR-85 2.531E401 0.000E400 0.000E400 RB-86 1.983E405 1.035E407 4.536E+08 RB-88. 5.624E402 3.779E404 0.000E400

-RB 3.452E402 1.452E405 0.000E400 SR-89 2.157E406 2.509E404 3.756E408 SR-90 1.010E408 0.000E400 8.111E+09 SR-91 1.739E+05- 2.511E406 4.128E-10 SR-92 2.424E+05 8.631E405 2.724E-48 Y-90 2.679E405 5.308E403 3.806E+05 Y-91M 2.812E403 1.161E405 0.000E+00 Y-91 2.627E406 1.207E406 1.872E408 Y-92 2,390E405 2.142E405 5.428E-35 Y-93 3.885E*05 2.534E405 1.207E-07 L ZR-95 2.231E406 2.837E408 4.763E408 l ZR-97 -3.511E405 -3.445E406 5.471E-01 L NB-95 6.142E405 1.605E+08 1.738E+09 L MD-99 -1,354E405- 4.626E406 -1.915E+05-TC-99M 4.810E4 03 2.109E405 5.394E-18 TC 101 5.846F402 2.277E404 0.000E+00 RU-103 6.623E+05 1.265E408 3.127E+09 nt-105 9.953E404 7.212E405 4.590E-25 RU-106 '1.432E407 5.049E+08 5.384E+10 AG-110M 5.476E406 4.019E409- 5.259E408 2.0-13 Draft

' GRAND GULF, UNIT 1 EfMT5719.48/SNLICFLR U:l...,_.,L.-..-..--.---.-...-.--.-.-....--..=---------- .

9 :

. g IABLE_22-Ib_.ICottLinued) f PAIJ1WAY QQSE l0fLAEEWD1LA RE0VIREBERI_L1L21 Land !

1E.CROJLLLLb, (P j)

@5;010RS !

Page 2 of 2 AGE _GRO.UP ( ChlLD 1 __ ( N uA. ) ( CHILD 1 !

_n010EE IHUAL&ILON GRQM8Q_ELANE GRSIANLIMEAl*

TE-125M 4.773E+05 2.128E+06 4.43BE408 .

TE-127M 1.480E406 '

1.083E+05 3.947E409 TE-127 5.624E404 3.293E403 1.254E-08 i TE-129M 1.761E+36 2.305E407 4.091E409 TE-129 2.549E+04 3.076E+04 0.000E400 lE-131M 3.078E405 9.459E406 7.656E403 l TE-131 2.054E*03 3.450E407 0.000E400 t TE-132 3.774E405 4.968E406 7.274E+06 1-130 1.846E+06 6.692E406 5.271E-04 '

1-131 1.624E407 2.089E407

293E409 1-132 1.935E405 1.452E406 1.895E-57 1-133 3.848E406 2.981E406 1.017E402

I-134 5. 069E4 04 5.305E+05 0.000E4 00 ,

1-135 7.918E405 2.947E406 8.104E-15 CS-134 1.014E406 8.007E409 1.180E+09 >

CS-136 1.709E+05 1.702E408 3.452E407 i CS-137 9.065E405 1.201E+10 1.040E409 CS-138 8.399E+02 4.102E405 0.000E400 BA-139 5.772E404 1.194E405 0.000E400 ,

BA-140 1.743E406 2.346E407 3.420E407 i BA-141 2.919E403 4.734E404 0.000E400 ;

BA-142 1.643E+03 5.064E404 0.000E400 '

LA-140 2.257E405 2.180E407 4.284E402 LA-142 7.585E404 8,886E405 0.000E+00 CE-141 5.439E405 1.540E407 1.078E407 i CE-143 1.273E405 2.627E406 1.963E402 :

CE-144 1.195E407 8.032E407 1.476E408 !

PR-143 4.329E405 0.000E400 2.815E407 ;

PR-144 1.565E403 2.112E+03 0.000E400 ;

ND-147 L 282E406 1.009E407 1.174E+07 W-187 9.iO2E404 2.740E+06 2.176E400 :

NP-239 6.401E404 1.976E406 1.741E403 3 3

linit s : Inhalation and a 1 tritium pathways - mrem /yr per pCi/m Others - m2 , mrem /yr per pCi/sec I

Valuo based on standard NUREG-0133, Section 5.3.1 assumptions unless i j otherwise indicated. $

Meat consumption assumed 75 percent beef and 25 percent mutton. l i

l 2.0-14 Draft j GRAND GULF, UW 7 1 >

EfMT5/19.48/SNLiCFLR ;

lABLE_212-Za 2A1HWALDOS ESC 10RLE0LACEttiDILLBLQUIREtiERLLn41AtlD SEQHORAL2J. (Ry Page 1 of

'AGLGRODP f IREARLJ L N.L i ( IREAtil i f 1REANT )_ ( _ IREA[11 1 ISQIDEE_.__JNtiAL&110N GROUBQ__El.AML_GRSLLOWIMILK .. .GRSif0W/ MEAT YLGEIA110ll H-3 6.468E402 0.000E400 2.382E403 0.000E400 0.000E400 C-14 2.646E404 0.000E400 2.340E409 0.000E400 0.000E400 NA-24 1.056E404 1.385E407 1.542E407 0.000E400 0.000E400 P-32 2.030E406 0.000E+00 1.602E411 0.000E400 0.000E400 CR-51 1.284E404 5.506E406 4.700E406 0.000E400 0.000E+00 MN-54 9.996E405 1.625E409 3.900E407 0.000E400 0.000E+00 MN-56 7.168E404 1.068E406 2.862E+00 0.000E+00 0.000E400 FE-55 8.694E404 0.000EiOO 1.351E408 0.000E400 0.000E+00 FE-59 1.015E406 3.204E408 3.919E408 0.000E400 0.000E400 C0-58 7.770E405 4.464E408 6.055E+07 0.000E+00 0.000E4 00 C0-60 4.508E+06 2.532E+10 2.098E408 0.000E400 0.000E400 NI-63 3.388E405 0,000E400 3.493E+10 0.000E400 0.000E+00 NI-65 5.01PE404 3.451E405 3.020E401 0.000E400 0.000E+00 CU 1,498E404 - 6.876E405 3.807E406 0.000E400 0.000E400 ZN-65 6.468E405 8.583E+08 1.904E+10 0.000E400 0.000E+00 ZN-69 1.322E404 0.000E400 3.855E-09 0.000E400 0.000E+00 BR-83 3.808E402 7.079E403 9.339E-01 0.000E400 0.000E400 BR-84 4.004E+02 2.363E405 1.256E-22 0.000E400 0.000E+00 BR-85 2.044E401 0.000E400 0.000E400 0.000E400 0.000E400 RB-66 1.904E405 1.035E407 2.234E+10 0.000E400 0.000E400 RB-68 5.572E+02 3.779E404 1.874E-44 0.000E+00 0.000E400 RB-89 3.206E402 1.452E+05 4.193E- 53 0.000E400 0.000E+00 SR-89 2.030E+06 2.509E404 1.258E410 0.000E400 0.000E*00 SR-90 4.088E407 u.000E400 1.216E+11 0.000E+00 0. 000E4 00 SR-91 7.336E404 2.511t'06 3.215E405 0.000E400 0.000E400 SR-92 1.400E405 8.631E405 5.005E+01 0.000E400 0.000E+00 Y-90 2.588E405 5.308E403 9.406E405 0.000E*00 0.000E4 00 Y-91M 2.786E403 1.161E405 1.876E-15 0.000E400 0.000E400 Y-91 2.450E406 1.207E406 5.251E406 0.000E+00 0.000E400 1 1.266E405 2.142E405 1.026E401 0.000E400 .0.000E*00 Y-93 1.666E405 2.534E405 1.776E404 0.000E+00 0.000E400 ZR-95 1.750E406 2.837E+08 8.257E405 0.000E4 00 0.000E+00 ZR-97: 1.400E405 3.445E+05 4.446E+C4 0.000E+00 0,000E400 NB-95 4.788E+05 1.605E+08 2.062E+08 0.000E+00 0.000E400 M0-99 1.348E405 4.626E+06 3.108E408 0.000E+00 0.000E+00 TC-99M 2.030E403 2.109E405 1.646E404 0.000E400 0.000E400 IC-101 8.442E402 2.277E404 1.423E-56 0.000E400 0.000E+00 RU-103 5. 516E405 1.265E408 1.055E405 0.000E400 0.000E+00 RU-105 4.844E404 7.212E405 3.204E400 0.000E400 0.000E400 RU-106 1.156E+07 5.049E408 1.445E406 0.000E+00 0.000E400 AG-110M 3.668E+06 4.019E409 1.461E+10 0.000E400 0.000E400 l 2.0-15 Draft GRAND GULF. UNIT 1 l

.EFMT5719.48/5NLICFLR

IABLE12-2a_(Collinuedl EA1HWALD01tJE10RS_LORREINQ1LARQUIREBLMIAILALAND

.51C110N 1 2. L b. (Rj )

Page 2 of 2 AGE _GRQVP ( fMEARI_1 ( N.A. 1 ( INEANT ) ( INFANT ) ( INFANT j_

1$010PE _ _INHAlall0N J ROVND_ ELAN E_.__GR5LCOWINIUL_GRILCOW/EEAT EEGEIAllDit.

TE-125M 4.466E405 2.128E 06 1.508E408 0.000E400 0.000E400 1E-127M 1.312E406 1.083E405 1.037E409 0.000E400 0.000E400 TE-127 2.436E404 3.293E403 1. 359E405 0.000E400 0.000E400

_1E-129M 1.680E406 2.305E407 1.392E409- 0.000E400 0.000E+00 !

TE-129 2.632E404 3.076E404 1.678E-07 0.000E400 0.000E400 J TE-131M 1.988E405 9.459E406 2.288E407 0.000E400 0.000E400 !

1E-131 8.218E403 3.450E407 1.384E-30 0.000E400 0.000E400 l TE-132 3.402E405 4.968E406 6.513C407 0.000E400 0.000E400 l I-130 1.596E406 6.692E406 8.754E408 0.000E400 0.000E400 1 1-131 1.484E407 2.089E407 1.053E+12 0.000E400 0.000E400 i 1-132 1.694E405 1.452E406 1.188E402 0.000E400 0.000E400 l I-133 3.556E406 2.981E406 9.601E409 0.0000400 0.000E400 i 1-134 4.452E404 5.305E405 8.402E-10 0.000E400 0.000E400 f I-135 6.958E405 2.947E406 2.002E407 0.000E400 0.000E400 i CS-134 7.028E405 8.007E409 '

6.801E410 0.000E400 0.000E+00 C5-136 1.345E+05 1.702E408 5.795E409 0.000E400 0.000E400 t CS-137 6.118E*05 l'.201E410 6.024E410 0.000E400 0.000E400 !

CS-138 8.764E402 4.102E405 2.180E-22 0,000E+00 0.000E400 !

BA-139 5.096E404 1.194E405 2. 874 E- 05 0.000E400 0.000E400 BA-140 1.596E406 2.346E407 2.410E408 0.000EiOO 0.000E400 BA-141 4.746E403 4.734E+04 3.141E-44 0.000E400 0.000E400 t

-BA-142-- -1.554E403 5.064E404 0.000E400 0.000E400 0.000E400 l LA-140 1.680E405 2.180E407 1.880E405 0.000E400 0.000E400 ,

LA-142 5.950E404 8.886E405 6.019E-06 0.000E400 0.000E400 l CE-141- 5.166E405 1.540E407 1.366E407 0.000E400 0.000E400 7 CE-143 1.16?E405 2.627E406 1.536E406 0.000E+00 0.000E400 >

CE-144 9.842E406 8.032E407 1.334E+08 0.000E400 0.000E400 ;

PR-143 4.326E405 0.000E400 7.845E405 0.000E400 0.000E400 i PR-144 4.284E+03 2.112E403 1.171E-48 0.000E400 0.000E400 :

ND-147 3.220E405 1.009E407 5.743E405 0.000E400 0.000E400 !

i W-187 _ 3.962E404 2.740E406 2.501E+06 0.000E400 0,000E400 i NP-239 5.950E404 1.976E406 9.400E404 0.000E+00 0.000E+00 t

3 Units: Inhalation and all tritium pathways - mrem /yr per pCi/m Others - m2. mrem /yr per pC1/sec Values based on standard NUREG-0133, Section 5.3.1 assumptions unless otherwise- ;

-indicated. i I

2.0-16 Draft I 1

1 GRAND GULF. UNIT 1 !

EfMT5719.48/SNLICFLR

]

_ . _ . _ _ _ _ _ . _ _ . _ _ _ = _ a-- a

JABLL222-2b PA1WALDOS LEACJOALE0LAffMDJLAJE0111RLtiMLML 21MD SEC110!L212221b, (R )

4 Page 1 of 2

~

AGLGROUP ( C1111,0 ) ( 'ii.L.J f CHILD -) f Cli1LD- ) ( CHI LIL _ L '

l$.010fE INtiALAi10N GROUNDJ1ME__GRSICOMMILK .GRSLCDW/ MEAL _ EEG11A110]L 11- 3 1.125E403 0.000E400 1.570E403 2.341E402 4.008E403 C-14 3.589E404 0.000E400 1.195E409 3.3342408 8.894E408 NA-24 1.610E404 1.385E407 8.853E406 1.725E-03 3.729E405 P-32 2.005E406 0.000E400 7.775E410 7.411E409 3.366E409 ;

CR-51 1.698E404 5.506E406 5.398E406 4.661E405 6.213E406 MN-54 1.576E406 1.625E409 2.097E407 8.011E406 6.648E408 i MN-56 1.232E405 1.068E406 1.865E400 2.437E-51 2.723E403 FE 55 1.110E405 0.000E4 00 1.118E408 4.571E408 8.012E408 FE-59 1.269E406 3.204E408 2.025E408 6.338E408 6.693E408 CO-58 1.106E406 4.46AE408 7.080E407 9.596E407 3.771E408 C0-60 7.067E406 2.532E410 2.391E408 3.838E+08 2.095E409 N1-63 8.214E405 0.000E400 2.964E410 2.912E410 3.949E+10 NI-65 8.399E404 3.451E405 1.909E+01 4.061E-51 1.211E403 CU-64 3.670E404 6.876E405 3.502E406 1.393E-05 5.159E405 7N-65 9.953E+05 8.583E408 1.101E+10 1.000E409 2.164E409 ZN-69 1.018E404 0.000E400 1.123E-09 0.000E400 9.893E-04 BR-83 4.736E402 7.079E403 4.399E-01 9.519E-57 5.369E400 BR-84 5.476E402 2.363E405 6.508E-23 0.000E400 3.822E-11 ,

BR-85 2.531E+01 0.000E400 0.000E400 0.000E400 0.000E+00 RB-86 1.983E405 1.035E407 8.804E409 5.816E408 4.584E408 RB-88 5.624E402 3.779E404 7.150E-45 0.000E400 4. 374 E- 22 RB-89 3.452E+02 1.452E+05 1.715E-53 0.000E+00 1.642E-26 SR-89 2.157E+06 2.509E404 6.618E409 4.815E408 3.593E410 SR-90 1.010E408 0.000E400 1.11/E+11 1.040E+10 1.243E412 SR-91 1.739E*05 2.511E406 2.878E+05 5.292E-10 1.157E406 SR-92 2.424E405 8.631E405 4.134E401 3.492E-48 1.378E404 Y-90 2.679E405 5.308E403 9.171E405 4.879E405 6.569E+07 Y-91M 2.812E403 1.161E405 5.198E-16 0.000E400 1.737E-05 Y-91 2.627E406 1.207E+06 5.199E406 2.400E408 2.484E409 Y-92 -2.390E405 2.142E405 7.310E400 6.959E-35 4.576E404 Y-93 3.885E405 2.534E405 1.573E404 1.547E-07 4.482E406 t ZR-95 2.231E406 2.837E408 8.786E405 -6.106E408 8.843E408 7R-97 3.511E405' 3.445Ee06 4.199E404 7.015E-01 1.248E407 ND-95 6.142E405 1.605E+08 2.287E408 2.228E+09 2.949E408 MD-99 1.354E605 4.626E+06 !.738E408 2.456E405 1.647E407 TC-99M 4,810E403 2.109E405 1.474E+04 6.915E-18 5.255E+03

.10-101 5.846E+02 2.277E+04 5.593E-58 0.000E400 4.123E-29 RU-103- 6,623E405 1.265E408 1.108E+05 4.009E409 3.971E408 RU-105 9.953E404 7.212E4 05 2.493E+00 5.885E-25 5.981E404 RU-106 1.432E407 5.049E408 1.437E+06 6.902E410 1.159E+10 AG-110M 5.476E+06 4.019E409 1.678E+10 6.742E408 2.581E409

\.

j- 2.0-17 Draft ;

GRAND GULF, UNIT 1 EfMT5719.48/5NLICfLR-

R 1ABLE 2.2-2b (CoAtinutd) fA1WALQQSE FAC10RSl0!LAEEWQ1LA.REQUIREKMLid111AND 1ECllDN 2.2 21b (R4 ) )

Page 2 of 2 AGLGRQDP ( Clulu- ) L N .A,_1 L_ClilLD ) ( GILD ) ( ClllLD_L ISQlDPE IMALAI1QN GROUh91 LANE G!UiLCQW/EILK_ GRS2(QWMEAT VEGETATION -

1E-125M 4.773E405 2.128E406 7.377E407 5.690E408 3.506E+08 TE-127M 1.480E406 1.083E405 5.932E408 5.060E+09 3.769E409 TE-127 5.624E+04 3.293E+03 1.191E405 1.607E-08 3.903E405 TE-129M 1.761E406 2.305E407 7.961E408 5.245E409 2.460E409 TE-129 2.549E404 3.076E404 6.166E 08 4.000E400 7.204E-02 TE-131M 3.078E405 9.459Ee06 2.244E+07 9.815E403 2.163E407 i TE-131 2.054E403 3.450E+07 8.489E 32 0.000E400 1.349E-14 )

TE-132 3.774E405 4.968E406 4.551E407 9.325E406 3.111E407-1-130 1.846E406 6.692E406 3.845E408 6.758E-04 1.370E408 1-131 1.624E*07 2.089E407 4.333E411 5.503E409 4.754E+10 1-132 1.935E405 1.452E406 5.129E401 2.429E-57 7.314E403 1-133 3.840E406 2.981E+06 3.945E409 1.304E402 8.113E408 1-134 5.069E404 5.305E+05 3.624E-10 0.000E400 6.622E 03 1-135 7.918E+05 2.947E406 8.607E406 1.039E-14 9.973E+06 CS-134 1.014E406 8.007E409 3.715E+10 1.513E409 2.631E*10 CS-136 1.709E405 1.702E408 2.773E409 4.426E407 2.247E+08 CS-137 9.065E405 1.201E+10 3.224E410 1.334E409 2.392E+10 CS-138 8.399E402 4.102E405 5.528E-23 0.000E+00 9.133E-11 ,

BA-139 5.772E404 1.194E405 i.231E-05 0.000E400 2.950E400 BA-140 1.743E406 2.346E407 1.171E408 4.384E407 2.767E408 BA-141 2.919E403 4.734E404 1.210E-45 0.000E4 00 1.605E-21 BA-142 1.643E403 5.064E404 0.000E400 0.000E400 4.105E-39 LA-140 2.257E+05 2.180E+07 1.894E405 5.492E402 3.166E+07 LA-142 7.585E404 8.886E405 2.904E-06 0.000E400 1.582E401 CE-141 5.439E405 1.540E407 1. 361E407 1.382E407 4.082E408 CE-143 1.273E+05 2.627E+06 1.488E+06 2.516E+02 1.364E407 CE-144 1.195E407 8.032E+07 1.326E408 1. 893E408 1.039E410 PR-143 4.329E405 0.000E+00 7.754E405 3,609E407 1.575E408 PR-144 1.565E403 2.112E403 2.040E-50 0.000E+00 3.829E-23 ND-147 1.282E405 1.009E+07 5.712E405 1.505E407 9.197E+07 W-187 9.102E404 2.740E406 2.420E406 2.790E400 5.380E406 NP-239 6.401E404 1.976E+06 9.138E404 2.232E403 1.357E407 Units: Inhalation pand all tritium-pathways - mrem /yr per pCi/m 3 Others - m . mrom/yr per pCi/ sec Values based on standard NUREG-0133, Section 5.3.1 cssumptions unless otherwise indicated.

2.0-18 Draft GRAND GULF. UNIT 1 EFMI5719.48/SNLICFLR <

_ . _ _ . _ _ _ _ . . _ - . . _ _ . . _ . _ . . . . - , _ . _ _ . . _ . _ . _ . _ . . . ~ _ _ _ _ - . _ _

i I

r JABLE_L h as f EA1BWALDQSE EAC10RS_IOR_A!TE801X .A REQUIREMENLLELLAND i S10110lLLLLb. (R4 ) [

t Page 1 of 2 l f

5~GE_GROUE _LIEElaGERL ( N A. 1 LIEENAGER) LIEEtnGER) (IEEtnGERL. !

IS010EE INLIALA110N _ GRORND _ PLANE ____CBSLCQW/ MILK GRSIEORMEAT VEGEIAl101L !

H-3 1.272E4 03 0.000E+00 9.941E+02 1.938F402 2.588E+03 :

C-14 2.600E404 0.000E400 4.859E408 2.040E408 3.690E408 i NA-24 1.376E404 1.385E407 4.255E406 1.084E-03 2.389E405 !

P-32 1.888E406 0.000E400 3.153E+10 3.931E409 1.608E409 !

CR-51 2.096Et04 5.506E406 8.387E406 9.471E+05 1.037E407 i MN-54 1.984E406 1.625E+09 2.875E407 1.436E407 9.320E408 i MN-56 5.744E404 1.068E406 4.856E-01 8.302E-52 9.451E+02 I FE-55 1.240E405 0.000E400 4.454E407 2. 382E4 08 3.259E408 ;

FE-59 1.528E406 3.204E408 2.861E408 1.171E409 9.895E408 I CO-58 1.344E406 4.464E408 1.095E408 1.942E408 6.034E408 -!

C0-60 8.720E406 2.532E410 3.62]E408 7.600E408 3.238E+09

N1-63 5.800E405 0.000E+00 1.182E+10 1.519E410 1.606E+10 I N1-65 3.672E+04 3.451E405 4.692E400 1.305E-51 3.966E402 I CU-64 6.144E404 6.876E405 3.293E406 1.713E-05 6.465E405 !

ZN-65 1.240E406 8.583E+08 7.315E409 8.688E408 1.471E409- !

ZN-69 1.584E403 0.000E+00 1.760E-11 0.000E+00 2.067E-05 BR-83 3.440E402 7.079E403 1.790E-01 5.066E-57 2.911E400 BR-84 4.328E402 2.363E405 2.877E-23 0.000E400 2.251E-11 ,

BR-85 1.832E+01 0.000E+00 0.000E400 0.000E400 0.000E+00 i RB-86 1.904E405 1.035E407 4.7EE409 4.101E408 2.772E408 RB-88 5.456E402 3.779E404 3.Si E-45 0.000E400 3.168E-22 i RB-89 3.520E402 1.452E405 9.774E-54 0.000E400 1.247E-26 i SR-89 2.416E406' 2.509E404 2.674E409 2.545E408 1.513E+10 l SR 1.080E408 0.000E400 - 6.612E+10 8.049E409 7.507E+11 '

SR-91 2.592E+05 2.511E406 2.409E405 5.794E-10 1.291E406 i SR-92 1.192E405 8.631E405- 2.277E401 2.516E-48 1.012E404 i Y-90 . S.592E405 5.308E403 1.074E+06 7.470E405 1.025E408 i Y-91M 3.200E403 1.161E405 5.129E-18 0.000E400 2.285E-07 !

Y-91 2.936E406 1.207E406- 6.475E406 3.910E408 3.212E409 }

Y-92 1.648E405 2.142E+05 2.828E400 3.522E-35 2.360E404 i Y-93 5.792E405 2.534E+05 1.312E*04 1.688E-07 4.983E406 !

2R-95 2.688E406 2.837E408 1.201E406 1. 092E4 09 1.253E409 !

ZR-97 6.304E405 3.445E406 4.225E404 9.231E-01 1.673E407 i ND-95 7.512E405 1.605E408 3.338E408 4.251E+09 4.551E408 :

M0-99 2.688E405 4.626E+06 1.023E408 1.892E405 1.293E407 TC-99M 6.128E403 2.109E405 1.055E+04 6.471E-18 5.011E+03 {

TC-101 6.6726 02 2.277E404 3.287E-58 0.000E400 3.229E-29 i RU-103 7.832E4 05 1.265E408- 1.513E405 7.162E409 5.706E408 !

RU-105 9.040E404 7.212E405 1.263E400 3.900E-25 4.039E404 )

RU-106 1.608E407 5.049E408 1.799E+06 1.130E+11 1.484E410 i AG-110M 6.752E406- 4.019E+09 2.559E410 1.345E4 09 4.031E+09 l I

2.0-19 Draft -i GRAND GULF, UNIT 1 l EFMI5719.48/SNLICFLR l

IADLEll-lc_(Continnd)

PA111WAL 003 E_EACIORL EOR _Al2LNQ1LAlEQUIRWERLid1ALAND SEC11DR 1 2,2J (R4 )

Page 2 of 2 AGE R OUP (IEEBAGERI [ N A2 m__) (lIWAGER) IILENAGER) LIEENAGER)_

15010PE 1EliALA110N GROVBQlLAME GR$4t0WlEILtL__GRS100W/EE61 VEGEIA110R.

lE-12bM 5.360E405 2.128E406 8.863E407 8.941E408 4.375E408 TE-127M 1.056E406 1.083E405 3.420E408 3.816E409 2.236E409-TE-127 8.080E404- 3.293E403 9.572E404 1.689E-08 4.180E405 s TE-129M 1.976E406 2.305E407 4.602E408 3.966E409 1.508E409 !

1E-129 3.296E403 3.076E404 2.196E-09 0.000E400 3.418E-03 ,

TE-131M 6.208E405 9.459E406 2.529E407 1.447E404 3.248E407 l 1E-131 2,336E403 3.450E407 2.879E-32 0.000E400 6.099E-15 !

1E-132 4.632E405 4.968t+06 8.581E407 2.300E407 -7.818E407 :

1-130 1.488E406 6.692E406 1.742E+08 4.005E 8.276E407 !

1-131 1.464E407 2.089E407 2.195E411 3.645E409 3.140E+10 l 1-132 1.512E405 1.452E406 2.242E401 1.389E-57 4.262E403 1-133 2.920E406 2.981E406 1.674E409 7.234E401 4.587E408 !

134 3.952E404 5.305E405 1.583G10 0.000E400 3.854E 03- !

1-135 6.208E405 2.947E406 3.77406 5.963E-15 5.832E+06 ;

CS-134 1.128E406 8.007E409 2.31v 9 1. 231E4 09 1.671E410 CS-136 1.936E405 1.702E408 1.759E409 3.671E+07 1. 708E408 CS-137 8.480E405 1.201E410 1.781E+10 9.634E408 1.348E+10 CS-138 8.560E402 4.102E405 3.149E-23 0.000E400 6.935E-11 i RA-139 6.464E403 1.194E405 7.741E-07 0,000E400 2.472E-01 BA-140 2.032E406 2.346E407 7.483E407 3. 663E4 07 2.130E408 BA-141 3.288E403 4.734E+04 4.922E-46 0.000E400 8.699E-22

BA-142 1.912E403 5.064E404 0.000E+00 0.000E400 2.269E-39 :

LA-140 4.872E405 2.180E407 2.291E405 8 689E402 5.104E407 '

LA-142 1.200E404 8.886E405 2.574E-07 0.000E400 1.868E400

CE-141 6.136E405 1.540E407 1.696E407 2.252E407 5.404E408 CE-143 2.552E405 2.627E406 1.671E406 3.695E402 2.040E407 CE-144 1.336E407 8.032E407 . 1.655E408 3.089E408 1.326E+10 '

PR-143 4.832E405 0.000E400 9.553E405 5.817E+07 2.310E408 PR 144 1.752E403 2.112E403 1.238E-53 0.000E400 3.097E-26 ;

ND-147 3.720E405 1.009E407 7.116E405 2,452E407 1.424E408 W-187 1.768E405 2.740E406 2.646E406 3.989E400 7.839E406 NP-239 1.320E405 1.976E406 1.060E+05 3.387E403 2.097E407 Units: InSalation 2and all tritium pathways mrem /yr por pCi/m 3

- Others - a . mrom/yr per pCi/sec Values based on standard NUREG-0133, Section 5.3.1 assumptions unless otherwise indicated.

2.0-20 Draft ,

GRAND GULF, UNIT 1 EFMT5719.48/5NLICFLR pgge p., my.,ggg gma.nyr cy a g-pg yy.geg.-qwa say.pqpgqggy pqq, pm 9, p y *Wyq wp $yi* hs.' p q rwp' y FT tre-wwump twy .g' p wvM F g*- *tM-*#'$

i I

IABLE_2 4 2d EAltNALDOSIJAC10RLEOR AEEE801ULRE0MIRGENLb1h2AMfD RC110H12. Pub (R4 ) !

il Page 1 of 2 6GLGROUP ( AQULT T ( lid 1 L A0140 1- lL.ADQU ) i AQULLL i ISD10EL INEALA110H GROUND _fLAlfE___.GRSIC0Wo31LK GRSLCOWitiE61 _.YLGEIA110L i H3 1.264E403 0.000E400 7.629E402 3.248E402 2.260E403 l C-14 1.816E+04 0.000EN0 2.634E408 2.414E408 2.276E408 i NA-24 1.024E404 1.3852407 2.438E400 1.356E-03 2.690E405 '

P-32 1.320E406 0.000E400 1.709E410 4.651E409 1.403E409 CR-51 1.440E*04 5,506E406 7.187E406 1.772E406 1.168E407 i MN-54 1.400E406 1.625E409 2.578E407 2.812E407 9.b85E408 !

MN-56 2.024E404 1.068E406 '

1.328E-01 4.958E 52 5.082E402 FE-55 7;208E404 0.000E400 - 2.511E407 2.933E408 2.096E408 i FE-59 1.016E406 3.204E408 2.326E408 2.080E409 9.875E408 i 00-58 9.280E405 4.464E408 9.565E407 3.703E408 6.252E608 C0-60 5.968E406 2.532E+10 3.082E408 1.413E409 3.139E409 !

N1-63 4.320E405 0.000E400 6.729E409' 1.888E+10 1.040E410 (

N1 65 1.232E404 3.451E405 1.219E400 7.405E-52 2.026E+02 t C0-64 4.896E404 - 6.876E405 2.031E406 2.307E-05 7.841E405 !

ZN-65 8.640E405 8.583E408 4.365E409 1.132E409 1.009E409 !

ZN 69 9.200E402 0.000E400 5.207E-12 0.000E400 1.202E-05 1 BR-83 2.408E402 7.079E403 1.399E-01 8.648E-57 4.475E400 BR-84 3.128E402 2.363E 05 1.609E-23 0.000E400 2.475E-11 BR-85 1.280E401 0.000E+00 0.000E400 0.000E400 0.000E400 i RD-86 1.352E405 1.035E407 2.604E409 4.914E*08 2.217E408 RB-88 3.872E402 3. 779E4 04 2.139E-45 0.000E400 3.428E-22 RB-89 2.560E402 1.452E405 5.523E-54 0.000E+00 1.385E-26 I SR-89 1. 400E4 06 2.509E404 1.451E409 3.014E408 9.061E409 !

SR-90 9.920E407 0.000E400 4.680E410 1.244E+10 6 SE*11 I SR-91 1.912E405 2.511E406 1.377E405 ? 233E-10 1.451E+06 I SR-92 4,304E404 8.631E405 9.675E400 2.334E-48 8.452E+03 l Y 90 5.056E405 5.308E403 7.511E405 1.141E406 1.410E408 i Y-91M- 1.920E403 1,161E+05 1.743E-19 0.000E400 1.527E-08 [

Y-91 1.704E406 1.207E406 4.726E406 6.231E408 2.814E?09 t Y.92 7.352E404 2.142E405 9.772E-01 2.657E-35 1.603E404 ,

Y-93 4.216E405 2.534E405 7.388E403 2.075E-07 5.517E406 !

2R-95 1.768E406 2.837E408 9.587E405 1.903E409 1.194E409 L ZR-97 5.232E405 3.445E406 2.707E404 1.292E400 2.108E407 i NB-95 5,048EiO5 '.605E408 2.786E408 7.74BE409 4.798E+08 i

-MO-99 2.480E405 4.626E406 5.741E407 2.318E405 1.426E407 t TC-99M- 4.160E403 2.109E405 5.553E403 7.439E-18 5.187E403 !

T0-101 3.992E402 2.277E404 1.813E-58 0.000E400 3.502E-29 ,

RU-103 5.048E+05 1.26bE408- 1.189E405 1.229E410 5.577E408 !

RU-105 4,816E404 7.212E405 5.240E-01 3.533E-25 3.294E+04 i RU-106 9.360E406 5.049E408 1.320E+06 1.811E+11 1.247E+10 l

.AG-110M 4,632E406 4. 019E4 09 2.198E410 2.523E409 3.979E409 i i

2.0-21 Oraft

)

GRAND GULF, UNIT 1

! EfM15719.48/SNLICFLR ;

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

MilLL212-2LIConu0uuD MulWALDOSLfACl08LfOR APPERQ1L6_REQUEEEDLL4JLLL#iD 1EC110N..L 2 A b. (Rg )

Page 2 of 2 AGLGROUP ( AD01J ) ( N. A. ) f ADVL1 ) ( ADI)LT. .. ..L ( __AQV11 )

11010PE INHALAIJQN GROUND _PL&NE GMLCOW/Jilu GR$1COWBEAT YEGElAHOL 1E-125M 3.136E405 2.128E*06 6.626E407 1.460E409 3.927E408 1E-127M 9.66dE405 1.083E+05 1.860E408 4.531E+09 1.418E409 TE-127 5.736E404 3.293E403 5.278E404 2.034E-08 4.532E405 TE-129M 1.160E406 2.305E407 3.028E408 5.698E409 1.261E409 1E-129 1.936E403 3.076E+04 9.167E-10 0.000E+00 2.806E-03 1F-131M 5.560E405 9.459E406 1.753E407 2.190E404 4.428E407 TE-131 1.392E403 3.450E407 1.578E-32 0.000E400 6.575E-15 1E-132 5.096E405 4.968E406 7.324E407 4.287E407 1.312E408 1-130 1.136E406 6.692E406 1.050E408 5.272E-04 9.809E407 1-131 1.192E407 2.089E407 1.388E411 5.034E+09 3.785E+1n J-132 1.144E+05 1.452E406 1.342E401 1.816E-57 5.016E403 1-133 2.152E406 2.981E406 9.891E408 9.336E401 5.331E408 1-134 2.984E+04 5.305E405 9.491E-11 0.000E400 4.544E-03 1-135 4.480E405 2.947E406 2.217E+06 7.644E-15 6.731E406 CS-134 8.480E+05 8.007E+09 1.345E+10 1.565E409 1.110E+10 CS-136 1.464E405 1.702E408 1.036E409 4.724E+07 1.675E408 C5-137 6.208E405 1.201E+10 1.010E410 1.193E409 8.696E409 CS-138 6.208E402 4.102E405 1.786E-23 0.000E400 7.730E-11 i' DA-139 3.760E403 1.194E+05 8.322E-08 0.000E400 5.225E-02

_ BA-140 1.272E406 2.346E407 5.535E407 5.917E+07 2.646E408 BA-141 1.936E403 4.734E+04 2.677E-46 0.000E+00 9.305E-22 l BA-142 1.19?E403 5.064E404 0.000E400 0.000E400 2.463E-39 LA 140 4.584E405 2.180E+07 1.672E405 1.385E403 7.327E407 LA-142 6.328E403 8.886E405 3.503E-08 0.000E+00 4.999E-01 CE-141 3.616E405 1.540E407 1.253E407 3.632E407 5.097E408 CE-143 2.264E405 2.627E+06 1.149E+06 5.547E+02 2.758E+07 CE-144 7.776E406 8.032E407 1.209E+08 4.928E408 1.112E+10 PR-143 2.808E405 0.000E400 6.923E+05 9.204E407 2.748E408 PR-144 1.016E403 2.112E+03 6.716E-54 0.000E+00 3. 303E-26 ND-147 2.208E+05 1.009E407 5.231E405 3.935E+07 1.853E+08 W-187 1.552E405 2.740E406 1.796E406 5.912E400 1.046E407 2 NP-239- 1.192E405 1.976E406 7.385E+04 5.152E+03 2.872E407 Units: Inhalation 2and all tritium pathways - mrem /yr per pCi/m 3 Others - m , mrem /yr per pCi/sec Values based on standard NUREG-0133, Section 5.3.1 assumptions unless otherwise indicated.

l i

l 2.0-22 Draft

-- GRANO GULF, UNIT 1

! FfMT5719.48/SNLICFLR 1

+- . -,.,m. . - . _ . - _ _ . - - . . . . _ - , . . _ , , - . , - ~ , _ , , , . . . - - . _ _ _ _ , - . . - , , - , - , . , - . .

MOLLL2-3 .

00RIROLLINGECEEIOEJf *10E_MQJAlifen l

Distance Origin (for Sertor meteri) M1.lts** Ea.ttway Agt..Groun _.inf9anlyl I (A) N 1481 0.92 Vegetation Adult aarden I (0) NNE 1207 0.75 Vegetation Teenager garden (C) NE 1002 0.66 vegetation Teenager garden (D) FNE 4300 2.69 inha1/Gnd Plano Child- residence .

i (E) E 982 0.61 Inha1/Gnd Plano Adult residence

-(f) ESE 7000- 4.38 inha1/Gnd Plane Adult residence :

(G)SE 3100 1.94 Inha1/Gnd Plane Child residence (11) SSE 1800 1.13 Inha1/Gnd Plane Adult residence

-(J) S 805 0.50 Vegetation Child hypothetical

7 (K) $$W 3734 2.33 Vegetation Child garden (L) SW 1432 0.90 inha1/Gnd Plane Adult residence (M) WSW 8047 5.00' cow / Milk Infant hypothetical ,

(N) W ;8047 5.00 Cow / Milk Infant hypothetical {

(P)WNW 7680 4.80 Vegetation Child garden !

.(Q) NW 8047 5.00 Cov/ Milk Infant hypothetical

-(R) NNW 1207 0.75 Vegetation Child hypothetical

i i

Table based on 1986 Iand Use Census

These -locations represent GGNS gardens located inside the SITE BOUNDARY.

- Distance

shown are actual mileage in each sector. -

2,0-23 Rev. 11 - 06/88

'I

,. GRAND GULF, UNIT 1 ,

l EFMT5719.48/SNLICFLR I

{......-.-.---..--.-.-..-.-..--.-...--.---~~ - - _ - . - - - -

t f

f i

2.3 httatalogicalliedel 2.3.1 Atmo.spherjc_ Dispersion j i

lhe atmospheric dispersion for gaseous releases may be i calculated using a ground level, wake-split form of the f

straight line flow model.

X/Q = atmospheric dispersion (sec/m')

i 2JLLL i rut where.

r e distance (m) from relesse point to location of ;

t interest [-

6 =- plume depletion factor at distance r from

Figure 2.3-1 u .= wind speed at ground level (m/sec) {

i k = open terrain recirculation factor at distance r, j from page 2.0-34 .

I- a the lesser of (c' +-b')b-or- I3 o f; v

i where:

o = vertical standard deviation (m) of the plume at [

i distance r for ground level releases under the .!

stability category indicated by T, from Figure [

t 2.3-2 ,

=

T temperature differential with vertical

]

separation (*K/100m) f l

b = height of the reactor building = 53.3m !

2.0-24 Draft ;

GRAND GULF, UNIT 1 -[

EFM15719,4B/SNLICFLR !

2.3.2 Deposition Relative deposition per unit area for all releases is calculated for a ground level release as follows:

D/Q = relative deposition per unit area (m-2)

=

LM (D 9) r-where:

O g

a relative deposition rate at distance r for ground level releases from Figure 2.3-3 i

l l

l^

L l

l 2.0-25 Draft GRAND GULF, UNIT 1

.EFMI5719,48/SNLICFLR

IABLL2d-1 MtcSftlERILDLSKRS10RfARMEERS* FDILAffE01XJLREQUIREMENIS

.4JL21LLadL2.2diL2m3. A uAid SEC10R ** MILES XLQ DLQ (A) N 0.92 1.333 x 10-6 5.485 x 10'9 (B) NNE 0.75 1.129 x 10-6 5.298 x 10'9 (C) NE 0.66 9.373 x 10'7 5.821 x 10'9 (D) ENE 2.69 7.358 x 10'O 4.341 x 10-10

-7 (E) E 0.61 8.618 x 10 5.135 x 10 -9 (F) ESF 4.38 3.206 x 10-8 1.824 x 10-10 (G) SE 1.94 2.628 x 10'7 1.474 x 10'9 (H) SSE 1.13 7.347 x 10'7 3.587 x 10~9 (J) S 0.50 4.057 x 10-6 1.408 x 10'8 (K) S$W 2.33 4.022 x 10-7 8.232 x 10-10 (L) SW 0.90 2.653 x 10-6 4.463 x 10~9 (M) WSW 5.00 3.931 x 10'7 3.177 x 10-10 (N) W 3.00 4.259 x 10-7 3.746 x 10-10 (P) WNW 4.80 3.164 x 10*7 3.739 x 10-10

~7 (Q) NW 5.00 1.584 x 10 2.733 x 10-10 (R):NNW 0.75 2.199 x 10-6 7.650 x 10'9

Reference:

Grand Gulf Nuclear Station, Final Environmental Report, Table 6.1.26. 6.1~.28, 6.1.29 and ODCM Table 2.2-3. _

Distances shown are actual miles in each sector. In those cases where X/9 and D/Q were not available from FER Table 6.1.26, they were taken from FER Tables 6.1.28 and 6.1.29 using the closest distance interval to the plant.-

2.0-26 Draft GRAND GULF, UNIT 1 EFMT5719.48/SNLICFLR

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

i 2.4 Del 101Li.011Luf_G u cF ILELfh e r1LLE mmelm b a height of reactor building (m) (2.3.1)

C = count rate of the station vent monitor corresponding to grab sample radionuclide concentrations (2.1.1) l l

C' a count rate of station vont monitor corresponding to a 1.0 i pCi/ml concentration of-Xe-133 (2.1.2)

D = relative deposit l 9- Figure 2.3-3(m'jonrateforgroundlevelreleasesfrom

) (2.3.2)

Dg = average nrqan dose rate in current year (mrem) (2.2.1.b)

D e dose to an individual from radioiodines and radionuclides in P

particulate form, with half-life greater than eight days (mrem) ,

(2.2.2.b)

D, = average skin dose rate in current year (mrem) (2.2.1.a) ,

D tb

= average total body dose rate in current year (mrem) -

(2.2.1.a)

D = air dose due to beta emissions from noble gas radio-O nuclide 1 (mrad) (2.2.2.a) ,

D, a air dose due to gamma emissions from noble gas radio-nuclide 1 (mrad) (2.2.2.a)

D/Q = relative deposition per unit area (m-2) (2.3.2) o = plume depletion factor at distance r for appropriate stability class and effective height from Figures 2.3-2 and 2.3-3 (2.3.1)

F n fraction of current year elapsed at time of calculation (2.1.1) k = open terrain recirculation factor at distance r from Figurn 2.3-1 (2.3.1)

K = total body dose f actor for 3Kr-89, the-most restrictive isotope (mrem /yr per pCi/m ),-from Table 2.1-1 (2.1.2)

Kj =

totalbodydosefactorduetg)gammaemissionsfrom isotope 1 (mrem /yr per pCi/m- from Table 2.1-1 (2.1.1) 2.0-27 Draft GRAND GULF, UNIT 1 EFMT5719.48/SNt1CFLR ;

E

i l

2.4 Daf.if1111001. ALG ERQUA.Elfheldi.hranchtL( CDAlifw ed.1 i i

0 7g = limiting dose rate to the total body based on the limit [

of 500 mrem in ona year (2.1.1) [

1 0, e limiting dose rate to the skin based on the limit of 3000 mrem 3 f in one year (2.1.1) -i L = skin dose factor for Kr-89, the most restrictive isotope (mrem /yr per pCi/m') from Table 2.1-1 (2.1.2)

L 4

m skin dose factor due to beta emissions from isotope i (mrem /yr per pCi/m'), from Table 2.1-1 (2.1.1) j i

M- = air dose factor for Kr-89, the most restrictive isotope (mrad /yr per pCi/m') from Table 2.1-1 (2.1.2)

~M 4

= air dose factor due to gamma emissions from isotope 1 (mrad /yr .

per pCi/m8 ) from Table 2.1-1 (2.1.1) l

?

N-g = air dose factor due to beta emissions from noble gas-radionuclide 1 (mrad /yr per pCi/m ) from Table 2.1-1 (2.2.2.a) 8 p = dose parameter for radionuclide i, (mrem /yr per pCi/m ) for 8 g

f inhalation from (m'

mrom/yr per pCi/sec) for other pathways,

{

from Table 2.2-1-(2.2.1.b) {

O'g = rate of release of noble gas radionuclide 1 (pCi/sec) (2.1.1) f 5

Q'4

=- average release rate for the current year (pCi/sec) of isotope !

i of tritium, I-131, 1-133 or other radionuclide in particulate i I' form, with half-life greater than eight (8) days (2.2.1.b) i I

L ;

l i 2.0-28 Draft l

!= GRAND GULF, UNIT l' ,

l DOC l p

t

~ . - . _ . . - . _ - -- - - . , . . - - _ _ - , - - - . ,- -- :

2.4 DeLinitionLpLO auttau tilflus o tilaraticrLICatinyed)

Og a cumulative release of radionuclide i of noble gas, tritium, 1-131, 1-133, or material in particulate form over the period of interest (pC1) (2.2.2.a) (2.2.2.b)

{= assigned release rate value of, for nample, 1.0 pCi/sec, Xe-133; related to definition of C' for the vent (Note 3)

R 4

= dose factor for radionuclide i, (mrem /yr per pCi/m') or (m2

mrem /yr per pCl/sec)

R 3

= count rate per mrem /yr to the skin (2.1.1)

R g

= count rate per mrem /yr to the total body (2.1.1)

R"3

= conservative count rate per mrom/yr to the skin (2.1.2)

R"t

= conservative count rate per mrem /yr to the-total body (Xe-133 detection. Kr-89 dose) (2.1.2) r *-- distance-(m) from release point to location of interest for dispersion calculation (2.3.1) i p

2.0-29 Draft GRAND Gulf, UNIT 1 EfMT5719,48/SNLICFLR

. p J, ..

v;[s .4 DCf jaillRnLQ.f_aaies.uaf_uviui.oratemeier_tcr2011auee)

(, -

3 idh . ,

S y

- count rate of station vent noble gas monitor at alarm setpoint Zf level (2.1.1)

%-V f.

+ F "

=

sticci standard deviation of the plume with building wake

v arrection (m) (2.3.1) r;$ .

Q% 7-rk;

"- endard deviation (m; of the plume at distance r foe

, 3 o = vertical

$s@/.

g

[ ,

effective height under stability cateoory indicated by T(m) 1 ,y from Figure 2.3-2 (2.3.1)

%. ) .

- T = temperature differential with vertical separation ( V/100m)

}- (2.3.1) f; - u r wind speed at ground level (m/sec) (2.3.1)

W = controlling sector annual average atmospim - dispersion at the site boundar" 'or the appropriate pathwai 'ec/r$) (2.2.1.b)

W' =

relative concentration for unrnstrictea areas (sec/m ) 8 (2.2.2,b)

X/Q = atmospheric dispersion (sec/m ) (2.5.1) 8 E= highest sector annual average atmospheric dispersion at the unrestricted area boundary (sec/m8 ) (2.1.1)

X/Q' s re;etive concentration for unrestricted areas (sec/m ) 8 (2.2.2.a) 2.0-3C Draft '

I GRAND GULF, UNIT 1 EFMT5719.48/SNLICFLR

figure 2,3-1 Plumt_ Depletion Effect7 di dFound-Level Releases (All Atmospheric Stability Classes) ev i

l

- -s' / g

__ / o

/

_- /

)

-. _ / '

/

N -

E E a M C

- /

o,

g

/ 3d U / E E / -- w k / W e l 5 m

a

.i.

/ g E <

- - g i E 5 B j i

o. h e L

_ i

. I _. ,

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l J .

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o o e.

N

m w n. *1 e.

e o o o a o o' o o a 3Wn*1d NI DNINIVW3B NOI.L*)VWt 9 2.0-31 Draft CRAND GULF, UNIT 1 f" Mis 719.48/SNLICFLR

Fig 9re 1 3-2 Vertical Standard Deviation of Material in a Plume (letters Teii3Ee lisq'uIII 5 tai >iiitj~tlisi)~ ~

1000 , , -

r 1 i s

~~

l i /

/ / /

l ,/ / ,

e-

) ) \

/ y',

/

/ j E f / / /

5 /

w

., A

/

\

/ ,- /

/

~

N 100 1 i _

} s

/

7

/

/ '

s s s r B

c E

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f.B/ ;

/

_/ #

u / f___ / / / /~s

$* / / / /

A

$ f // 'Of/ s

'~

s' 0

/./>/ > / / / > /

e ,

c E '

N

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g 10 i .

,/ /

/ /

G w s s s s /

s s / /

/ / / /

/ / /

l , /

/, / \

/

3

. \..-

0.1 1.0 10 100 ;

r. PLUME TAAVEL DISTANCE hiLOMETERS)

Temperature Change *asquill Stability with Hei-ht (t)(*K1100 m) Categories Classification

<-1.9 A Extremely unstable

-1.9 to -1 7 8 Moderately unstable

-1.7 to -1.5 C Slight,y unstable 1._ to -0.5 D Neutral

-0.5 to 1.~ [ Slightly stable l 1.5 to 4.0 f Mooerately stable l > 4.0 G [ stremely stable 2.0-32 Draft GRAND GULF, UNIT 1 l EFMT5719.48/SNLTCFLR

Fi

, .Relativ.e D.epositio.gure A 3-3 n for Groun.d L.ev.el. Releases- --

10*3 -

10-4 \

x ^ y E _

W ,

& % w l

r \

U N

\

.=- 3s

.e s

$ 10-5

\

E _

\

~

N

's y =

s l P N 5 \

w \

". \

8 10-6 \

3 3

10-7 0.1 1.0 10.0 100.0 200.0

r. PLUME TR AVEL DISTANCE (KILOMETERS)

Graph taken fiom Reference 7, Figure 6 '

2.0-33 Draft l GRAND GULF, UNIT 1 EFMT5719.48/SNLICFLR ;

t t-

_v- .

Figure 2,3-4 !

Open.TerraIE hicI7iulition r Factor l

,8

)

4

.)

~- , e W /

6 _

/ -

..& / -a w or-

/ =

- s

/ w

/

w g t

w- r

/ s 5

T a

W-u

_.__.. 2 i E- / '

u

%=-

( y c 0 o /

.ar 6 e o

a

. i.

b as

~

l o i n

, o -

^

M d W013Vd NOll33WW03 '4 2.0-34 Draft

. GRAND GULF, UNIT I EFMI5719.48/SNLICFLR

2.5 Galenul_Radwaste Trealtent_Sm lem The instruments required to be_ checked by Appendix A Requirement 3/4.11.2. asure that the GASEOUS RADWASTE TREATMENT (Offgas)

SYSTEM is functioning are:

1. Absorber train bypass switch (IN64-HS-M611)

2. Bypass valve indication (IN64-F045)

When the absorber train bypass switch is in the TREAT position and the bypass valve indicates closed, the GASEOUS RADWASTE TREATMENT (Offgas)-SYSTEM is functioning.

ROIES for Fiaure 2.5-1 A flow diagram for the Gaseous Radwaste T eatment System is provided -

on the following page. Notes for the diagram are listed below.

(1) The charcoal beds are bypassed during startup unt ~ an adequate dewpoint is obtained in the process stream.

(2) This pathway may be utilized for power levels s 5%.

(3) Standby Gas Treatment System not normally operated.

4 l

4 L i l~

+

2.0-35 Draft i

GRAND GULF, UNIT 1 i EFMT5719.48/SNLICFLR

fl9Ur.12di A GaleDERadgaste TreAlmeRLiv>1em * ' 4 '*

.-~. b ....

,~. - ~

,AA0!Atim'i 4

e este - is e mass uw tu l\ finaq*,

ed ' \'*!*/

8,,",,",, / %* _,_

CC '-

Q.'

$* . utfmc

~ ~ ' ~

M

!N supune,rarm er a mp un n orac7tv,

< m us ;

e - / mareer ;

a mm !

l IBM. M. Map 5 l

- - a mm N M O l _

s e r i :

I e I

i !

~

"""." : rat = l

{ M S rE'm E.d - l i

f I

I I -to j atismes :

! d I-i p am

-,NN-r twenn m _ ea ewona en i i term _ Pam ram _

mE_~ ram !

,g

- (* MLDrus - >

"Ed"" i lanounid, ==

iman <# .

nn."'-W' .-- 's . ,

lb d-to attesmou .

(an*/ A wmu ,, rn* maam ' r T a - meano ,

a i

... ... to ainemeu 4 am.m.ar -.

- > = = Qa,E,,,',3""'

e g

u mm.t.

p P8s mm m* .*

ounceu s.

,i,ETm

,d

}

-:--* lamu M i l \=**/ !

l l l is ansames i l

e ,'

a sTment ans i 88u *a owram,_,1 8'* ;

mm _

ram _

am tram Tiaatiert a

, }

, - su m m ar m :

lanm4M er a e un- !

an . nm. e \===/ ..,"

2.0-35a Draft i GRAND GULF, UNIT 1 !

EFMT5719.48/SNLICFLR i i

a w -

2.6 AnnwLl_DR5LComaLimtat For the purpose of implementing Appendix A Requirement 3.11.4. the-annual-(calendar year) dose or-dose commitment to any MEMBER OF THE

=PUBLIC-will be rt.;culated by summing the following doses for the calendar year:

Direct radiation dose Liquid officent dose (Diau) !

Noble. gas dose (Dg , Dg )

Particulate dose (Dp )

These calculations tre required only if the liquid or gaseous effluents exceed twice the limits of Appendix A Requirements

-3.11.1.2.a, 3.11.1.2.b, 3.11.2.2.a, 3.11.2.2.b, 3.11.2.3.a, or 3.I1.2.3.b.

2.6.1 DJutttJLa&Liptuoic_tieasmsment

-Appendix A. Requirement 3.11.4 requires the determination of cumulative dose contributions to a MEMBER OF THE PUBLIC from direct radiation from the reactor units and from radwaste storage tanks. This requirement-is applicable-only under conditions set forth in Appendix A Requirement 3.11.4 Action a. This determination is made by the ut:litation of direct radiation measurements from indicator thermoluminescent dosimeters 's) located near the GGNS property 1ine in each of the 16 meteorological sectors.

J 2.0-36 Draft GRAND GULF, UNIT 1 EFMI5719.48/SNLICFLR

_ . _ - _ _ __ _ _ _ - . _ . . . . . _ _ _ . _ _ _. m. . . . _ . - _ . _ . _ _ _ _ . _ _ . _ .._

4 I

l

)

Measurements from these_TLDs represent the direct adiation generated by the facility plus normal background ;

iation, The locations are identified in Table 3.0-3 by the following TLD numbers:

M-16 M-22 M-41 M-86 M-18 M-25 M-42 M-92 M-19 M-27 M-44 M-93 M-21 M-28 -M-45 M-94 -

Control TLDs are also utilized to differentiate between background radiation and direct radiation from the facility. The following seven TLDs are designated as controls based on the criterion that they are located ten miles or greater.from the facility.

Exact locations are identified in Table 3.0-3.

M-06 M-12 M-14 M-39

-M-11 M-13 M-33 The difference between the averaged _ quarterly radiation measurements of the indicator TLDs,and the control TLDs-represents the direct radiation dose to a MEMBER OF-THE- '

- PUBLIC from the operating facility.

2.0-37 Rev. 10 - 12/86 e

~

GRAND GULF, UNIT 1.

EFMT5719.48/SNLICFLR

3.01 R&QLQLOGICAL- ENVIRONMENTAL MONITORING 3.1- Sa_mpling Locations Sampling locations for the GGNS Environmental Surveillance Program -

5 are described in Tables 3.0-1 through 3.0-3 and shown-on maps in Figures 3.0-1 through 3.0-3. Those sampling locations required to fulfill the

? requirements of Appendix A Requirement 3/4.12.1, as described in Appendix A Table 3.12.1-1, are identified with an asterisk-in Tables 3.0-1 through 3.0-3. The types of vegetation and fish which are normally available for sampling are identified in Tables 3.0-4 and 3.0-5, respectively, f

f y

j .-

l i

e i

6 1

3.0-1 Draft

. GRAND GULF' UNIT 1 ,

EFMT5719.48/SNLICFLRL

. f i

JABLE_l a.1 _ ;

AIR SAMPLER CHLLECTION SITES i

AIR SAMPLEBE l

HIEaER EIGURE LOCAI10N l

AS-1 PG 3.0-3 Southeast of GGNS at the Port Gibson City Barn !

(Sector G Radius 5.5 miles) j AS-2 61N 3.0-2 North-northeast of GGNS on Hry 61, across from i the Yokena Church (Sector B Radius 13 miles) !

AS-3 61VA 3.0-2 North-northeast of GGNS on Hwy. 61, north of the <

Vicksburg Airport (Sector B Radius 18 miles) l>

AS-4 GJOE 3.0 1 Southwest of GGNS, Glodjo property on Bald Hill i Road (Sector L Radius 0.9 miles) .;

t AS-5 TC 3.0-1 ' South of GGNS behind the Support Services Center l (Sector J Radius 0.4 miles) j

AS-6 RS 3.0-1 Northeast of GGNS, south side of Grand Gulf l Road (Sector C Radius 0.5 miles) .

AS-7 MT 3.0-1 North of GGNS, located next to the Meteorological Tower (Sector A Radius 0.8 miles) !

t

AS-8 WR 3.0-1 East of GGNS, located at former site of Maggie !

Jackson's trailer on Bald Hill Road near the 9 eastern SITE B0UNDARY (Sector E Radius j 0.6 miles) l AS-9 GGMP 3.0-1 North of GGNS, located in Grand Gulf Military-Park (Sector A Radius 1.5 miles) !

AS-10-NLT 3.0 West-northwest of GGNS, located at Newellton, '

Louisiana (seetor P Radius 12.5 miles) j AS-11 STJ 3.0-3 West-southwest of GGNS, located at St. Josech, !

Louisiana-(Sector M Radius 13.0 miles) !

r ;

L

Appendix A-Requirements lc 1;

7 3.0-2 Draft j GRAND GULF, UNIT 1 EfMT5719.48/SNLICFLR h

= - -. .-

i i

?

IABLE_3.0-2 l MISIELLA!fE0VS COLLEGIl01LSilfS ,

Page 1 of 3 l

Mll.JLSAMP.LES (CONTROL _LOCAJ1010 ElGURE Alcorn State University

3.0-3 Located south-southwest of GGNS '

(Sector K Radius 10.5 miles) ;

i E1 STERN W&lE8

{

1. McGee Cistern

3.0 Located north of GGNS at the McGee house (Sector A Radius 0.9 miles)

2. Willis Cistern

3.0-3 Located at the C. E. Willis house east-northeast of GGNS across from the Shiloh Baptist Church '

(Sector 0 Radius 6 miles)

GRQD.fla MAIER

1. PGWELL* 3.0-1 PORT GIBSON WELLS - Taken from ;

distribution system or one of the five wells (Sector G Radius 5.0 miles)

2. AAWELL* 3.0-1 Arnold Acres Trailer Park, ;

inactive (Sector J Radius 1.1 ,

miles) ,

3. LAKE BRUIN 3.0-3 Taken frcm faucet at the bath -

house in Lake Bruin Statt Park, !

Louisiana (Sector M Radius 9.5 '

miles) l

Appendix A Requirements i

?

3.0-3 Oraft

-GRAND GULF, UNif 1 EFMT5719.48/SNLICFLR

1ADLE 3.0.-2_1Csntiondl MUiCELIMEQULCOLLEC110fL111ES Page 2 of 3 TVREAC D AIIB ELGURE Upstream

3.0-1 4500 ft upstream of the GGNS discharge point into.the Mississippi River to allow adequate mixing of the Mississippi:and Big Black Rivers (Sector Q)

Downstream " 3.0-1 5000'ft downstream of the GGNS discharge point into the Mississippi River near Radial Well No. 1 (Sector N)

Discharge-Basin

3.0-1 West-northwest of GGNS in parking lot (Sector P, 0.3 miles)

YEGEIAUDN Broadleaf Vegetation

3.0-1 South of GGNS near the Support Services Center (Sector J, 0.4 miles) and north-northwest of GGNS near the Meteorological Tower-(Sector R, 0.8 miles)

The above locations are gardens maintained by GGNS inside the SITE I llRIE:

BOUNDARY in order to provide a more conservative calculation of doses due to the potential ingestion of contaminated vegetation. These two sampling sites exceed the requirements-of Appendix-A Requirement 3.12.1.

Alcorn: State University _

south-southwest of GGNS (Sector -

K, 10.5 miles) when available, othorwise a_ location _15-30 km distant L EIStL16MP1ES

. Commercially or- Downstream of the GGNS discharge recreationally important point into the Mississippi River species

Upstream of t.he GGNS' discharge .

point into the Mississippi River uninfluenced by plant operations

-Appendix A Requirements 3.0-3a Draft GRAND GULF, UNIT 1 EFMI5719.48/SNLICFLR e

JADLE1Q:LLConullMO BJ1CELLANEQULC01LECILOLSIIES Page 3 of 3 1EDlMENLS&MP1E5 EIAURE SEQll4}]* 3.0-1 Downstream of the GGNS discharge.

point into the Mississippi River in the vicinity of the boat landing near-liamilton Lake outfall (Sector N, 2 miles)

- SEQBA8 3.0-1 Barge slip (Sector Q, 1,5 miles)

SEDCONI 3.0-1 Upstream from the GGNS discharge point.into the Mississippi River in the vicinity of Upper Grand-Gulf Landing (Sector R, 2 miles) t i

l l

l'

-

llamilton Lake outfall is an Appendix A Requirem;mt 3.0-3b Draft GRAND GULF,-UNIT 1 EFMT5719.48/SNLICflR-

16BLE 3.0-3 ILD_LQCA110RS j Page 1 of 7 ILDJ01 LQC.AILON ElGV.RE SEC10B tilLE

]

M-00 Maintained in lead shield - - -

during the_ exposure period !

i M-01 Across the road from the Lake 3.0-3 5 3.5 Claiborne entry gate M-02 Windsor Ruins entry gate 3.0-3 L 7.0 M-03 Ilwy. 61 across from 3.0-3 ll 7.0 i P.G. Country Club entrance ;

M-04 Hwy. 547-between twin power poles 3.0-3 G 6.5 j M-05 Hwy. 18, 5 miles east of Ilwy. 61- 3.0 F 9.0 ;

i !

M-06' REA pole east of Willows beyond- 3.0-3 0 10.0 -!

Campbell Church, Miss. Hwy. 462

M-07 Port Gibson City Barn, AS-1 3.0-3 G 5.5- !

I M-08 West side-Big Black. River, 3.0-3 C 8.5 ,

south entrance i M-09 Tree adjacent to Warner 3.0-3 D 3.5 !

Tully Camp entrance

! -* M-10 Grand Gulf Military Park entrance' 3.0-1 R 1.5 .

gate ;

i M-11 Ilwy. 61, 3 miles north of 3.0-3 _C 10.5 Big Black River at twin tower .

t. r M-12 Hwy. 61 at AS-2-61 across from 3.0-2 B 13.0 l Yokena Church :

M-13 West side of Hwy. 61, Letourneau 3.0-2 8 15.0 <

Hill I

?

Appendix'A Requirements '

r I

I b

l 3.0-4 Draft {

GRAND GULF, UNIT 1 '

-EFMT5719.48/SNLICFLR i

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

IABLE 3.0-3 (.C.catinuedl ILD 10 Call 085-Page 2 of 7 ILD_RO. 1.QCAUDN EIGURE 1ECIDB MILE

M-24 Hwy. 61, AS-3-61VA, north of 3.0-2 B 18.0 (CONTROL) Vicksburg Airport M-15 Barge slip (south edge) 3.0-1 P 1.5

M-16 AS-7 MT, Meteorological Trwer 3.0-1 A 0.8

-M-17 AS-6-RS, Grand Gulf Road 3.0-1 0 0.5

M-18 ;Former railroad crossing eastern 3.0-1 F 0.5 SITE BOUNDARY-M-19 Behind burn pit on fen;e at 3.0-1 E 0.5 eastern SITE BOUNDARY M-20 Eastern SITE BOUNDARY behind 3.0-1 F 0. 5 -

hazardous waste storage area M-21 AS-5-TCi Support 3ervices Center 3.0-1 J 0.4 M-22 100 yards south of. former RR 3.0-1 G 0.5 entrance crossing on west side M-23 County Road / Heavy Haul Road 3.0-1 Q 0.5

50 yards north on power pole M-24 ' Upper Grand Gulf Landing 3.0-1 R 2.2

=";M-25 Hamilton Lt.ke-boat launch- 3.0-1 N 1.0 M-26 Hamilton Lake outfall 3.0-1 N 1.5-

M-27 South point SITE BOUNDARY 3.0-1 M _1. 5 200 yards along property line .

M-28 - AS-4-GJOE, Glodjo - residence 3.0-1 L 0.9

'M In sharp curve of-. Waterloo Road 3.0-1 K 1.5 to Waterloo-Plantation

M-30 Arnold Acres Trailer Park (inactive) entrance 3.0-1 J 1.1

Appendix A Requirements 3.0-5 Draft GRAND GULF, UNIT 1 EFMT5719.48/SNLICFLR i'

3 , , . . - - . - . , , ~ , , . __ . . - _.-._,,,___..m,- ..__, ,_.... __,,... __..,._- .,c_. -- _ - - . _ _ .

. .. . - . . ~ ~ .. . . - - ..- - -. - - - ~ - - - . ~. - - - .

t I

16BLE 3.0-3 {. Continued). -

ILDJRCA110HS Page 3 of 7 l

~ ILD_X01 LOCA110B ElftllRE 1EC103 MILE l

M-31 Ouplicate TLD installed - - -

. quarterly at varying locations l l

M-32 Duplicate TLD installed - - -

l quarterly at varying locations 'l

)

M-33 Newe11 ton, Louisiana, Water .

3.0-3 P 12.5 l Tower j t

M-34 Levee at end of County Road at- 3.0-3 R 8.0 i Point Pleasant, Louisiana M-35 Amacker Landing - Lake Yucatan 3.0-3 Q 8.0 J M-36 Curve on 608, point nearest 3.0-3 P !, . 0 i GGNS at power pole !

M-37 Winter Quarters Home 3.0-3 N 8.0 f

'* M-38. Lake Bruin State Park, 3.0-3 M 9.5 I second pole :

M-39 St. Joseph, Louisiana, Aux. 3.0-3 M 13.0 t

' Water Tank i e

M4fl Fnternational Paper Road, 3.0-3 M 5.0 [

6 miics from site l

M-41 Heavy Haul Road - J pipe 3.0-1 P 1.0

on concrete block '

M 4P tiaavy Haul Road north iron gate 3.0-1 Q 1.C.

f

M*43 Gi1 Lake entrance 3.0-1 p, R 1.2 Truck bypass on Grand Gulf Road '

M-44 3.0-1 C 0.5 M-45 Old Visitor Center gate 3.0-1 0 0.5 f l

Appendix A-Requirements 3.0-6 Draft $

i GRAND GULF, UNIT 1 t EFMT5719.48/SNLICFLR

m . _ . . . _ _ _ _ . . _ . . _ . _ . _ _ _ . _ _ . _ __ _ . _ . _ . . . . _ -.._ .__ _ _

g IAELE_LQ-LLC 011.thuedl ILD_LOCAIIDHS Pege 4 of 7 ILO_tlo LQCAIl08 ElGLIRE Sr;CTOR tilLE

M-46 Church yard across from-Grand 3.0-1 E 1.0 Gulf / Bald Hill Roads intersection

M-47 Bridge 0.6 miles west of Rodney 3.0-3 L 5.2

\!estside Road /Aont Gomer Road intersection, Morth side

M-48 .

Property line fence 0.4 miles 3.0-3 K -4.8 on Mont-Gomer Road on west side

M-49 Fork in Werthers Road 3.0-3 H 4.5

M-50 Panola Hunting Club entrance 3.0-3 B 5.5

M-51' Power pole 0.5 miles on gravel 3.0-3 C 4.8 road-to Big Black on west side

M Power pole, Bald Hill Road 3.0-1 K 1.0

M-53 Arnold-Acres property fence 3.0-1 11 1.1

-past inactive trailer park

M-54_ Bottom of curve past Arnold's 3.0-1 G 1.0 house

M Behind Bonner's-Beauty Shop 3.0-3 D 5.0

-at MSDli air sampler

M-56 Hwy. 61 at "All Creatures 3.0-3 G 5.0 Veterinary Hospital"

M-57 Ilwy 61, behind the Welcome 3.0-3 F 4.5 to Port Gibson sign at Glensdale Subdivision

M-58 Hwy, 61, Big Bayou Pierre bridge, 3.0-3 E 5.0 southeast end

M-59 Off levee at Winter Quarters 3.0-3 N 5.1 Hunting Camp

Appendix A Requirements 3.0-6a Draft GRAND GULF, UNIT 1 EFMI5719.48/SNLICFLR

i IABLE_.L 0-3_LContinuad i ILD_L0cAllDRS Page 5 of 7

-i ILO_.t102 LOCAll0N -ELGURE SEC108 MLLE M-60 Duplicate TLD installed quarterly - - -

at varying locations M-61 Protected area fence by the Not P Onsite vehicle entrance gate Shown M-62. Protected area fence northeast "

N corner parking lot M-63 Protected area fence middle "

N parking lot M-64 Protected area fence southeast "

M corner parking lot M-65 South protected area fence "

L behind warehouse M South protected area fence "

K across from cooling tower M-67 South protected area fence- "

J "

east end-M-68 East protected area fence "-

H across from chlorination tank: ,

M-69 East protected area fence near "

C electric bus

M North fence behind Turbine Bldg. "

F

-M-71 133' elevation railway bay "

-C - "-

M-72 133' elevation railway bay-B M-73 Corner of fence outside Control -"

P Bldg.

Appendix A Requirements 3.0-6b Draft GRAND GULF, UNIT 1 EFMI5719.48/SNLICFLR

t IABLE10-3 (Corttinuedl ILD_LO.CA110NS fage 6 of 7 _;

ILO._H02 LOCAlLOS ELOMRE SEC10E MLLE M-74 Midway of north fence Not P Onsite [

Shown l

M-75 Corner in fence in front "

A of Maintenance Shop i M-76 Sou+heast corner SSW Besins A

[

Protected area fence ., side " "

-M-77 R [

Maintenance Shop ;

M-78 Outside vault in Admin. Bldg. "

Q l

i M-79 Wall in Central Records (middle) Q ;

M-80 Wall in Central Records, old Q !

library location j i

M-81 Inside Admin. Bldg., 2nd floor, "

Q i

northeast wall j M-82 Tech Support area "

Q

" I M-83 Tech Suppert secretary's offic e "

-0 -"

l M-84 Security Island P f

M-85 Lee Electric Building across 3.0-3 G 5.2 ,

from Port Gibson liigh School '

M-86 Bechtel gate north SITE BOUNDARY 3.0-1 0 0.5 i

M-87 Intersection of Rodney Westside - 3.0-3 J 3.5 !

Road & transmission line M-88 River mile marker 409.5 . 3.0-1 A 4.2 l M-89 Middle Ground Island 3.0-1 R 4.4 L M-90 Across from Middle Ground Island 3.0-1 Q 3.5 :

Appendix A Requirements ,

3.0-6c Draft [

GRAND GULF, UNIT 1 EFMT5719.48/SNLICFLR

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ILD10CAIl0fiS Page 7 of 7 ILQ.Jf01 LQCAUDN flGURE SEC10B MJ.LE

Transmission line by pond M-91 3.0-1 J 4.5 M-92 Fence behind orchard Not Shown. K 0.4 M-93 Underground cable sign Not Shown 11 0.4 M-94 Sector R garden Not Shown R 0.8 Appendix A Requirements 3.0-6d Draft GRAND GULF, UNIT 1 EFMT5719,48/3NLICFLR

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JABLE_3.ad YEGETAT10.tUiABELE_iQURCES This table identifies the common names of vegetation sources which are normally available for broadleaf vegetation sampling-as required by Appendix A Requirement 3.12.1; however, this list is not considered all inclusive.

Beets Mustard Greens Box elder Oak Broccoli Pear l Cabbage Peas Cauliflower Pecans Clover _(red and white) Poplar

, Collards Potato l Corn Radishes l Cottonwood Rape

[ Cucumbers Rhubarb Elephant cars Skunk Cabbage s Honeysuckle Soy beans ;

Johnson grass Spinach !

Kale- Squash l Kudzu Turnip greens i Lettuce Vetch !

L Magnolia Watermelon -;

L Mayapple !

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3.0-10 Draft- 1 GRAND GULF, UNIT 1 EFMT5719.48/SNLICFLR i i

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16BLE 3.0-5 ELSIL5 AMPLE _S.01)EES This table identifies the common names of fish sources which are normally available

-for sampling as required by Appendix A Requirement 3.12.); however, the list is not considered all inclusive.

" lack bass Gar Breau Sturgeon Buffalo White bass Catfish White perch f

f 3.0-11 Draft

. GRAND GULF, UMIT 1 EFMT5719.48/SNLICFLR

4 2

i 0FFSITE DOSE CALCULATION MANllAL t

APPENDIX A !

RADIOLOGICAL EFFLUENT CONTROLS AND i RADIOLOGICAL ~ ENVIRONMENTAL MONITORING PROGRAMS }

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- EFMT5719,48/SNLICFLR _

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

i DEF_INITIONS ;

I

ACTION ;

1.1 ACTION shall be that part of a Requirement which prescribes remedial !

measures required under designated conditions. _

-CHANNEL CALIBRATION !

1.2 A-CHANNEL CALIBRATION shall be the adjustment, as necessary, of the channel output such that it responds with the necessary range and accuracy to known values of the parameter which the channel monitors. ,

The CHANNEL CALIBRATION shall encompass the entire channel including i the sensor and alarm and/or trip functions, and shall include the i CHANNEL FUNCTIONAL TEST. The CHANNEL CALIBRATION may be performed by any series of sequential, overlapping or total channel steps such that the entire channel is calibrated.

CHANNEL CHECK I 1.3 A CHANNEL CHECK shall be the qualitative assessment of channel behavior I during operation by observation. This determination shall include, '

where possible, comparison of the channel indication and/or status with other indications and/or status derived from independent instrument .

channels measuring the same parameter. {

f CHANNEL FUNCTIONAL TEST I 1.4 A CHMNEL FUNCTIONAL TEST shall be: (

a. Analog channels - the injection of a simulated signal into the !

channel as close to the sensor as practicable to verify OPERABILITY including alarm and/or trip functions and channel f'ilure trips. _j i

b. Bistable channels - the injection of a simulated signal into the i sensor to verify OPERABILITY including alarm and/or trip functions. {

l The CHANNEL FUNCTIONAL TEST may be performed by any series of i sequential, overlapping or total channel steps such that the entire channel is tested.

DOSE E_QUIVALENT I-131 !

1.5 DOSE EQUIVALENT I-131 shall be that concentration of 1-131, microcuries !

per gram, which alone would produce the same thyroid dose as the .!

quantity and isotopic mixture of I-131, 1-132, I-133, I-134, and I-135 j actually present. The thyroid dose conversion factors used for this ;

calculation shall be those listed in Table III of TID-14844, !

" Calculation of Distance Factors for Power and Test Reactor Sites." !

FREQUENCY NOTATION l 1.6 The FREQUENCY NOTATION specified for the performance of Surveillance i Requirements shall cor espond to_the intervals defined in Appendix A )

Table 1.1. .i l

i A-1 Draft l i

GRAND GULF,-UNIT 1 i

EFMT5719.48/SNLICFLR j

-j

l SYSTEM ,

-D GASEOUS The GXS$60f RA0 WASTE RA0 WASTE TREATMENT (0FFGAS)T TDRGAS) SYSTEM is the s!

TREA~1R$N and installed to reduce radioactive gaseous effluents by collecting primary coolant system offgases from-the primary system and providing_

for delay or holdup for the purpose of reducing the total radioactivity prior to release to the environment.

MEMBERIS) 0F THE PUBLIC 1.8 MEMBER (S) 0F THE PUBLIC shall include all persons who are not occupationally associated with the plant. This category does not include employees of the utility, its contractors or vendors. Also excluded from this category are persons who enter the site to service equipment or to make deliveries. This category _does include persons who use portions ~of the site for recreational, occupational or other purposes not associated with the plant.

OFFSITE DOSE CALCULATIONJANUAL_(ODCM).

e 1.9 The OFFblTE DOSE CALCULATION MANUAL (ODCM) shall contain the methodology and parameters used in the calculation of offsite doses resulting from radioactive gaseous and liquid effluents, in the calculat_lon of gaseous and liquid ef fluent monitoring Alarm / Trip Setpoints, and in the conduct of the Environmental Radiological Monit_oring Program. Ina ODCM shall also contain (1) the Radioactive Effluent Controls and Radiological Environmental Monitoring Programs required by Technical Specification 6.8.3 and (2) descriptions of the information that should be included in the Annual Radiological

-Environmental Operating and Semiannual Radioactive Effluent Release

. Reports required by Technical Specifications 6.9.1.6, 6.9.1,7, 6.9.1.8 and 6.9.1.9.

O_P_ERABLE - OPERABILITY 1.10 A system, subsystem, train, component or device-shall be OPERABLE or have OPERABILITY when-it is capable of performing i_ts specified function (s) and when all necessary attendant instrumentation, controls, electrical power, cooling or seal water, lubr kation or other auxiliary equipment that are required for the system, subsystem, train, component i or device to perform its function (s) are also capable of performing E their related support function (s).

OPERATIONAL CONDITION - CONDIT:0N 1.11 An-0PERATIONAL CONDITION --i.e., CONDITION, shall be any one inclusive combination of mode switch position and average-reactor coolant temperature as specified in Appendix A Table 1.2.

l PROCESS CONTROL PROGRAM (PCP) 1.12 The PROCESS CONTROL PROGRAM (PCP) shal_1 contain the current formulas, samplings analyses, test, and determinations to be made to ensure that processing and packaging of solid radioactive wastes based on

' demonstrated-proces' sing of actual or simulated wet solid wastes will be accomplished in such a way as.to assure compliance with 10CFR Parts 20, 61, and 71, State regulations, burial ground requirements, and other requirements governing the disposal of solid radioactive waste.

t A-2 Draft GRAND GULF, UNIT 1 EFMI5719.48/SNLICFLR

,. . _ - . . - . - ~ _ _ . - . - - - . - - - . . . - _ - . - _ - . - . - - - . . . _ - _ . .

i RATED-THERMAL POWER -

1.13 RATED THERMAL POWER shall be a-total reactor core heat transfer rate to !

the reactor coolant of 3833 MWT. t i

SITE BOUNDARY i J,Til~ihT 5 lie BOUNDARY shall be that line beyond which the land is neither !

owned, nor leased, nor otherwise controlled by the licensee. j SOURCE CHECK 1.15 A SOURCE CHECK shall be the qualitative assessment of channel response j when the channel sensor is exposed to a radioactive source. ;

i THERMAL POWER F 1.16 THERMAL POWER shall be the total reactor core heat transfer rate to the - i reactor coolant. }

i UNRESTRICTED AREA l 1.17 An UNRESTRICTED AREA shall be any area at or beyond the SITE BOUNDARY i,

access to which is not controlled by the licensee for purposes of- l protection of MEMBERS OF THE PUBLIC from exposure to radiation and ;

radioactive materials, or any area within the SliE BOUNDARY used for residential quarters or for industrial, commercial, institutional, l and/or recreational purposes. [

r VENTILATION EXHAUST TREATMENT SYSTEM {

1.18 A VENTILATION EXHAUST TREATMENT SYSTEM is any system designed and j installed to reduce gaseous radiciodine or radioactive material in r particulate form in effluents by passing ventilation or vent exhaust !

gases through charcoal adsorbers and/or HEPA filters for the purpose of i removing iodines or particulates from the gaseous exhaust stream prior '

to the release to the-environment (such a system is not considered to have any effect on noble gas effluents), Engineered Safety Feature ,

(ESF) atmospheric cleanup systems are not considered to be VENTILATION !

EXHAUST TREATMENT SYSTEM components. }

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GRAND GULF, UNIT 1 -!

I EFMI5719.48/SNLICFLR f i

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

s

-lABLE_1t1 SURVEILLANCE FREQUENCY NOTATION NOTATION FREQUENCY S tt least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months , ,

D At least-once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

W At least once per 7 days, M ,At least once'per 31 days..

Q At least once per 92 days, SA At least once per 184 days, A At least once per 366 days, R At least once per 18 months (550 days).. -

L S/U Prior to each reactor startup, N.A. Not applicable.

P Completed prior to each release, l

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A-4 Draft GRAND GULF, UNIT 1 EFMT5719.48/SNLICFLR -

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i TABLE 1.2-l OPERATIONAL CONGITIONS -l i

MODE SWITCH AVERAGE REACTOR -l CONDl_ TION _ POSITION _ _C00_LANT TEMPERATURE- j

1. POWER OPERA 110N Run Any temperature

2. STARTUP Startup/ Hot Standby Any temperature

3. _ HOT SHUTDOWN Shutdown #,*** > 200*F

4. COLD SHUTOCWN Shutdown #,##,*** s 200*F i

5. REFUELING

Shutdown or Refuel **,# s 140aF i

-............................ i

-#- The reactor mode switch may be placed in the Run or Startup/ Hot Standby position- to test the switch interlock functions providt: '

s the control ,

rods-are verified to remain fully inserted-by a second licensed operator or '

i other technically qualified' member of the unit technical staff.

l

1. The reactor mode switch may be-placed in the Refuel-position while a single :

control rod drive is being removed from the reactoi pressure vessel per f

-_ Technical Specification 3.9.10.1. !

Fuel in the reactor vessel with the vessel head closure bolts less than i fully tensioned or with the_ head removed, j i

See Technical Specification Special Test Exceptions 3.10.1 and 3.10.3.

-l

- - - The reactor mode switch may be placed in the Refuel position while a single control rod is being moved provided that the one-rod-out interlock is ,

OPERABLE.

1 i

A-5 Draft .!

GRAND GULF, UNIT 1 !

EFM15719.48/SNLICFLR j i

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SECTIONS 3.0 AND 4.0 LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS 4..

A-6 Draft

i 3/4.0 APPLICABILITY- i LIMITING CONDITION FOR OPERATION !

3.0.1 Compliance with the Limiting Conditions for Operation contained in j the-succeeding Appendix A Requirements is required during the OPERATIONAL i CONDITIONS or other conditions specified therein; except that upon failure j to meet the Limiting Condition for Operation, the associated ACTION requirements shall be met.

3.0.2- Noncompliance with an Appendix A Requirement shall exist when the ,

requirements of the Limiting Condition for Operation and associated ACTION i requirements are not met within the specified time intervals. If the l Limiting Condition for Operation is restored prior to expiration of the i specified time intervals, completion of the Action requirements is not {

required. j i

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APPLICABillTY' SURVEILLANCE RE0VIREMENTS 4,0.1 Surveillance Requirements shall be met during the OPERATIONAL

-CONDITIONS or other conditions specified for individual Limiting Conditions for Operation unless otherwise stated in an individual Surveillance _ Requirement.

4.0.2 Each Surveillance Requirement shall be performed within the specified time interval with:

a, A maximum allowable extension not to exceed 25% of the surveillanco interval, but

b. The combined time interval for any 3 consecutive surveillance intervals shall not exceed 3.25 times the specified surveillance interval.

4.0.3 Failure to perform a Surveillance Requirement within the allowed surveillance interval, defined by Applicability Requirement 4,0.2, shall constitute noncompliance with the OPERABILITY requirements for a. Limiting Condition-for Operation. The time limits of the ACTION requirements are applicable at the time it is identified that a Srrveillance Requirement has not been performed. Surveillance Requirements do not have to be performed on inoperabis equipment- ,

4.0.4 Entry into an OPERATIONAL CONDITION or other specified applicable condition shall not be made unless the Surveillance Requirement (s) associated with the Limiting Condition for Operation have been performed within the applicable surveillance interval or as otherwise specified.

I t

A-8 Draft

-3/4.3 INSTRUMENTATION' 3/4.3.7 MONITORING INSTRUMENTAT103 RADI0 ACTIVE L10VID EFFLUENT MONITORING INSTRUMENTATION :

LIMITING CONDITION FOR OPERATION :

3.3.7.11 The radioactive liquid effluent monitoring instrumentation :

channels shown in Appendix A Table 3.3.7.11-1 shall be OPERABLE with their alarm / trip setpoints set to ensure thLt the limits of Appendix A Requirement 3.11.1.1 are not exceeded. The alarm / trip setpoints of these channels shall be determined in accordance with the OFFSITE DOSE CALCULATION MANUAL (00CM).

APPllCABILITY: At all times.

ACTION: l

a. With a radioactive liquid effluent monitoring instrumentation channel alarm / trip setpoint less conservative than required by t the above requirement, immediately suspend the release of radioactive liquid effluents monitored by the affected channel or declare the channel inoperable. l

b. With less than the minimum number of radioactive liquid :

effluent monitoring instrumentation channels OPERABLE, take i the ACTION shown in Appendix A Table 3.3.7.11-1. Restore the i inoperable instrumentation to OPERABLE status within the time :

specified in the ACTION and, if unsuccessful, explain why this +

inoperability was not corrected in a timely manner in the next Semiannual Radioactive Effluent Release Report, e

I SURVEILLANCE RE0VIREMENTS

---=-=---_ -------_----_-_-------_-------------------------------

-4.3.7.11 Each radioactive liquid-effluent monitoring instrumentation channel shall be demonstrated OPERABLE by performance of the CHANNEL :

CHECK, SOURCE CHECK, CHANNEL CAllBRATION and CHANNEL FUNCTIONAL TEST i

+

operations at the frequencies shown in Appendix A Table 4.3.7.11-1. !

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-TABLE 3.3.7.11-1' RADI0 ACTIVE LIOUID EFFLUENT MONITORING' INSTRUMENTATION MINIMUM CHANNELS INSTRUMENT OPERABLE ACTION

1. GROSS RADI0 ACTIVITY MONITORS PROVIDING ALARM AND AUTOMATIC TERMINATION OF RELEASE 1

a. Liquid Radwaste Effluent Line 1 110

2. FLOW RATE MEASUREMENT DEVICES 4

a. Liquid Radwaste Effluent Line 1 111

~

b. Discharge Canal or Circulating Water Blowdown 1 111

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r TABLE 3.3.7.11-1 (Continued) !

l RADI0 ACTIVE L10VID EFFLUENT MONITORING INSTRUMENTATION l ACTION STATEMENTS l t

i ACTION 110 - With the number of channels OPERABLE less than required by :

the Minimum Channels OFERABLE requirement, effluent ,

releases from this pathway may continue for up to 14 days [

provided that prior to initiating a release,

a. At least two independent samples are analyzed in i accordance with Appendix A Requirement 4.11.1.1.1, and i i

b. At least two technically qualified members of the !

Facility Staff independently verify the release rate i calculations and discharge line valving; l Otherwise, suspend release of radioactive effluents via ;

this pathway. !

t ACTION 111 - With the number of channels OPERABLE less than required by l the Minimum Channels OPERABLE requirement, effluent :

releases via this pathway may continue for up to 30 days i provided the flow rate is estimated at least once per ;

4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months during actual releases. Pump curves may be used to ;

estimate flow. l r

E v

l I

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i

[

A-ll Draft l

P

TABLE 4.3.7.11-1 RADIDACTIVE'LIOUID EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS I

CHANNEL i CHANNEL . SOURCE CHANNEL FUNCTIONAL.

INSTRUMENT. CHECK CHECK CALIBRATION TEST -i

1. GROSS RADI0 ACTIVITY MONITORS PROVIDING 't ALARM AND AUTOMATIC TERMINATION OF RELEASE-Liquid Radwaste Effluent Line

a. D P A(2) Q(1) i f

2. FLOW RATE MEASUREMENT DEVICES *

a. Liquid Radwaste Effluent Line D(3) N.A. -R Q i

b. Discharge Canal or Circulating Water ' Blowdown D(3) N.A. R Q S[

5.,

c 1 t

4 . -% 4 w ,r -

.,--*-2, . ew. -w -r- +w,,tv-5-wr-.-twa,-,,v e t- . wmor e n % -, ., ,,,,,,c--ww. nw..-.,w--www--r,-,,,_-.*w1.mu--w'v==em=*te-m+ e w ' w e r-s -w , r' w-e >+v w e - w e v - -* w-- +t'w*- --T--'*-

. .- - ~. - - - - . .

TABLE 4.3.7.11-1 (Continued)

RADI0 ACTIVE L10VID EFFLUENT HONITORING INSTRUMENTATION SURV(JLLANCE REQUIREMENTS TABLE NOTAi!ON (1) The CHANNEL FUNCTIONAL TEST shall also demonstrate that automatic isolation of this pathway and control room alarm annunciation occur if any of the following conditions exists:

1. Instrument indicates measured levels above the alarm / trip setpoint.

2. Circuit failure.

3. Instrument indicates a downscale failure.

4. Instrument controls not set in operate mode.

(2) The initial CHANNEL CALIBRATION shall be performed using one or more of the reference standards certified by the National Bureau of Standards or using standards that have been obtained from suppliers that participate in measurement assurance activities with NBS. These standards shall permit calibrating the system over its intended range of energy and measurement range. For subsequent CHANNEL CALIBRATION, sources that have been related to the initial calibration shall be used.

(3) CHANNEL CHECK shall consist of verifying indication of flow during periods of release. CHANNEL CHECK shall be made at least once per 24 hou s on days which batch releases are made.

h i

A-13 Draft f

, , -- - - ~ - -.

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

INSTRUMENTATIDH R&Q10 ACTIVE GASE0VS EFFLVENT MONITORING INSTRUMENTATION llMITING CONDITION FOR OPERA 110N 3.3.7.12 The radioactive gaseous effluent monitoring instrumentation channels shown in Appendix A Table 3.3.7.12-1 shall be OPERABLE with their alarm / trip setpoints set to ensure that the limit of Appendix A Requirement 3.11.2.1 are not exceeded. ihe :ltrm/ trip setpoints of applicable channels shall be determineo in accordance with the ODCM.

APPllCABILITY: As shown in Appendix A Table 3.3.7.12-1 ACTION:

a. With a radioactive gaseous effluent monitoring instrumentation channel alarm / trip setpoint less conservative than required by the above requirement, immediately suspend the release of radioactive gaseous effluents monitored by the affected channel ;

or declare the channel inoperable. :

i

b. With less than the minimum number of radioactive gasecus j effluent monitoring instrumentation channels OPERABLE, take the i ACTION shown in Appendix A Table 3.3.7.12-1. Restore the I inoperable instrumentation to OPERABLE status within the time l specified in the ACTION and, if unsuccessful, explain why this inoperability was not corrected in a timely manner in the next Semiannual Radioactive Effluent Release Report. ;

SURVEllLANCE RE0VIREMENTS

-t 4.3.7.12 Each radioactive gaseous effluent monitoring instrumentation l channel shall be demonstrated OPERABLE by performance of the CHANNEL ;

CHECK, SOURCE CHECK, CHANNEL CAllBRATION and CHANNEL FUNCTIONAL TEST ,

operations at the frequencies shown in Appendix A Table 4.3.7.12-1. .

I i

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i

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I A-14 Draft i f

l TABLE 3.3.7.12-1 RADI0 ACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION MINIMUM CHANNELS INSTRUMENT OPERABLE APPLICAB!LI;T1 ACTION.

1. RADWASTE BUILDING VENTILATION MONITORING SYSTEM

a. ' Noble Gas Activity Monitor -

Providing Alarm 1

121

, b. Iodine Sampler 1 122

c. Particulate Sampler 1 122

d. Effluent System Flow Rate Measuring Device

1 123

e. Sampler Flow Rate Measuring Device 1

123

?

+

2. NOT USED

3. CONTAINMENT VENTILATION MONITORING SYSTEM

a. Noble' Gas Activity Monitor Providing Alarm 1 121

b. Iodine Sampler 1

122

c. Particulate Sampler 1 122

d. Effluent System Flow Rate Monitor I

123

e. Sampler Flow Rate Monitor 1 123 a

5

?

TABLE 3.3.7.12-1 (Continued)

RADI0 ACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION MINIMUM CHANNELS INSTRUMENT OPERABLE APPLICABILITY ACTION

4. TURBINE BLDG. VENTILATION MONITORING SYSTEM'

a. Noble Gas Activity Monitor 1 121 Iodine Sampler *

b. 1 122

c. Particulate Sampler 1

122

d. Effluent System Flow Rate Monitor 1 123

e. Sampler Flow Rate Monitor 1

123

?

5. FUEL HANDLING AREA VENTILATION MONITORING SYSTEM

a. Noble Gas Activity Monitor 1 121-

b. Iodine Sampler

122 1

c. Particulate Sampler I

122

d. Flow Rate Monitor 1 123 Sampler Flow Rate Monitor *

e. 1 123 o

S

?

TABLE 3.3.7.12-1 (Continued)L RADI0 ACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION MINIMUM CHANNELS INSTRUMENT OPERABLE APPLICABILITY ACTION

6. OFFGAS PRE-TREATMENT MONITOR

a. Noble Gas Activity Monitor 1

- - '126

7. OFFGAS POST-TREATMENT MONITOR l a. Noble Gas Activity Monitor Providing Alarm and Automatic Termination of Release 2 ** 125

8. STANDBY GAS TREATMENT EXHAUST

?" MONITORING SYSTEM (A&B)

a. Noble Gas Activity Monitor 1/ system

127 5

3

I TABLE 3.3.7.12-1 (Contirumd1 B.AD10 ACTIVE GASE0US EFFLUENT MONITORING INSTRUMENTATION j TABLE NOTATION l At all times.

- During main condenser offgas treatment system operation.

- - During operation of the main condenser air ejector.

ACTION 121 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue for up to 30 days provided grab samples are taken at least once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months and these samples are analyzed for gross activity within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

ACTION 122 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue for up to 30 days provided samples are continuously collected with auxiliary sampling equipment as required by Appendix A Table 4.11.2.1.2-1.

ACTION 123 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent release via this pathway may-continue for up to 30 days provided the flow rate is estimated at least once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months .

ACTION 124 - NOT USED ACTION 125 - a. With one of the required monitors inoperable, place the inoperable channel in the downscale tripped condition within one hour.

b. With both of the reTJired monitors inoperable, effluent releases via this pathway may continue for up to 30 days-providcd grab samples are taken at least once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months and these samples are analyzed for gross activity within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

ACTION 126 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, the SJAE

-effluent may be released to the environment for up to 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months provided:

a. The--offgas system is not bypassed, except for filtration system bypass during plant startups, and

b. The offgas delay system noble gas activity effluent downstre3> monitor is OPERABLE; Otherwise, be in at least HOT SHUTDOWN within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months , and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

.- ACTION 127 - With the number of channels 0PERABLE less than required by L the Minimum Channels OPERABLE requirement, effluent

releases via this pathway may continue for up to 30 days l provided grab samples are taken at least once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months i and these samples are analyzed for gross activity within i 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

A-18 Draft

TABLE 4.3.7.12-1 RADI0 ACTIVE GASE0US EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS CHANNEL MODES IN WHICH CHANNEL SOURCE CTANhEL FUNCTIONAL SURVEILLANCE INSTRUMENT CHECK CHECK CALIBRATION TEST REOUIRED I. RADWASTE BUILDING VENTILATION MONITORING SYSTEM i

a. Noble Gas Activity Monitor -

Providing Alarm D M A(3) Q(2)

b. Iodine Sampler W N.A. N.A. N.A. * !

c. Particulate' Sampler W N.A. N.A. N.A. *

d. Flow Rate Monitor D N.A. R

Q(5)

e. Sampler Flow Rate Monitor D N.A. R N.A. *

2. NOT USED -

3. CONTAINMENT VENTILATION !

MONITORING SYSTEM

a. Noble Gas Activity Monitor Providing Alarm D M A(3) Q(2)

b. Iodine Sampler N.A. N.A.

W H.A.

c. Particulate Sampler W N.A. N.A. N.A. *

d. Effluent System Flow Rate Monitor D N.A. R

Q(5)

? e. Sampler Flow Rate Monitor D N.A. R N.A.

b 1

TABLE 4.3.7.12-1 (Continued)

RADI0 ACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS CHANNEL MODES 1 ; ;H '

l CHANNEL SOURCE CHANNEL FUNCTIONAL SURVE. t E INSTRUMENT CHECK CHECK CALIBRATION TEST REQUlkma

4. TURBINE BLDG. VENTILATION -

MONITORING SYSTEM l

'a. Noble Gas Activity Monitor D M A(3) Q(2)

b. Iodine Sampler W N.A. N.A. N.A. *

c. Particulate. Sampler W N.A. N.A. N.A. *

d. Flow Rate Monitor D N.A. R- Q(5)

,, e. Sampler Flow Rate Monitor D N.A. R N.A.

b

5. FUEL HANDLING AREA VENTILATION MONITORING SYSTEM

a. Noble Gas Activity Monitor D M .A(3) Q(2)

b. Iodine Sampler W H.A. N.A. N.A. *

c. Particulate Sampler- W. N.A. N.A. N.A. *

d. Flow Rate Monitor D N.A. R Q(5)

e. Sampler Flow Rate Monitor 0 N.A. R N.A.

a w

?

TABLE 4.3.7.12-1 (Continued).

l

( RADI0 ACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS l

l CHANNEL. MODES IN WHICH CHANNEL SOURCE- CHANNEL FUNCTIONAL SURVEILLANCE INSTRUMENT CHECK CHECK CALIBRATION TEST REOUIRED

6. OFFGAS PRE-TREATMENT MONITOR Noble Gas Activity Monitor ***

a. D M# A(3)## Q(2)

7. OFFGAS POST-TREATMENT MONITOR

a. Noble Gas Activity Monitor Providing Alarm and Auto-matic Termination of Release D M A(3)## Q(1)

8. STANDBY GAS TREATMENT EXHAUST 2 MONITORING SYSTEM (A&B)

~~

Noble Gas Activity Monitor *

a. D M A(3) Q(2)

?

5

--i+.-+, g- y -, y- ,- ,%-m.-q.,e-m ye y i.. , i w-- t w.. Sv,-,p. ,e a v- g---trg e - --v'g,e gip- e p.-n.-, , - w .e r g s m w.. imi,-,4cv- . - . + ..-m- mee,y.w.-g,-., ,w..- -e.-.wm.--e - . < . - . , ~,v.#.dmr+ .~.y-

TABLE 4.3.7.12-1 (Continued)

RAQ10 ACTIVE GASEOUS-EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS TABLE NOTATION At all times.

- During main condenser offgas treatment system operation.

- - During operation of the main condenser air ejector.

SOURCE CHECK may be deferred to the next shutdown of greater than 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months duration if unable to be performed at the monthly interval due to inaccessibility because of being in a high radiation area.

1. The sensor will be calibrated for mr/hr or cpm from the calibration standard. The conversion to release rate will be performed during subsequent unit operation, but within one week.

(1) The CHANNEL FUNCTIONAL TEST shall also demonstrate that automatic isolation of-this pathway and control room alarm annunciation occurs if any of the following conditions exists:

1. Instrument indicates measured levels above the alarm / trip setpoint.

2. Circuit failure. ,

3. Instrument indicates a dowascale failure.

4. Instrument controls not set in operate mode.

(2) The CHANNEL FUNCTIONAL TEST shall also demonstrate that control room alarm annunciation occurs if any of the following conditions exists:

1. Instrument indicates measured levels above the alarm setpoint.

2. Circuit failure.

3. Instrument indicates a downscale failure.

4. Instrument controls not set in operate mode.

(3) The initial CHANNEL CAllBRATION shall be performed using one or more of the reference standards certified by the National Bureau of Standards (NBS) or using standards that have been obtained from suppliers that participate in measurement assurance activities with NBS. These standards shall permit calibrating the system over its intended measurement range. For subsequent CHANNEL CALIBRATION, sources that have-been related to the initial calibration shall be used.

(4) NOT USED (5) Compare the measured flow rate to the expected design flow rate for existing plant ' conditions, t

i A-22 Draft 1

3/4.11 RAD 10ACT!VE EFFLUENTS 3/4.11.1 L10VID EFFLUENTS CONCENTRATION LIMITING CONDITION FOR OPERATION 3.11.1.1 The concentration of radioactive material released in liquid effluents to UNRESTRICTED AREAS (see Technical Specification Figure 5.1.3-1) shall be limited to the concentrations specified in 10 CFR Part 20, Appendix B. Table II, Column 2 for radionuclides other than dissolved or entrained noble gases. For dissolved or entrained noble '

gases, the' concentration shall be limited to 2 x 10" microcuries/ml total activity.

APPLICABILITY: At all times.

ACTION:

With the concentration of radioactive material released in liquid effluents to UNRESTRICTED AREAS exceeding the above limits, immediatet -

restore the concentration to within the above limits.

SURVEllLANCE RE0VIREMENTS 4.11.1.1,1 The radioactivity content of each batch of radioactive liquid waste shall be determined prior to release by sampling and analysis in accordance with Appendix A Table 4.11.1.1.1-1. The results of pre-release analyses shall be used with the calculational methods in the 00CM to assure that the concentration at the point of release is maintained within '

the limits of Appendix A Requirement 3.11.1.1.

4.11.1.1.2 Post-release analyses of samples composited from batch I releases shall be performed in accordance with Appendix A Table 4.11.1.1.1-1. The results of the radioactivity analysis shall be -

used.in accordance with the methodology and parameters in the ODCM to '

' assure that the concentrations at the point of release are maintained t within the limits of Appendix A Requirement 3.11.1.1.

i i

1 i A-23 Draft i

, , , - - . . . , n a , - - , , , - , - - - - - - - - -

TABLE 4.11.1 1 1.d-l RADI0 ACTIVE L10010 WASTLSAMPLiliG_AND ANALYSIS PROGRAJJ Minimum lype of Lower Limit Liquid Release Sampling Analysis Activity of Detection Type Frequency Frequency Analysis (LLD)

(,Ci/ml)(a)

A. Batch Waste P P Principal Gamma 5x10" Release Each batch Each Batch Emitters (d)

Tanks (c) 4 1-131 lx10 4

P M Dissolved and 1x10 One Batch /M Entrained Gases (Gamma emitters) 4 P M H-3 lx10 Each Batch C om p o s i t e ( b ) --- - - -- -- - -- - - - - - -- - - - - - - - -- --- - - -

Gross Alpha lx10" P Q Sr-89, Sr-90 5x10" Each Batch C om p o s i t e ( b ) - ------ -- - -- - - ----- ---- ----- -----

Fe-55 l x 10-'

D B. SSW Basin Principal Gamma 5x10" (prior to Each Each Batch Emitters (d) blowdown) Blowdown - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -

1-131 lx10 4

A-24 Draft l

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

TABLE 4.11.1.1.1-1-(Continued)

-RADI0 ACTIVE L10010 WASTE SAMPLING AND ANALYSIS PROL TABLE NOTAT103

a. The LLD is the smallest concentration of radioactive material in a !

sample that will yield a net count (above system background) that will be detected with 95% probability eith only 5% probability of falsely concluding that 4 blank observation represents a "real" signal. ;

for a particular measurement system (which may include radiochemical separation):

_4.66 s, LLD = --------------------------------------

E.V. 2.22 x 10' . Y . exp(-Aat) where LLD is the "a priori" lower limit of detection as defined above (as ,Ci per unit mass or volume). (Currentliterature :

defines the LLD as the detection capability for the instrum9ntation only, and the MDC, minimum detectable concentration, as the detection capability for a given )

instrument, procedure, and type of sample.)

s, is the standarc deviation of the background counting rate or of the counting rate _ of a blank sample as appropriate :

(as counts per minute) ?

E is the counting efficiency (as counts per disintegration)

V is the sample size (in units of mass or volume) !

t 2.22 x 10' is the number of disintegrations per minute per microcurie j Y is the fractional radiochemical yield (when applicable) l i

is the radioactive decay constant.for the particular 1

radionuclide At is the elapsed time between sample collection (or end of ;

the sample collection period) and time of counting -

The value of s, used in the calculation of the LLD for a particular measurement system should be based on the actual observed variance of l the background counting rate or of the counting rate of the blank i samples (as appropriate) rather than on an unverified theoretically ;

predicated variance.

Typical values of E, V, Y and At should be used in the calculation.

It should be recognized that the LLD is defined as an a pfi ori :

(before the fact) limit representing the capability of a measurement '

system and not as a posteriori (after the fact) limit for a ,

particular measurement. '

A-25 Draft !

l t

^

-IASLE 4.11.1.1.1-1 (Continuedl RADI0 ACTIVE LIOUID WASTE SAMPLING AND ANALYSIS PROGRAM TABLE NOT4110H_(Continued) [

b. A composite sample is one in which the quantity of liquid sampled is l proportional to the quantity of liquid waste discharged and in which -

the method of sampling employed results in a specimen which is !

representative of the liquids released, j

c. A batch release is the discharge of liquid wastes of a discrete !

volume. Prior to sampling for analyses, each batch shall be i isolated, and then thoroughly mixed to assure representative l' sampling.

d. The principal gamma emitters for which the LLD specification applies exclusively are the following radionuclides: Mn-54, Fe-59, Co-58, i Co-60, In-65, Mo-99, Cs-134, Cs-137, Cc 141, and Ce-144. This list :

does not mean that only these nuclides are to be detected and i reported. Other peaks which are measurable and identifiable, ;

together with the above nuclides, shall also be identified and '

reported.

i t

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l 1

1 1

I A-26 Draft l !

I r I- , . - - .., ....-

RAD 10AGLVE EfflyBl$ I i

001E !

LIMITING CONDITION FOR OPERATION 3.11.1.2 The dose or dose commitment to a HEMBER Of THE PUBLIC frem radioa-tive materials in liquid effluents released, from each reactor >

unit, to UNRESTRICTED AREAS (see Technical Specification figure 5.1.3 1) !

shall be limited: )

a. During any calendar quarter to less than or equal to 1.5 mrem to i the total body and to less than or equal to 5 mrem to any organ, ;

and j

b. During any calendar year to less than or equal to 3 mrom to the total body and to less than or equal to 10 mrem to any organ. ,

APPLICABILITY: At all times, j i

ACTION: L l

With the calculated dose from the release of radicactive materials in i liquid effluents exceeding any of tht. above limits, prepare and submit to !

the Commission within 30 days, pursuant to Technical Specification 6.9.2, a Special Report which identifies the cause(s) for exceeding the limit (s) )

and defines the corrective actions that have been taken to reduce the e releases and the corrective actions to be taksn to ensure that future i releases will be in compliance with the above limits. This Special Report ;

shall also include (1) the results of radiological analyses of the j drinking water source and (2) the radiological impact on finishad drinking >

water supplies with regard to the requirements of 40 CfR fart 141.*

EURVEILLANCE RE0MIREME14TS t

4.11.1.2 Dose Calculations. Cumulative dose contributions from liquid '

effluents for the current calendar quarter and the current calendar year shall be determined in accordance with the methodology and parameters of !

the ODCM at least once per 31 days. !

i 1

i

Applicable only if drinking water supply is taken from the receiving water body within 3 miles downstream of the plant discharga. l i

i i

A-27 Draft f l ,

R&D10AcT1vt ErrLUENTS L10V_ID WASTE TREATHENI LIM 111R0_10NDITION FOR OPERATION 3.11.1.3 The liquid radwaste system shall be used to reduce the radioactive materials in liquid wastes prior to their discharge when the projected doses due to the liquid effluent from each reactor unit to UNRESTRICTED AREAS (see Technical Specification rigure 5.1.3 1) would exceed 0.06 mrem to the total body or 0.2 mrom to any organ, in a 31 Jay period.

APPLICABillTY: At all times.

6(JJpfj:

With radioactive liquid waste being discharged without treatment and in excess of the above limits, prepare and submit to the Commission, within 30 days pursuant te Technical Specification 6.9.2, a Special Report which includes the following information:

a. Explanation of why liquid radwaste was being discharged without treatment, identification of-any inoperable equipment or subsystems, which resulted in liquid radwaste Seing discharged without treatment, and the reason for the inoperability, and

b. Action (s) taken to restore the inoperable equipment to OPERABLE status, and

c. Summary description of action (s) taken to prevent a recurrence.

SVRVEILLANCE RE0QIREMENTS 4.11.l.3.1 Doses due to liquid releases from each reactor unit to UNRESTRICTED AREAS shall be projected at least once per 31 days, in accordance with_ methodology and parameters in the ODCM.

4.11.1.3.2 The installed liquid radwhste system shall be demonstrated OPERABLE by meeting Appendix A Requirements 3.11.1.1 and 3.11.1.2.

j A-28 Draft

,y-1 l

RADIDACTIVE EFFLUENTS i 3/4.11.2 GASEOUS EffLVENTS DOSE RATE LIM 111NG CONDITION FOR OPERATION 3.11.2.1 The dose rate due to radioactive materials released in gaseous effluents from the site to areas at and beyond the Sill BOUNDARY (see ,

Technical Specification figure 5.1.3 1) shall be limited to the following. .

t

a. For noble gases: Less than or equal to 500 mrem /yr to the total body and less than or equal to 3000 mren/yr to the skin, and

b. For all iodine 131, iodii 133, tritium and all radionuclides in particulate form with hal lives greater than 8 days: Less than er equal to 1500 mrem /yr o any organ.

APPLICABILITY: At all times. .

ACT.10N:

With the dose rate exceeding the above limits, immediately decrease the release rate to within the above limit (s).

EMRYfll' ANCE RE0VIREMENTS -_.

4.11.? 1.1 The dose rate due to noble gases in gaseous effluents shall be deter ned to be within the above limits in accordance with the methodology and parameters of the ODCM.

4.11.2.1.2 The dose rate due to iodine 131, iodine-133, tritium and to radionuclides in particulate form with half lives greater than 8 days in gaseous effluents shall be determined to be within the above limits in accordance with the methodology and parameters of the ODCH by obtaining representative samples and performing analyses in accordance with the sampling and analysis program specified in Appendix A Table 4.11.2.1.2-1.

A 29 Draft

t 4 i r

TABLE 4.lL2.1 2 1 i

fLAD10 ACTIVE GASE0VS WAS1E SAMPLING AND ANALYSIS PROGRM

___ __-__. _______ ._,____..._____.____..______________ .._-___-_____.... ____. f Gaseous Release Type . Sampling Minimum Type of lower Limit frequency Analysis Activity of Detection frequency Analysis (LLD) j (sti/ml)(a) :

.--_._ -_..__. __....... .._.... .... _.__.. ._.._.......... ..... _......... __-. i A. (1) Radwaste Building H H Principal Gamma lx10

Ventilation Grab Sample Emitters (b,e) .

Exhaust -..---------_-...----------- I H3 lx10 i I

(2) fuel Handling Continuous (d) W(c) 1-131 l x 10'" !

Area Ventila- Charcoal - - - - - - - - - - - - - - - - . - - - - - - - - - - -

tion Exhaust t Sample 1 133 lx10"' !

(3) Containment Continuous (d) W(c) Principal Gamma l x 10'" i Ventilation Particulate Emitters (e) ;

Exhaust Sample (113),Others) i (4) Turbine Building Continuous (d) H Gross Alpha l x 10~" l Ventilation Composite i Exhaust Particulate #

Sample !

Continuous (d) Q Sr-89, Sr-90 l x 10'" l Composite Particulate Sample Continuous Noble Gas Noble Gases lx10 ' :

Monitor Gross Beta or Gamma !

B. (1) Offgas Post M M Principal Gamma l x 10

Treatment Grab Sample Emitters (e)

Exhaust, when-ever there e is flow (2) Standby Gas :

Treatment A Exhaust, when-ever there is flow.

(3) Standby Gas Treatment B E::haust, when-ever there is flow.

See " Table Notation" which follows.

A-30 Draft

IABLE 4.11.2.1.2 1 (Continued)

$5;;l0AC.1VEGASEOUSWASTESAMPLINGANDANALYSISpROGRAM IABLE NOTATION

a. The LLD is the smallest concentration of radioactive material in a sample that will yield a not count (above system background) that will be detected with 95% 3robability with only 5% probability of falsely concluding that a slank observation represents a "real" signal.

for a particular measurement system (which may include radiochemical separation):

4.66 s.

LLD -

E. V. 2.22 x 10' . Y. exp( 1At) where LLD is the "a priori" lower limit of detection as cefined above (as nCi per unit mass or volume). (Current literature defines the LLD as the detection capability for the instrumentation only, and the MDC, minimum detectable concentration, as the detection capability for a given instrument, procedure, and type of sample.)

s, is the standard deviation of the background counting rate or of the counting rate of a blank sample as appropriate (as counts per minute)

E is the counting efficiency (as counts per disintegration)

V is the sample size (in units of mass or volume) 2.22 x.10' is the number of disintegrations per minute per microcurie Y is the fractional radiochemical yield (when applicable)

A is the radioactive decay constant for the particular radionuclide At is the elapsed time between sample collection (or end of the sample collection period) and time of counting l

The value of s, used in the calculation of the LLO for a particular measuren. ant system should be based on the actual observed variance of the background counting rate or of the counting rate of the blank samples (as appropriate) rather than on an unverified theoretically predicated variance.

Typical values of E, V, Y and At should be used in the calculation.

It should be recognized that the LLO is defined as an a priori (before the fact) limit representing the capability of a measurement system and not as A posteriori (after the fact) limit for a particular measurement, t,- 31 Draft

1 IAD1LL11.2.1.2-1 -(OnLintitdl RADIOACTIVE CASLOVS WASTE SAMPLINLAND ANALn1S PROGRAM 1A.D1Lt(01 A110li (Continued)

b. Analyses shall also be performed following startup from cold shutdown, or a 1HERMAL POWER change exceeding 15 percent of the RATED 1HERMAL POWER within a one hour period. This requirement does not apply if (1) routine analysis reduired by Technical Specification Table 4.4.5-1 shows that the DOSE EQUIVALENT l 131 concentration in the primary coolant has not increased more than a factor of 3; and (2) the noble gas monitor shows that of fluent activity has not increased more than a factor of 3.

c. Samples shall be changed at least once per 7 days and analyses shall be completed within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months af ter changing or after removal from sampler. Sampling and analyses shall be performed at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months for at least 7 days following each shutdown, startup or THERMAL POWER change exceeding 15 percent of RATED THERMAL POWER in one hour. When sample. collected for 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months are analyzed, the corresp:,nding LLD's may be increased by a factor of 10. This requirement does not apply if (1) routine analysis required by Technical Specification lable 4.4.51 shows that the DOSE EQUIVALENT l-131 concentration in the prinary coolant has not increased more than a factor of 3; and (2) the noble gas monitor shows that effluent activity has not incre sed more than a factor of 3.

d. The ratio of the sample flow rate to the sampled stream flow rate shall be known for the time period covered by each dose or dose rate calculation made in accordance with Appendix A kequirements 3.11.2.1 and 3.11.2.3.

e. 1he principal gamma emitters for which the LLD specification applies exclusively are the following radionuc'. ides: Kr 87, Kr 88, Xe-133, Xe-133m, Xe-135, and Xe-138 for gaseous emissions and Mn-54, Fe-59, Co-58, Co-60, Zn-65, Mo 99, Cs-134. Cs-137, Ce 141 and Ce 144 for particulate emissions. This list does not mean that only these nuclides are to be detected and reported. Other peaks which are measurable and ioentifiable, together with the above nuclides, shall also be identified and reported.

A 32 Draft

B&D10 ACTIVE EFFLUENTS DOSE - 40BLE GASES LIMITING CONDITION FOR OPERATION 3.11.2.2 The air dose due to noble gases released in gaseous effluents, from each reactor unit, from the site to areas at and beyond the SITE B0UNDARY (see Tect.nical Specification figure 5.1.31) shall be limited to the following:

a. During any calendar quarter: Less than or equal to 5 mrad for gamma radiation and less than or equal to 10 mrad for beta radiation, and

b. During any calendar year Less than or equal to 10 mrad for gamma radiation and less than or equal to 20 mrad for beta radiation.

APPLICABILIJ1: At all times.

ACTION:

With the calculated air dose from the radioactive noble gases in gaseous effluents exceeding any of the above limits, prepare and submit to the Commission within 30 days, pursuant to Technical Specification 6.9.2, a Special Report which identifies the cause(s) for exceeding the limit (s) and defines the corrective actions to be taken to ensure that future releases will be in compliance with Appendix A R(quirement 3.11.2.2.

SVRVEILLANCE RE0VIREMENTS 4.11.2.2 Dose Calculations. Cumulative dose contributions for noble gases for the current calendar quarter and current calendar year shall be determined in accordance with the methodology and parameters in the ODCM at least once per 31 days.

s A-33 Draft I

.j

RAD 10AC11VE EFfLV[NIS 2

093[ - 10 DINE-131. IDDINE 133. TRIT 10M AND RA&10M[LIDES IN PAR 11CV1A'E EDM LIMITING CONDITION FOR OPERATION l 3.11.2.3 The dose to a HEMBER Of THE PUBLIC from iodine 131, iodire 133, tritium and radionuclides in particulate form with half lives greater than 8 days in gaseous effluents released, from each reactor unit, from the site to areas at and beyond the Si1E BOUNDARY (see Technical Specification Figure 5.1.3 1) shall be limited to the following:

a. During any calendar quarter: Less than or equal to 7,5 mrem to any organ, and

b. During any calendar year: Less than or equal to 15 mrem to any organ.

APPLICABILITY: At all times.

ACTION:

With the calculated dose from the release of iodine-131, iodine-133, tritium and radionuclides in particulate form, with half-lives greater than 8 days, in gaseous effluents exceeding any of the above limits, prepare and submit to the Commission within 30 days, pursuant to Technical Specification 6.9.2, a Special Report which identifies the cause(s) for exceeding the limit and defines the corrective actions that have been taken to reduce releases and the proposed corrective actions to be taken to ensure that future releases will be in compliance with Appendix A Requirement 3.11.2.3.

SilRVEILL ANCE RE0VIREMEN1' 4.11.2.3 Dose Calculations. Cumulative dose contributions from iodine-131, iodine-133, tritium and radionuclides in particulate form with half-lives greater than 8 days for the current calendar quarter and current calendar year shall be determined in accordance with the methodology and parameters in the ODCM at least once per 31 days.

A-34 Draft

fLAD10AC11VE EFFLulldS cASr00S RADRMILlRLALMLtd Lidill![G C0f4DIT10N FOR OPERA 110N 3.11.2.4 The GASEOUS RADWASTE TREATMENT (Of fGAS) SYSTEM shall be in operation.

APPLICABillll: Whenever the main condenser .r ejuctor system is in operation.

ElLQ1J:

With gaseous radwaste from the main condenser air ejector system being discharged without treatment for more than 7 consecutive days, prepare and submit to the Commission within 30 days, pursuant to Technical Specification 6.9.2, a Special Report which includes the following information:

a. Explanation of why gaseous radwaste was being discharged without treatment, identification of the inoperable equipment or subsystems which resulted in gaseous radwaste being discharged without treatment, and the reason for inoperability,

b. Action (s) taken to restore the inoperable equipment to OPERABLE status, and

c. Summary description of action (s) taken to prevent a recurrence.

SVRVElllANCE RE0VIREMENTS 4.11.2.4 The instruments specified in the ODCM shall be checked every 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months whenever the main condenser air ejector system is in operation to ensure that the GASE0US P.ADWASTE TREATMENT (OffGAS) SYSTEM is functioning.

A-35 Draft

L I

R&D10 ACTIVE EfrLUENTS t VENTILATION EXilAUST 1REATHENT l LIM 111NG CQHDITION FOR OPERA 110N ,

3.11.2.5 The VENTILA110N EXilAUST TREA1HENT SYSTEM shall be used to reduce !

radioactive materials in gaseous waste prior to their discharge when the !

projected dose due to gaseous effluent releases from each reactor unit to i areas at and beyond the Si1E BOUNDARY (see Technical Specification l figure 5.1.3-1) in a 31 day period would exceed 0.3 mrem to any organ. !

I APfllfhBjll1Y: At all times other than when the VENTILATION EXIIAUST I 1RLAIMENT SYS1[H is undergoing routine maintenance.* i ACTION: !

With gaseous waste being discharged without treatment and in excess of the above limits, prepare and submit to the Commission within 30 days, ;

pursuant to Technical Specification 6.9.2, a Special Report which includes i the following information l

[

a. Explanation of why gaseous radwaste was being discharged without [

treatment, identification of any inoperable equipment or i subsystems which resulted in gaseous radwaste being discharged !

without treatment, and the reason for the inoperability. l E

b. Action (s) taken to restore the inoperable equipment to OPERABLE !

status, and l

c. Summary description of action (s) taken to prevent a recurrence.

l EURVEILLANCE RE0VIREMENTS 4.11.2.5.1 Doses due to gaseous releases from each reactor unit to areas !

at and beyond the Si1E BOUNDARY shall be projected at least once per 31 days in accordance with the methodology and parameters in the ODCH. f 4.11.2.5.2 The installed VENTILATION EXHAUST TREA1 MENT SYSTEM shall be demonstrated OPERABLE by meeting Appendix A Requirements 3.11.2.1 and ,

3.11.2.2 or 3.11.2.3. t I

Not applR i5Te to Turbine Building ventilation exhaust unless filtration !

media is installed. !

t I

i A-36 Draft i

_ . _ . _ _ _ .__ _ . _ . . _ _ . . _ _ .._.___.___._.___.__.s

RADIOACTIVE EFFLUENTS l l

3/4.11.4 TOTAL DOSE l LIMITING CONDITION FOR OPERATIB i

3.11.4 The annual (calendar year) dose or dose commitment to any HEMBER Of l THE PUBLIC due to releases of radioactivity and to radiation from uranium i fuel cycle sources shall be limited to fets than or equal io 25 mrem to the total body or any organ, except the thyroid, which shall be limited to less i than or equal to 75 mrem. !

APPllCABillTY: At all times. l efll08: f With the calculated doses from the release of radioactive materials in liquid or gaseous effluents exceeding twice the limits of Appendix A Requirements 3.ll.l.2.a. 3.ll.l.2.b. 3 ll.2.2.a. 3.ll.2.2.b, 3.ll.2.3.a.

or 3.ll.2.3,b, calculations should be made including direct radiation contributions from the reactor units and from outside storage tanks to ,

determine whether the above limits of Appendix A Requirement 3.11.4 have ;

been exceeded. If such is the case, prepare and submit to the Commission !

within-30 days, pursuant to Technical Specification 6.9.2, a Special Report l that defines the corrective action to be taken to reduce subsequent releases j to prevent recurrence of exceeding the above limits and includes the schedule for achieving conformance with the above limits.- This Special !

Report, as defined in 10 CFR Part 20.405c, shall include an analysis that i estimates the radiation exposure (dose) to a MEMBER Of THE PUBLIC from uranium fuel cycle sources, including all effluent pathways and direct l radiation, for the calendar year that includes the release (s) covered by {

this report, it shall also describe levels of radiation and concentrations j of radioactive material involved, and the cause of the exposure levels or i concentrations. If the estimated dose (s) exceeds the above limits, and if !;

the release condition resulting in violation of 40 CFR Part 190 has not i already been corrected,- the Special Report shall include a request for a variance in accordance with the provisions of 40 CfR Part 190. Submittal of (

the report is considered a timely request, and a variance is granted until ;

staff action on the request is complete. '

SVRVElllANCE RE0VIREMENTS 4.11.4.1 Cumulative dose contributions from liquid and gaseous effluents shall be determined in accordance with Appendix A Requirements 4.11.1.2, !

4.11.2.2, and 4.11.2.3, and in accordance with the trethodology and 7 parameters in-the ODCH.

t 4.11.4.2 Cumulative dose contributions from direct radiation from the i.

reactor units and from radwaste storage tanks shall be dotarmined in i accordance with the methodology and parameters in the ODCH. This }

requirement is applicable only under conditions set forth in Appendix ;

A Requirement 3.11.4.a.

A-37 Oraft

3/4.12 RADIOLOGIGL ENVIRONMENTAL M0M10R1RG 3/4.12.1 MON 110 RING PROGRAM LIMITING CONDITION FOR OPERA 110N_ _

3.12.1 The radiological environmental monitoring program shall be conducted as specified in Appendix A Table 3.12.1 1.

APPLICABILITY: At all times.

ACTION:

a. With the radiological environmental monitoring program not being ,

conducted as specified in Appendix A Table 3.12.1-1, prepare and submit to the Conunission, in the Annual Radiological Environmental Operating Report per Technical Specification 6.9.1.7, a description of. the reasons for not conducting the program as required and the plans for preventing a recurrence,

b. With the level of radioactivity as the result of plant effluent in an environmental sampling medium at a specified location exceeding the reporting levels of Appendix A Table 3.12.1 2 when averaged over any calendar quarter, pre)are and submit to the Commission within 30 days pursuant to Tec1nical Specification 6.9.2 a Special Report that identifies the cause(s) for exceeding the limit (s) and defines the corrective actions to be taken to reduce radioactive effluents so that the potential annual dose to a MEMBER Of 1HE pVBLIC is less than the calendar year limits of Appendix A Requirements 3.11.1.2, 3.11.2.2 and 3.11.2.3. When more than one of the radionuclides in Appendix A Table 3.12.12 are detected in the sampling medium, this report shall be submitted ift 21W11Lat ion (l L., + Canctnin110lLil)_ + . . .t 1.0 reporting level (1) reporting level (2)

When radionuclides other than those in Appendix A lable 3.12.1-2 ,

are detected and are the result of plant efficents, this report shall be suomitted if the potential annual dose to a MEMBER Of illE pVBLIC is equal to or greater than the calendar year limits of Appendix A Requirements 3.11.1.2, 3.11.2.2 and 3.11.2.3. This report is not required if the measured level of radioactivity was not the result of plant effluents; however, in such an event, the condition shall be reported and described in the Annual Radiological Environmental Operating Report,

c. If milk or broad leaf vegetation sampling is relocated from one or more of the sample locations required by Appendix A Table 3.12.1-1 identify new locations for obtaining replacement samples and add them to the radiological environmental monitoring 3rogram

, within 70 days, in addition, report the cause(s) of t1e l unavailability of samples and the new locations for o$ ining t

replacement samples in the next Semiannual Radioactive ;.ffluent ,

Release Report, include in this report the revised ODCH figure (s) and table (s) reflecting the new locationb 1he specific locations i from which samples were unavailable may then be deleted from the I radiological environmental monitoring program and the table (s) in l the ODCM, provided the locations from which the replacement samples were obtained are added to the tabic (s) as replecement locations.

A-38 Draft

i t

RAD 1010HlCAL ENVIRONMENTAL MOR110 RING ;

r SURVElltANCE RE0VJREMENTS l 7

4.12.1 The radiological environmental monitorin samples shall be !

collected pursuant t1 Appendix A lable 3.12.1 1 rom the locations given j in the table and figu.es in the ODCH and shall be analyzed pursuant to the i requirements of Append;x A Tables 3.12.1 1 and 4.12.1-1.

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TAB! E 3.12.1-1 OPERATIONAL RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

- - - - - - - - - - - - - - - . . - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - Type

- - - - and

- - - Frequency Number of Samples (a) Sampling and Exposure Pathway Collection Frequency (a) of Analysis and/or Sample and Locations AIRBORNE Samples from 5 locations: Continuous sampler Radiciodine Cannister:

Radiciodine and operation with sample Analyze weekly for Particulates collection weekly or as I-131 3 samples close to the SITE BOUNDARY (in different secters) required by dust hav'ng the highest calculated loading, whichever is annual average groundlevel 3/Q. core frequent Particulate Sampler:

I sample from the vicinity of a Gross beta radio-community having the highest activity following calculatea annual average ground- filter change,(b) level P/Q. composite (by location)

, for gamma isotopic (c)

I sample from a control location o quarterly l 15-30 km (10-20 miles) distance (d) -- --- -- -------.-- --- ---------------------------

40 stations with two -------------------Quarterly or more dosi-Gamna dose quarterly DIRECT RADIATION (e) meters or one instrument for measuring and recording dose rate continuously to be placed in each accessible

sector as follows:

1) an inner ring of stations in the general areas of the SITE BOUNDARY

2) an outer ring approximately 3 to 5 miles from the site.

EE The balance of the stations should El be placed in special interest areas

" such as population centers, nearby residences, schools, and in 1 or 2 areas to serve as control stations.

TABLE 3.12.1-1 (Continued)

OPERATIONAL RADIOLOGICAL ErfVIRONMENTAL MONITORING PROGRAM Exposure. Pathway Number of Samples (a) Sampling and Type and Frequency and/or Sample and Locations Collection Frequency (a) of Analysis WATERBORNE Surface (f) I sample upstream Monthly Gamma' isotopic analysis I sample downstream monthly (c). Composite for tritium analyses

- - quarter'y Discharge Basin Composite sample over one-month period (g)

Ground Samples from 2 sources Quarterly Gamma isotopic (c) and tritium analysis

?> quarterly Cistern Water 1 sample of the nearest source Monthly I-131, Gross s and gamma that could be affected isotopic analyses (c) monthly. Composite for 1 sample from a control location tritium analysis quarterly Sediment from I sample from downstream area Semiannually Gamma isotopic Shoreline analyses (c) semiannually INGESTION Milk Samples from milking animals in 3 Semimonthly when Gamma isotopic (c) and locations within 5 km distant having animals are on pasture, I-131 analysis semi-the' highest dose potential. If monthly at other times monthly when animals there are none then, I sample from are on pasture; monthly c2 milking animals in each of 3 areas at other times.

2 between'5 to 8 km distant where doses

~0 - are calculated to be greater than 1 mrem per year (h)

!. l i l TABLE 3.12.1-1 (Continued)

! OPERATIONAL RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM i _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . ___________ -_- _- _______________- --

l Exposure Pathway Number of Samples (a) Sampling and Type and frequency and/or Sample- and Locations Collection Frequency (a) of Analysis

Milk (cont'd) I sample from milking animals at a control location (15-30 km

, distant)

Fish and I sample of one species of commer- Semiannually Gamma isotopic (c) 4 Invertebrates cially or recreationally important analysis on edible i fish in vicinity of discharge point portions I sample of same species in areas not influenced by plant discharge Food Products Samples of 3 different kinds of Monthly when available Gamma isotopic (c)

.3 3" broad leaf vegetation grown nearest and I-131 analysis

each of two different offsite loca-

! tions with highest anticipated annual j average ground-level D/Q if milk-4 sampling is not performed i

i I sample of each of the similar Monthly when available Gamma isotopic (c)

vegetation grown 15-30 km distant and I-131 analysis if milk sampling is not performed 1

i

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1 1

2

$ C3

' 2 1

i d

TABLE 3.12.1-1 (Continued)

OPERATIONAL RADIOLOGICRL ENVIRONMENTAL MONITORING PROGRAM TABLE NOTATION o As described in the ODCM.

a Specific parameters of distance and direction sector from the centerline of one reactor, and additional description

where pertinent, shall be provided for each and every sample location in Appendix A Table 3.12.1-1 in the table (s) 2 and figure (s) in the ODCM. Refer to NUREG-0133, " Preparation of Radiological Effluent Technical Specifications for

Nuclear Power Plants," October 1978, and to Radiological Assessment Branch Technical Position, Revision 1, November l

1979. Deviations are permitted from the required sampling schedule if specimens are unobtainable due to hazardous conditions, seasonal unavailability, malfunction of automatic sampling equipment and other legitimate reasons. If

specimens are unobtainable due to sampling equipment malfunction, every effort shall be made to complete corrective action prior to the end of the next sampling period. All above deviations from the sampling schedule shall be documented in the Annual Radiological Environmental Operating Report pursuant to Technical Specification 6.9.1.6.

It-is recognized that, at times, it may not be possible or practicable to continue to obtain samples of the media of choice at the most desired location or time. In these instances suitable alternative media and locations may be

chosen for the particular pathway in question and appropriate substitutions made within 30 days in the radiological i environmental monitoring program. Identify the cause of the unavailability of samples for that pathway and identify

the new location (s) for obtaining replacement samples in the next Semiannual Radioactive Effluent Release Report and also include in the' report a revised figure (s) and table (s) for the ODCM reflecting the new location (s) .

?'

*b Particuhte sample filters should be analyzed for gross beta 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or more after sampling to allow for radon and

! thoron dag hter decay. If gross beta activity in air or water is greater than ten times the yearly mean of control l samples for ny medium, gamma isotopic analysis should be performed on the individual samples.

! c Ganaa isntopic analysis means the identification and quantification of ga:raa-emitting radionuclides that may be

attributable to the effluents from the facility.

d The purpose of this sample is to obtain background information.

l' e One or more instruments, such as a pressurized ion chamber, fnr measuring and recording dose rate continuously may be

! used in place of, or in addition to, integrating dosimeters. For the purposes of this table, a thermoluminescent

dosimeter may be considered to be one phosphor and two or more phosphors in a packet may be considered as two or = ore

! dosimeters. Film badges should not be used for measuring direct radiation.

1 i

f The " upstream samole" should be taken at a distance beyond significant influence of the discharge. The " downstream" sample should be taken in an area beyond but near mixing zone.

t kg Composite sa=ples should be collected with equipment (or equivalent) which is capable of collecting an aliquot at i - time intervals which are very short (e.g., hourly) relative to the compositing period (e.g., monthly).

h The dosa shall be calculated using methodology contained in the ODCM.

a d

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TABLE 3.12.1-2 REPORTING LEVELS FOR HADI0ACT!VITY CONCENTRATIONS IN ENVIRONMENTAL SAMPLES l

Reporting Levels i

Water Airborne Particulate Fish Milk Food Products Analysis (pC1/1) or Gases (pCi/m') (pCi/Kg, wet) (pCi/1) (pC1/Kg, wet) a M-3

2 x _10' NA NA NA NA

! Mn-54 1 x 10' NA 3 x 10' NA NA i

Fe-59 4 x 10' NA 1 X 10' NA NA i

Co-58 1 x 10' NA 3 x 10' NA NA 1

1 C9-60 3 x 10' NA 1 x 10' NA NA i

! Zn-65 3 x 10' NA 2 x 10' NA NA l ?

! $ Zr-Nb-95 4 x 10' NA f4A NA NA J

f I-131 2 0.9 NA 3 1 x 10' i"

Cs-134 30 10 1 x 10' 60 I x 10' Cs-137 50 20 2 x 10' 70 2 x 10' Ba-La-140 2 x 10* NA NA 3 x 10' NA a For drinking water samples. This is a 40 CFR Part 141 value. If no drinking water pathway exists, a

value of 30,000 pCi/1 may be used.

d a

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__ _________._._._____.__m

TABtl 4.12.1-1 MAXIMUM VALUES FOR THE LOWER LIMIT 5 0F DETECTION (LLD)fa.b)

Airborne Particulate Broad Leaf Water or Gas Fish Milk Vegetation Sediment Analysis (pCi/l) (pCi/m') (pCi/kg, wet) {pti/1) (pCi/kg, wet) (pCi/kg, dry)

Gross beta 4 1 x 10 2 NA NA NA NA H-3 2000(d) NA NA NA NA NA Mn-54 15 NA 130 NA NA NA Fe-59 30 NA 260 NA NA NA Co-58,60 15 Y 130 4A NA NA In-65 30 NA 260 NA NA NA hZr-95 30 NA NA NA NA NA Nb-95 15 NA NA NA NA NA I-131 1(c) 7 x 10 NA 1 60 NA Cs-134 15 5 x 10 # 130 15 60 150 Cs-137 18 6 x 10' 150 18 80 180 4

Ba-140 60 NA NA 60 NA NA La-140 15 NA NA 15 NA NA

?.

IMLE 4.12.1 1 (Continued 1 BAUMVUALKLl0R THE LORILLIMillor DLIECilDULLDJ JADLE NOTA 1108 a Acceptable detection capabilities for thermoluminescent dosimeters used for environmental measurements are given in Regulatory ,

Guide 4.13.

b Appendix A Table 4.12 1 indicates acceptable detection capabilities for radtw etive materials in environmental samples. These detection capabilities are tabulated in terms of the lower limits of detection (LLDs). The LLD is defined, for purposes of this guide, as the smallest concentration of radioactive material in a sample that will yield a net count (above system background) that will be detected with 95% >robability with only 5% probability of falsely concluding that a blan( observation represents a "real* signal.

for a particular measurement system (which may include radiochemical separation):

LLD -

L . V . 2.22 . Y . exp ( 14t) where LLD is the "a priori" lower limit of detection as defined above (as pCi per unit mass or volume). (Current literature defines the LLD as the detection capability for the instrumentation only, and the MDC, minimum detectable concentration, as the detection capability for a given instrument, procedure, and type ofsample.)

s, is the standard deviation of the background counting rate or of the counting rate of a blank sample as appropriate (as counts per minute)

E is the counting efficiency (as counts per disintegration)

V is the sample size (in units of mass or volume) 2.22 is the number of disintegrations per minute per pictaurie Y is the fractional radiochemical yield (when applicable)

A is the radioactive decay constant for the particular radionuclido At is the elapsed time between sample collection (or end of the i sample collection period) and time of counting The value of s,, used in the calculation of the LLD for a particular measurement system should be based on the actual observed variance of the background counting rate or of the counting rate of the blank samples (as appropriate) rather than on an unverified theoretically predicated variance.

A 46 Draft l

i IMLLLlt1-1 Konttance i tWLIMtLVALUES fOR THE LOW [fLLIM1S_or or1tc110N (LLD1 f

TABLE NOTAllD!j (Continued)

Typical values of E, V, Y and At should be used in the calculation. ;

I It should be recognized that the LLD is defined as an a prtgr1 (before the fact) limit representing the capability of a measurement system and not as i A posterior 1 (after the fact) limit for a particular measurement. ;

Occasionally background fluctuations, unavoidable small sample size, the l presence of interfering nuclides, or other uncontrollable circumstances i may render these LLDs unachievable, in such cases, the contributing factors should be identified and described in the Annual Radiological Environmental Operating Report pursuant to Technical l Speci fication 6.9.1.6. !

c LLD for drinking water samples. If no drinking water pathway exists, i the LLD of gamma isotopic may be used, j i

d if no drinking water pathway exists, a value of 3000 pCi/l may be used. j I

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l A-47 Draft !

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Mul0MILAlltiy1R9NMENIAL H0!1110RlhG '

3/_4,12,2 LAND USE CENSMS LIHITING CONQllLON fOfLDELPal10N 3.12.2 A land use census shall be conducted and shall identify within a distance of 8 km (5 miles) the location in each of the 16 meteorological sectors of the nearest milk animal, the nearest residence and the nearest garden of greater than 50 m' (500 f t') producing broad leaf vegetation.

Broad leaf vegetation sampling of at least three different kinds of vegetation may be performed at the SITE BOUNDARY in each of two different direction sectors with the highest predicted 0/Qs in lieu of the garden census. Specifications for broad leaf vegetation sampling in Appendix A Table 3.12.1-1 shall be followed, including analysis of control samples.

MELILAELLilY: At all times.

AC1103:

a. With a land use census identifying a location (s) which yields a calculated dose or dose commitment greater than the values currently being calculated in Appendix A Requirement 4.11.2.3, identify the new location (s) in the next Semiannual Radioactive Ef fluent Release Report, pursuant to Technical Specification 6.9.1.9.

b. With a land use census identifying a location (s) which yields a calculated dose or dose commitment (via the same exposure pathway) 20 percent greater than at a location from which samples are currently being obtained in accordance with Appendix A Requirement 3.12.1, add the new location (s) to the radiological environmental monitoring program within 30 days. The sampling location (s), excluding le control statiun locotlon, having the lowest calculated dose dose commitm.nt(s), via the same exposure pathway, may bitueleted from this monitoring program after October 31 of thew 3ar in which this land use census was conducted. Identify the-RadioactiveEffluentRol:;yhewlocation(s)inthenextSemiannual ase Report and also include in the report a revised figured) and table (s) for the ODCM reflecting the new location (s).

SVRVEILLANCE RE0VIR[HENTS 4.12.2 The land use census shall be conducted during the growing season at least once per 12 months using that information that will provide the l best results, such as by a door-to door survey, aerial survey, or by consulting local agriculture authorities. The results of the land use census shall be included in the Annual Radiological Environmental Operating Report pursuant to Technical Specification 6.9.1.7.

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i RAD 10LOGirAL ENVIR011!imIALEGlitTORING ;

3/4.12.3 INTERLABORATORY C.QMPARISON PROGRAM i LIMITING CONDITION FOR OPERATION

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l 3.12.3 Analyses shall be performed on radioactive materials that :

correspond to sampics required by Appendix A Table 3.12.1-1. These '

materials are supplied as part of an Interlaboratory Comparison Program which has been approved by the Commission. ,

APPLICABillTY: At all times. I ACTION: >

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With analyses not being performed as required aLove, report the corrective l actions taken to prevent a recurrence to the Cotaission in the Annual !

Radiological Environmental Operating Report pursuant to Technical Specification 6.9.1.7.

SURVEILLANCE RE0VIREMENTS 4.12.3 A summary of the results obtained as part of the above required l Interlaboratory Comparison Program shall be included in the Annual l Radiological Environmental Operating Report pursuant to Technical c Specification 6.9.1.7. [

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1 BASES FOR SECTIONS 3.0 AND 4.0 LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS A-50 Draft

3/4.3 INSTRUMENTATID!i mig 3/4.3.7.I1 RAD 10AC11VE LIQRDJ((Lylt[U1011110RIRLIKEIRtLUMIl011 The radioactive liquid effluent monitoring instrumentation is provided to monitor and control, as applicable, the releases of radioactive materials in liquid effluents during actual or potential releases of liquid effluents. The alarm / trip setpoints for these instruments shall be

. calculated in accordance with the procedures in the ODCH to ensure that the-alarm / trip will occur prior to exceeding the limits of 10 CfR Part 20.

The OPERABill1Y and use of this instrumentation is consistent with the require *,:ents of General Design Criteria 60, 63 and 64 of Appendix A to 10 CTR $0.

3/1 3 7.12 RAD 10ACTIVLGA510DS EFFLUENT MON 110 RING lNSTRUMHIAT10fi The radioactive gaseous effluent monitorin0 instrumentation is provided to monitor and control, as applicable, gaseous effluents during actual or potential releases. Those instruments that monitor the activity of gaseous offluents being released to the environment shall have their alarm / trip setpoints calculated in accordance with the meth.Js in the ODCM to ensure that the alarm / trip will occur prior to exceeding the limits of 10 CFR Part 20. Other instruments that monitor offgas processin Offgas Pre Treatment Monitor and Offgas Post-Treatment Monitor) are g, (i.e.,

calibrated according to plant procedures, lhe OPERABIL11Y and use of this

. instrumentation is consistent with the requirements of General Design Criteria 60, 63 and 64 of Appendix A to 10 CFR Part 50.

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1/4.11 RADIOKU.YE EffLQUIU basts 344.I1.1 L1041D EffLULun 3/4.11.1.1 - C01(CENTRAlikti This requirement is provided to ensure that the concentration of radioactive materials released in liquid waste effluents to UNRESTRICIED AREAS will be less than the concentration icvels specified in 10 CfR Part 20, Appendix 0. Table 11 Column 2. This limitation provides additional assurance that the levels of radioactive materials M botles of water in UNRESTRICTED AREAS will result in expo %res witnie. G) the Section ll.A design objectives of Appendix 1. 10 CFR 50, o a HEMBEA Of to the topulat Qn. The THE PUBLIC, and (2) concentration limit for dissolved or entri.ined nob the limits of 10 CFR 20.106(e)le gases b edi: upon the assumption that Xc 135 is the contro'. ling radioisotope and its MPC in air (submersion) was converted to n. equivalent concentration in water using the methods described in International Commission on Radiological Prciection (ICRP) Publication 2.

The required detection capabilities for radioactive materials in liquid waste samples are tabulated in terms of the lower limits of detection (LLDs). Detailed discussion of the LLD, and other detection limits, can be found in:

(1) HASL Procedures Manual HASL-39.Q (revised annually).

(2) Currie L. A., " Limits for Qualitative Detection and Quantitative Determination - Application to Radiochemistry," /Lqal. Chem. 49, 586 93 (1968).

(3) Hartwell, J. K., " Detection Limits for Radioisotopic Counting Techniques," Atlantic Richfield Hanford Company Report ARH-2537 (June 22, 1972).

3/4.11.1.2 DOS [

This requirement is provided to implement the requirements of Sections ll.A. I!!.A and IV.A of Appendix 1, 10 CFR Part 50. The Limiting Condition for Operation implements the guides set forth in Section ll.A of Appendix 1. The ACTION statements provide the required operating flexibility and at the same time implement the guides set forth in

$cction IV.A of Appendix ! which assure that the releases of radioactive material in liquid effluents to UNRESTRICTED AREAS will be kept "as low as is reasonably achievable." Alt.o f6r fresh water sites with drinking water supplies which can be potentially affected by plant operations, there is reasonable assurance that th) operation of the facility will not result in radionuclide concentrations in tha finished drinking water that are in excess of the requirements of 40 CfR 141. The dose calculations in the ODCM implement the requirements in Section Ill. A of Appendix 1 that conformance with the guides of Appendix ! be shown by calculational procedures based on models and data, such that the actual exposure of a MEMBER OF THE PUBLIC through appropriate pathways is unlikely to be substantially underestimated. The equations specified in the ODCM for calculating the doses A-52 Draft !

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i RAD 10AC11VE EfflVEN1S ,

i BASES 3/4.11.1.2 DOSE (Continued) due to the actual release rates of radioactive materials in liquid j effluents are consistent with the methodology provided in Regulatory ;

Guide 1.109, " Calculation of Annual Doses to Man from Routine Releases of -

Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR ;

Part 50, Appendix 1, Revision 1, Octooe- 1977 and Regulatory Guide 1.113, ;

Estimating Aquatic Dispersion of Effluent from Accidental and Routine '

Reactor Releases for tne Purpose of implementing Appendix 1," April 1977. ;

This requirement applies to the release of liquid effluents f rom each ,

reactor at the site, for units with shared radwaste trit.tment systems, the liquid effluents from the shared system are proportioned aaiong the -t units sharing that system. ;

3/4.11.1.3 L10VID WASTE TREATMENl lhe requirement that the appropriate portions of this system be used i when specified provides assurance that the releases of radioactive :

materials in-liquid effluents will be kept "as low as is reasonably r

' achievable." This requirement implements the requirements of 10 CFR j Part 50.36a, General Design Criterion 60 of Appendix A to 10 CfR Part 50 and the design objective given in Section II.D of Appendix 1 to 10 CfR ;

Part 50. The specified limit governing the use of appropriate portions of l the liquid radwaste treatment system were specified as a suitable fraction :

of the dose design objectives set forth in Section ll.A of Appendix 1, ;

10 CfR Part 50, for liquid effluents. ;

This requirement applies to the release of liquid effluents from each ,

reactor at the site. For units with shared radwaste treatment systems, !

the liquid effluents from the shared system are proportioned among the units sharing the system. .

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3/4.11.2 GASEOUS EffLV Wil j 3/_idl . 2.1 DOSE RATE f This requirement is provided to ensure that the dose any time at and !

beyond the SITE BOUNDARY from gaseous effluents from al'l units on the site [

will be within the annual dose limits of 10 CFR Part 20 for UNRESTRICTED r AREAS. The annual dose limits are the doses associated with the concent- :

rations of 10 CFR Part 20 Appendix B Table 11, Column 1. These limits !

provide reasonable assurance that radioactive material discharged in '

qaseous effluents will not result in the exposure of a HEMBER Of THE

>VBLIC in an UNRESTRICTED AREA outside the SITE BOUNDARY to annual average concentrations exceeding the limits specified in Appendix B, Table 11 of 10 CFR Part 20 (10 CFR Part 20.106(b)). For HEMBERS Of THE PUBLIC who may at times be within the SITE B0VNDARY, the occupancy of the MEMBER Of THE ,

PUBLIC will be sufficiently low to compensate for any increase in the l atmospheric diffusion factor above that for the SITE BOUNDARY. The speci- r fied release rate limits restrict, at all times, the corresponding gamma :

and beta dose rates above background to a HEMBER Of THE PUBLIC at or l beyond the SITE BOUNDARY to less than or equal to 500 mrem / year to the ,

total body or to less than or equal to 3000 mrem / year to the skin. These !

release rate limits also restrict, at all times, the corresponding thyroid l dose rate above background to a child via the inhalation pathway to less i than or equal to 1500 mrem / year. !

This requirement applies to the release of gaseous effluents from all reactors at the site, for a more complete discussion of the LLD, and !

other detection limits, see the following:

(1) HASL Procedures Manual, M SLa g (revised annually). .

(2) Currie, L. A., " Limits for Qualitative Detection and Quantitative !

Determination Application to Radiochemistry," Anal. @ m 40, !

58693(1968). :

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(3) Hartwell, J. K., " Detection Limits for Radioisotopic Counting .

Techniques," Atlantic Richfield Hanford Company Report ARH-RE)2 }

(June 22,1972). [

3/4.11.2.2 DOSE - NORLLitdi[1 ;

This requirement is provided to implement the requirements of Sections [

!!.B -Ill.A and IV.A of Appendix 1, 10 CFR Part 50. The Limiting :

Condition for Operation implements the guides set forth in Section 11.B of l Appendix 1. The ACTION statements provide the required operating flexibility and at the same time implement the guides set forth in !

Section IV.A of Appendix 1 to assure that the releases of radioactive !

material in gaseous effluents to UNRESTRICTED AREAS will be kept "as low j as is reasonably achievable " The Surveillance Requirements implement the requirements in Section Ill.A of Appendix ! that conformance with the i guides of Appendix 1 be shown by calculational procedures based on models i and data such that the actual exposure of j A 54 Draft l

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F RADI0 ACTIVE EFFLUENTS BASES 3/4.11.2.2 DOSE - N0BLE GASES (Continued) a MEMBER Of THE PUBLIC through appropriate pathways is unlikely to be substantially underestimated. The dose calculations established in the ODCM for calculating the doses due to the actual release rates of radioactive noble gases in gaseous effluents are consistent with the methodology provided in Regulatory Guide 1,109, " Calculation of Annual !

Doses to Man from Routine Releases of Reactor Effluents for the Pm se of ;

Evaluating Compliance with 10 CFR Part 50, Appendix I," Revision 1, j October 1977 and Regulatory Guide 1.111, " Methods for Estimating l Atmospheric Transport and Dispersion of Gaseous Effluents in Rautine :

Releases from Light-Mater Cooled Reactors," Revision 1, July 1977. The j ODCM equations provided for determining the air doses at and beyond the l SITE BOUNDARY are based upon the historical average atmospheric :

conditions. l This requirement applies to the release of gaseous effluents from each f reactor at the site. For units with shared radwaste treatment systems, f the gaseous effluents from the shared system are proportioned among the !

units sharing that system. [

, I 3/4.11.2.3 DOSE - 10 DINE-131 iDINE-133. TRITIUM AND RAD 10NUCllDES IN PARTICULATE FORM t This requirement is provided to implement the requirements of Sections II.C, III.A and IV.A of Appendix 1, 10 CFR Part 50. The Limiting :

Conditions for Operation are the guides set forth in Section !!.C of :

Appendix 1. The ACTION statements provide the required operating j flexibility and at the same time implement the guides set forth in

- Section IV.A of Appendix 1 to assure that the releases of radioactive i materials in gaseous effluents to UNRESTRICTED AREAS will be kept "as low 1 as is reasonably achievable." The ODCM calculational methods specified in ;

the Surveillance Requirements implement the requirements in Section Ill. A. !

of Appendix I that conformance with the guides of Appendix 1 be shown by calculational procedures based on models and data, such that the actual ;

exposure of a MEMBER OF THE PUBLIC through appropriate pathways is j unlikely to be substantially enderestimated. The ODCM calculational !

methods for calculating the doses due to the actual release rates of the !

subject materials are consistent with the methodology provided 'r R ;u- '

latory Guide 1.109, " Calculation of Annual Doses to Man from Routine '

Releases of Reactor Effluents for the Purpose of Evaluati:.g Compliance i with 10 CFR Part 50, Appendix I," Revision 1, October 19/7- and Regulatory i Guide 1.111, " Methods for Estimating Atmospheric Transport and Dispersion l of Gaseous Effluents in Routine Releases from Light Water-Cooled f Reactors," Revision 1, July 1977. These equations also provide for l determining the actual doses based upon the historical average atmospheric i conditions. The release rate specifications for iodine-131, iodine-133, t tritium and radionuclides in particulate form are dependent on the existing radionuclide pathway to man in the areas at and beyond the SITE B0UNDARY. The pathways which were examined in the development of these l calculations were: (1) individual inhalation of airborne radionuclides, (2) deposition of radionuclides onto green leafy vegetation with subsequent consumption by man, (3) deposition onto grassy A-55 Draft I

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-R&910 ACTIVE EFFLUENTS BASES 1L4.11.2.3 DOSE - 10 DINE-131. 10 DINE-133. TRITIUM AND RAD 10MUCllDES IN PARTICULATE FORM (Continued) >

areas where milk animals and meat-producing animals graze with consumption of the milk and meat by man, and (4) deposition on the ground with subsequent i exposure of man.

i This requirement applies to the release of gaseous effluer.ts from each reactor at the site, for units with shared radwaste treatment systems, the ,

gaseous effluents from the shared system are proportioned among the units -

sharing that system.

2/1 11 2.4 and 3/4.11.2.5 GASEQUS RA0 WASTE TREATMENT AND VENTILATIDji EXHAUST TREATMENT r The OPERABILITY of the GASE0US RADWASTE TREATMENT (OffGAS) SYSTEM and the VENTILATION EXHAUST TREATMENT SYSTEM ensures tnat the system will be available for use whenever gaseous effluents require treatmert prior to release to the ;

environment. The requirement that the appropriate portions of the system be used, when specified, provides reasonable assurance that the releases of radioactive materials in gaseous effluents will be-kept "as low as is reason-ably achievable." This requirement implements the requirements of 30 CFR Part 50.36a, General Design Criterion 60 of Appendix A to 10 CFR Part 50, and the design objectives given in Section 11.0 of Appendix 1 to 10 CFR Part 50. }

The specified limits governing the use of appropriate portions of the system i were specified as a suitable fraction of the dose design objectives set forth ,

in Sections II.B and II,C of Appendix 1,10 CFR Part 50, for gaseous effluents. I I

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RADI0 ACTIVE [fFLUENTS MSES 3/4.11.4 TOTAL DOSE This requirement is provided to meet the dose limitations of 40 CFR Part 190. The requirement requires the preparation and submittal of a Special f'eport whenever the calculated doses from plant generated radioactive effluents and direct radiation exceed 25 mrems to the total body or any organ, except the thyroid, which shall be limited to less than or equal to 75 mrems.

For sites containing up to 4 reactors, it is highly unlikely that the resultant dose to a MEMBER OF THE PUBLIC will exceed the dose limits of 40 CFR Part 190 if the individual reactors remain within twice the dose design objectives of Appendix 1, and if direct radiation doses from the reactor units and outside storage tanks are kept small. The Special Repart will describe a course of action that should result in the limitation of the annual dose to a MEMBER OF THE PUBLIC to within the 40 CFR Part 190 limits. For the purposes of the Special Report, it may be assumed that the dose commitment to the MEMBER OF THE PUBLIC from other uranium fuel cycle sources is negligible, with the exception that dose contributions from other nuclear fuel cycle facilities at the same site or within a radius of 8 km must be considered. if the dose to any MEMBER OF THE PUBLIC is estimated to exceed the requirements of 40 CFR Part 190, the Special Report with a request for a variance (provided the release conditions resulting in violation of 40 CFR Part 190 have not already been corrected), in accordance with the provisions of 40 CFR Part 190.11 and 10 CFR Part 20.405c, is considered to be a timely request and fulfills the requirements of 40 CFR Part 190 until NRC staff action.i; completed. The variance only relates to the limits of 40 CFR Part 190, and does not, apply in any way to the other requirements for dose limitation of 10 CFR Part 20, as addressed in Appendix A'Requiremeats 3.11.1.1 and 3.11.2.1. An individual is not considered a MEMBER OF THE PUBLIC during any period in which he/she is engaged in carrying out any operation that is part of the nuclear fuel cycle.

A-57 Draft

3/4.12 RAqlDLOGICAL ENVIRONMENTAL MONITORING

-BASES 3/4.12.1 MONITORING PROGRAM The radiological monitoring program required by this requirement provides-measurements of radiation and of radioactive materials in thosc exposure pathways and for those radionuclides, wnich lead to the highest potential radiation exposures of MEMBERS Of THE PUBLIC resulting from the station operation. This monitoring program implementsSection IV.B.2 of Appendix 1 to 10 CFR Part 50 and thereby supplements the radiological effluent monitoring program by verifying that the measurable concentrations of radioactive materials and levels of radiation are not higher than expected on the basis of the effluent measurements and modeling of the environmental exposure pathways.

The initially specified monitoring program will be effective for at least the first three years of commercial operation. Following this period, program changes may be initiated based on operational experience.

The detection capabilities required by Appendix A Table 4.12.1-1 are state-of-the-art for routine environmental measurements in industrial laboratories. It should be recognized that the LLD is defined as an "a priori" (before the fact) limit representing the capability of a measurement system and not as "a posteriori" (after the fact) limit for a particular measurement. Analyses shall be performed in such a manner that the stated LLDs will be achieved under routine conditions. Occasionally background fluctuations, unavoidably small sample sizes, the presence of interfering nuclides, or other uncontrollable circumstances may render these LLDs unachievable. In such cases, the contributing factors will be identified and described in the Annual Radiological Environmental Operating Report.

For a more complete discussion of the LLD. and other detection limits, see the following:

(1) HASL Procedure Manual, HASL-300 (revised annually).

(2) Currie, L. A.,." Limits for Qualitative Detection and Quantitative Determination - Application to Radiochemistry," Anal. Chem. 40, 586-93 (1968).

(3) Hartwell, J. K., " Detection Limits for Radioisotopic Counting Techniques," Atlantic Richfield Hanford Company Report ARH-2537 (June 22, 1972).

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RADIOLOGICAL ENVIRONMENTAL MONITORING BASES 3/4.12.2 LAND USE CENSUS This requirement is provided to ensure that changes in the use of areas at and bcyond the SITE BOUNDARY are identified and that modifications to the radiological environmental monitoring program are made if required by the results of the census. The best information from door-to-door survey, visual or ar; rial survey or from consulting with local agricultural authorities shall be used. This census satisfies the requirements of Section IV.B.3 of Appendix 1 to 10 CFR Part 50. Restricting the census to gardens of greater than 50 m' provides assurance that significant exposure pathways via leafy vegetables will be identified and monitored since a garden of this size is the minimum required to produce the quantity (26 kg/ year) of leafy vegetables assumed in Regulatory Guide 1.109 for consumption by a child. To determine this minimum garden size, the following assumptions were made: (1) 20% of the garden was used for growing broad leaf vegetation i.e., similar to lettuce and cabbage), and (2) a vegetation yield of 2 kg/m 3/4.12.3 INTERLABORATORY COMPARIS0N PROGRAM The requirement for participation in an approved Interlaboratory Comparison Program is provided to ensure that independent checks on the precision and accuracy of the measures of radioactive material in environmental sample matrices are performed as part of the quality assurance program for environmental monitoring in order to demonstrate that the results are valid for the purposes of Section IV.B.2 of Appendix 1 to 10 CFR Part 50.

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r SECTION 6.0 ADMINISTRATIVE CONTROLS l

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ADMINISTRATIVE CONTROLS ANNUAL RADIOLOGICAL ENVIRONMEtHAL_ OPERATING REPORT 6.9.1.6 Routine radiological environmental operating reports covering the operation of the unit during the previous calendar year shall be submitted prior to May 1 of each year.

6.9.1.7 The annual radiological environmental operating reports shall include summaries, interpretations, and an analysis of trends of the results of the radiological environmental surveillance activities for the report period, including a comparison with preoperational studies, operational controls (as appropriate), and previous environmental surveillance reports and an assessment of the observed impacts of the plant operation on the environment. The reports shall also include the results of land use censuses required by Appendix A Requirement 3.12.2.

If harmfyl effects or evidence of irreversible damage are detected by the monitoring, the report shall provide an analysis of the problem and a planned course of action to alleviate the problem.

The annual radiological environmental operating reports shall include summarized and tabulated results in the format of Regulatory Guide 4.8, December 1975 of all radiclogical environmental samples taken during the report period. Deviations from the sampling program identified in Appendix A Requirement 3.12.1 shall be reported. In the event that some results are not available for inclusion with the report, the report shall be submitted noting and explaining the reasons for the missing results.

The missing data shall be submitted as soon as possible in a supplementary report.

The reports shall also include the following: a summary description of the radiological environmental monitoring program; a map of all sampling locations keyed to a table giving distances and directions from one reactor.; and the results of licensee participation in the Interlaboratory Comparison Program, required by Appendix A Requirement 3.12.3.

SEMIANNUAL RADI0 ACTIVE EFFLUENT RELEASE REPORT 6.9.1.8 Routine radioactive release reports covering the operation of the unit during the previous 6 months of operation shall be submitted within 60 days af ter January 1 and July 1 of each year.

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ADMINISTRATIVE CONTROLS SEMIANNUAL RADI0 ACTIVE EFFLUENT RELEASE REPORT (Continued) 6.9.1.9 The radioactive effluent release reports shall include a summary of the quantities of radioactive liquid and gaseous effluents and solid waste released from the unit as outlined in Regulatory Guide 1.21,

" Measuring, Evaluating, and Reporting Radioactivity in Solid Wastes and Releases of Radioactive Materials in Liquid and Gaseous Effluents from

_ Light-Water-Cooled Nuclear Power Plants," Revision 1, June 1974, with data summarized on a quarterly basis following the format of Appendix B thereof.

The radioactive effluent release report to be submitted within 60 days after January 1 of each year shall include an annual summary of hourly meteorological data collected over the previous year. This annual summary may be either in the form of an hour-by-hour listing of wind speed, wind direction, and atmospheric stability, and precipitation (if measured) on magnetic tape, or in the form of joint frequency distributions of wind speed, wind direction, and atmospheric stability. This same report shall include an assessment of the radiation doses due to the radioactive liquid and gaseous effluents released from the unit or station during the previous calendar year. This same report shall also include an assessment of the radiation doses from radioactive liquid and gaseous effluents to MEMBERS OF THE PUBLIC due to their activities inside the SITE B0UNDARY (Technical Specification _ Figure 5.1.3-1) during the report period. All assumptions used in making these assessments, i.e., specific activity, exposure time and location, shall be included in these reports. The meteorological conditions concurrent with the time of release of radioactive materials in gaseot.s effluents (as determined by sampling frequency and measurement) shall be used for determining the gaseous pathway doses. The assessment of radiation doses shall be performed in accordance with the 0FFSITE DOSE CALCULATION MANUAL (0DCM).

The Semiannual Radioactive Effluent Release Report shall identify those radiological environmental sample parameters and locations where it is not possible or practicable to continue to obtain samples of the media of choice at the most desired location or time. In addition, the cause of the unavailability of samples for the pathway and the new location (s) for obtaining replacement samples should be identified. The report should also include a revised figure (s) and table (s) for the ODCM reflecting the new location (s).

The radioactive effluent release report to be submitted within 60 days after January 1 of each year shall also include an assessment of radiation doses to the likely most exposed MEMBER OF THE PUBLIC from reactor releases and other nearby uranium fuel cycle sources (including doses from primary effluent pathways and direct radiation)- for- the previous 12 consecutive months to show conformance with 40 CFR 190, Environmental Radiation Protection Standards for Nuclear Power Operation. Acceptable methods for calculating the dose contribution from liquid and gaseous effluents are r

given in Regulatory Guide 1.109, Rev.1.

The radioactive effluents release shall include the following information for each type of solid waste shipped offsite during the report period:

a. Container volume,

b. Total curie quantity (specify whether determined by measurement or estimate),

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ADMINISTRATIVE CONTROLS SEMIANNUAL RADI0 ACTIVE EFFLUENT RELEASE REPORT (Continued)

c. Principal radionuclide (specify whether determined by measurement orestimate),

d. Type of waste (e.g., spent resin, compact dry waste, evaporator bottoms),

e. Type of container (e.g., LSA Type A, Type B, large Quantity), and

f. Solidification agent (e.g., tement, urea formaldehyde).

The radioactive effluent release reports shall include unplanned rel-eases from the site to'the UNRESTRICTED AREA of radioactive materials in gaseous and liquid effluents on a quarterly basis.

The radioactive effluent release _ reports shall include any changes to the -

0FFSITE DOSE CALCULATION MANUAL (00CM) or radioactive waste systems made during the reporting period. ,

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ADMINISTRATIVE CONTROLS 6.15 MAJ07< CHANGES TO RADI0 ACTIVE WASTE TREATMENT SYSTEMS

6.15.1 Major changes to the radioactive waste systems, liquid, gaseous and solid:

1. Shall be reported to the Commission in the Semiannual Radioactive Effluent Release Report for the period in which the evaluation was reviewed by the PSRC. The discussion of each change shall contain:

a. A summary of the evaluation that led to the determination that the change could be made in accordance with 10 CFR 50.59;

b. Sufficient detailed information to totally support the reason for the change without benefit of additional or supplemental information;

c. A detailed description of the equipment, components and processes involved and the interfaces with other plant systems; l d. An evaluation of the change which shows the predicted l releases of radioactive materials in liquid and gaseous effluents and/or quantity of solid waste that differ from those previously predicted in the license application and amendments thereto;

e. An evaluation of the change which shows the expected maximum exposures to MEMBERS OF THE PUBLIC in the

, UNRESTRICTED AREA and to the general population that differ from those previously estimated in the license application and ::mendments thereto;

f. A comparison of the predicted releases of radioactive i materials, in liquid and gaseous effluents and in solid l waste, to the actual releases for the period prior to when i the changes are to be made;

g. An estimate of the exposure to plant operating personnel as l a result of the change; and l

l h. Documentation of the fact that the change was reviewed and l found acceptable by the PSRC.

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2. Shall become effective upon review and acceptance by the PSRC.

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The information called for in this Requirement may be submitted as part of the annual UFSAR update.

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PROPOSED REVISION OF Tile PROCESS CONTROL PROGRAM !

i GRAND GULF NUCIF.AR STATION "

(For ini'ormation Only) i, I

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S PROCESS CONTROL PROGRAM DESgRIP_ TION ,

i GRAND GULF NUCLEAR STATION 4

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P_889 DESCRIPTION APPROVli SilEET ........................................ 1 TABLE OF CONTENTS ................................................. 11 LIST OF EFFECTIVE PAGES ........................................... 111 A. Introduction .................................................-- 1 B. Administrative Controls ...................................... 2 C. Waste Streams ................................................ 2

' D. ' Conditioning of Wastos and Sampling _ for Verification of Solidification ~...................._........................ '3 s E. Sampling for Verification of Curie Content ................... 4 F. Specification for Radioactive Waste Solidification . . . . . . . . . . . 4 G. Changes to the PCP ........................................... 6 11 . Semiannual Radioactive Effluent Release Report ............... 6 11

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GRAND GULi', UNIT 1 DRAFT M9104302/SNLICFLR

GRAND GULF NUCLEAR STATION 'j

- P_ROCESS CONTROL PROGRAM (ICP)_ DES _CRIPTION-REQUIREMENTS FOR PROCESSING OF RADIDACTIVE- LigUIDS_AND WET _ SOLIDS A. Introduction-A. largo portion of the radioactive wasto produced in a nuclear power station is in a. form which is either 11guld (e.g., oil, oily sludge, EllC fluid, glycol) or in a wet solid form (n.g., resins, f i l t.or sludge) and requires. processing to obtain an acceptabin, solid, monolithic form for burial. - Some of this waste may bn _ sent to a licensed offsito vendor for volume reduction or other preparat.Jon for burial. Radwesto processing activit.ies at Grand Gulf Nuc1 car Statlon (GGNS)'are coordinated with the Radiation Control Section to ensure personnel exposures are kept. ALARA.

The GGNS Radwasto Solidification System was originally intended for the solidification of wet radioactive waste. Thn Installed solid radwasto system has never been utilized and vendor services are

~ employed for the processing of wet wastes.

Radioactive wot solids (powdored and bond resins) are processed by dewatering,_ vitrification or solidification to assurn thorn is no free-standing water. Dewatering of resins is performnd onsite by a

qualified vendor using a mobile dowatering system. Rosins are i dewatered in stool-liners or liigh Integrity Containers as_ necessary, according to vendor's proceduros. Resins may also be processed ,

offsito by vitrification at n' liennsed vendor facilit.y, or they may be dried and used as loosn fill material in' packages of supercompacted waste. .If the Contractor's PCP Topical Report for dewatering, solidification or vitrificat lon has bnen approved by the U.S. Nuclear Regulatory Commission (NRC), the approved report is

justif.ication to ensurn compliance with 10CFR20, 10CFR61, and

_10CFR71 as required by CGNS Technical Specifications. If the NRC L has not approved the Contractor's PCP Topical' Report, then it is thn

~ Plant Safet.y Review Committee's (PSRC) responsibilit.y to make certain that thn Contractor's equipment and procedures arn adequate to ensure compliance wit.h 10CFR20, 10CFR61, and 10CFR71.

Radioactive liquids (e.g. , oil, oily sludges, EllC fluid, glycol) may

' bn shipped of fsito for volumn reduction by-incineration or absorbed c and incinerated at a licensed vendor facility. Alternately, radioact.ivo liquids _ and wot solids, including rosius, may be "

solidified prior to disposal. Solidification may be performed onsite by a contractor utilizing a mobile solidification system or

of fsito at a licensod vondor f a c i l l t.y. I f the Contractor's - PCP Topical Report for incineration or solidification has been approved by the NRC, the approved rnport is just.Ification to ensure compliance with 10CFR20, 10CFR61, and 10CFR71 as required by GGNS GRAND GULF, UNIT 1 1 Rev. 3 - 04/90

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Technical Specifications. If thn NRC has not approved the Contractor's PCP Topical Report, then it is the PSRC's responsibility to make certain that the Contractor's equipment and procedures are adequate to ensure compliance with 10CFR20, 10CFR61, and 10CFR71.

If incineration, solidification or vitrification is to ho performed offsito at a 1iconsed vendor faci 1ity tbn waste wi11 be pncknged and shipped in accordance with the requirements in 49CFR. The processing facility will take title to the waste and cert ify that i t.

has been pioperly incinerated, solidified or vit rified prior to disposal.

B. Admin.istrative Conti;ols Compilance with 49CFR, 10CFR20, 10CFR61, 10CFR71 and stato and disposal site criterin is assured by adhnrenen to approved procedures and instructions. Adherence to GGNS and cont ractor procedures will be required for all act ivit.ies related to processing of radioactivn wasto for burial.

Directions for extensive or complex jobs where reliance on memory canr.ot bn trusted shall requir e the appr oprinto wr itten procedure to be present and referred to directly. Procedures shall include appropriato quantitativn and/or qualitative criteria for verifying that thn specified activities have been sat isfactorily accomplished.

Contractor procndures for onsit.e processing will be reviewed and approved by the Radwnstn OpernLlons Sectlon, Radiation Control Section and the PSRC, to ensurn compliance with thn applicable portions of the PCP. Chnnges to Contractor's procedures will be approved by the Endwast c Operat. ions Sect ion and Radiation Cont rol and screened for forwnrding to PSRC for review and approval when changes significantly a f fect. equipment or process parameters.

Documentation of thesn revtews end approvais wi11 be maintained as QA-records.

Documentation of pert inent dat.n required to classify waste will be mnintained on each batch of processed wnste as required by approved procedurns. Documentation will also be maint.ained to ensurn that containers, shipping casks, and methods of packaging wastes meet applienble Federal regulntions and disposal site criterin. Thesn documents w111 he mnintnined ns QA rocords.

C. Wasto Streams GGNS has five radwnste streams as foilows:

Stream #1 -

Condensate Pr acont. Filter Waste Stream #2 -

Ronctor Water Cleanup and Funi Pool Clennup Precoat Filter Waste GRAND GUhP, UNIT 1 2 Rev. 3 - 04/90 M9104302/SNLICFhR

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-Stream #3 -

' _ Liquid Radwasto Floor Drain and Equipment Drain Systems F.fiter Waste

-Stream'4 # -

Condensato and Liquid Radwaste Systems Demineralizer Wasto Resin Stream #5 "-

Contaminated Waste Oil Other waste streams will be designated as conditions warrant.

Occasional limited volumes of other wasto may also be processed, including 'out noc limited to, such liquids as EllC fluid and glycol. ,

D. Conditioning of Wasta and Sampling _ for Verification of Solidification

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A verification of the solidification of liquid radwastos must bn parformed on at least every tenth cont.alner in a batch of wasto, lloweve r . If trends indicato the: possibility of changing parameters

-which may hava an effect on the methods and materials used to ,

, produce a_ monolithic solid with no free-standing liquid, then moro frequent sampling may be required. When increased sampling is required, the-frequency.will be established by the Radiation Control Superintendent.

NOTE A Batch is defined as an isolated quantity of food waste t'o bo-processed having constant physical and-chemical character.istics; >

a quantity _of material that is determined to be a homogenous mixture for purposes of producing stable, solidified billets for disposal as radioactive wasto.

Examplo: - The contents of a waste holding / storage / mixing -tank

-that has been isolated (so that- additional waste cannot be -

introduced) would constitute a batch.

Verification'of solidification'shall bo performed as=follows:

-a) Thron test samples will be taken from the batch. The normal sample-volumo as specified in approved procedures will be used unless radiological condit f ons necessitato a smaller volumn.

b) The solidifying agents will be added_to the test samples in different proportions.

c) The test samples will be allowed to set or curo.

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d) Af ter curing, thn proportions of thn- solidificat lon agents which produced'tho_ maximum practica1 compressivo strengths sha11 be

-used.-

NOE The most stable billet does not have to be used, but 'the objectivo.js not simply to achieve the minimum-acceptablo compressivo strength.

n) If none of the samples are found to be satisfactory, the test shall bn repeated until an acceptablo solidirand billet with no free-standing liquid is obtained. '

For- batches of misenllaneous wastes, a vnrificat.f on of solidification analysis will be pntformnd as specified in steps a) through n) above. '

If a. contractor is performing solidification services, then the contractor will specify- the chemical analysis requirements and the acceptablo ranges for the physical and chemical charactoristics of the wast o being processed- according to contractor's proceduren. - - The contractor's. procedures shall tdress correctivo act.fons to be taken if samplos fail to verify solidification or the absence of free-standing liquids.

The proportions 'of- the solidification agents used for the test batch

. producing the maximum practical compressivo strengths for the verification of solidification shall be used for subsequent batches of-the same wanta stream.

E. . SampLt.ng ,,for Vori f tention of Cur.f e Content. -

An isotopic.nnalysis shal.1 bn performed on at least overy tenth.

container in a batch of each wanto stream so that the wastn can be classi fied in accordance wit h 10CFR61. . Ilownver, more frequent

-analysis may.bn perforred if doomed necessary by the Radlation Control Superintendenc.

The isotopic and curin content of each shipping container shall be determined in accordance wit h -49CFR packaging requirements. The

total activity in the container may bo determinnd by olther isotopic analysis or by dose-rato-to-curio conversion.

l- P.- Specification _ for Radioactive Wasto Solid.l_f f_ cation

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Solidification is deflood as the conversion of wet wastes into a form that monts shipping and burial ground requirements.

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l MMITl_NG . CONDITION .FOR 01 ERAT 10N , __ _ ___ _ _ ___

The solid radwnste system shall be u. sed in accordance with n Process Control Program to process wet radionctive wastes to meet shipping and burial ground requitements.

APPhlCABil>lTY : At all times.

ACT_1.ON :

With the provisions of the Process Control Program not satisfied, suspend ,

shipments of defectively processed or defectively pnckaged solid radionetlyn wastes from the s it e.

SURyEIhhANCE_REQU1REMENTS_ _ _ . _ . . _ _ _ . .

The Process Control Program shall be used to verify the sol id i f i ca t ion

of at least one represcut ative test specimen from at least every tenth batch of each type of wet- rndionetive waste, a) If any test specimen fails t o veri fy solidi f ica t ion *, the solidificat ion

of the hatch under test shall be suspended until such time as addit.ionni test specimens can be obtnined, alt ernative solidification

paramet ers enn be determined in accordance with t he Process Control Program, and a subsequent test verifies solidification *. Solidificat ion

of the batch may then be resumed using the alternative solidifient ion

parnmeters determined by the Process Control Program, b) If the initial test specimen from a b9tch of the waste fails to vnri fy solidificat ion,* the Process Control Program shall provide for the collection and testing of representative test specimens from each consecut.tvo bat ch of the same type of wet waste until at least 3 consecutive inittal test specimens demonstrate solidifiention*.

The Process Cont rol Program shall be modified as required, as provided in Technical Specification 6.13, to assure solid i ficat ion

of subsequent bat ches of waste.

BASES These procedurni details implement the requirements of 10CFR Part 50.36n and General Design Crit erion 60 of Appendix A t o 10CFR Part 50 The process parameters included in establishing the Process Control Program may include, but nrn not limited to, waste type, waste pH, waste / liquid / solidi fication agent / catalyst ratios, waste oil content, waste principal chemical constituents, mixing and curing times.

Except downtering.

GRAND GUhP, UNIT 1 5 DRAFT M9104302/SNh1CFhR

G. Changes to the,PCP Chnnges to the PCP shall be accomplished as specified in Technicnl Specificntion 6.13. Records of Ievlews performed for changes made to the PCP nhall be retained for the duration of the Unit Opernt ing 1,1censo as per Technical Specification 6.10.2.

11 . Seminnnpl Rn.slionet he Ef fluent Relens.n Report l . NOTE This section out lines t he solid waste information required for the Seminnnun1 RndlonttIve Effluent Release Report. For a listing of all l' 7tton required, including radioactive liquid and gnseous effluents and solid wnste, consult the ODCM.

Routinn radioactive release reports covering the operation of the unit during the previous 6 months of operation shall be submitted within 60 days af ter Janunty i nnd July 1 of ench year as specifled in Technical Specificat. inn 6.9.1.8.

The Seminnnunt Radioacti.ve Effluent Release Repott shnll include:

a) A summary of the quantitles of radioactIvo sol.id waste released from the unit ns out1ined in Regulatory Guide 1.21, " Measuring.

Evaluat ing, and Report ing Rr.dioact ivity in Solid Wastes and Releases of Radioacti.ve Materinis in 1.1 quid and Gaseous Effluents from 1.ight-Water-Cooled Nuctenr Power Plants,"

Revision 1, June 1974, with data summarized on a quarterly basis following thn format of Appendix B thereof b) The following information for each type of solid waste shipped offsite during the report period:

1) Container solume,

2) Tot al curie quant ity (speci fy whether det ermined by measurement or estimate),

3) Principal radionuclide (specify whet her .letermined by measurement or estimate),

4) Type of waste (e.g., spent resin, compact dry waste, evaporator bottoms),

5) Type of container (e.g. , l.SA, Type A, Type B, 1,nrge Quantity), and

6) Solidi ficat ion ngent (e.g. , cement, uren formablebyde).

GRAND GUhr, t! NIT 1 6 DRAFT M9104302/SNhlCFl.R

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NDTE sf Tbn luformation called for in c) may he submitted as part of the annun t FSAR upant e.

c) hicensea-initinted major changes to the radionctivo solid wanto systems for the period in which the evaluntion was reviewed by the PSRC, These changes shnll become effectivo upon review and acceptance by the PSRC. The discuss f on of each change shall contain:

1) A summary of the evaluntion thnt led to the determ' a that the chnnge could be mnde in accordnnce with 10CFR50.59;

2) Sufficient det ailed informat ion to t ot ally support the reason f or t he change without benefit of additional or supplemental informatlon;

3) A detnited description of thn equipment, con.conents and processes involved and the juterfacns with otin pinnt systems;

4) An evaluntion of the chnnge which shows the predicted relenses of radionctive materints and/or quant ity of solid waste that differ from thoso previously predicted in thn 1icense appltention and amendments thereto;

5) An evaluntion of the change which shows the expected maximum exposnres to MEMitERS OF Tile PUBl.1C in the UNRESTRICTED AREA and to thn general populat ton thnt dif fer from those previously estimated in the license application and amendments thereto; ,

6) A comparison of the predicted releases of radioactive materials, i ti solid waste, to the actual releases for the period prior to when the changes are to be mndn;

7) An est imate of the exposurn to plant. operating personnel as ,

a result. of t he change; nnd

8) Document at ion of t he fact that the change was reviewed and foutul nrceptable by the PSRC.

GRAND GULF, UNIT 1 7 DRAFT M9104 302/ SNLICFI.R

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