ML20108A269

Rev 17 to ODCM

ML20108A269
Person / Time
Site:	Grand Gulf
Issue date:	03/10/1995
From:	ENTERGY OPERATIONS, INC.
To:
Shared Package
ML20108A237	List: ML20108A236 ML20108A251 ML20108A269
References
PROC-950310, NUDOCS 9605020195
Download: ML20108A269 (160)

Text

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1 1

OFFSITE DOSE CALCULATION MANUAL l l

l GRAND GULF NUCLEAR STATION l

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l GRAND GULF, UNIT 1 Revision 17 - 03/95 9605020195 960502 PDR ADOCK 05d00416 ,

PDR R

l Revision No. 17 Date 03/95 CRAND GULF NUCLEAR STATION OFFSITE DOSE CALCULATION MANUAL SAFETY RELATED EV1UT1_ TION APPLICABfLTTY SAFETY EVALUATION ENVIRONMpITAL EVALUATION

( ( APPLICABLE () APPLICABLE

() NOT APPLICABLE ( N APPLICABLE Reviewed / Approved: AN / 2 *11

• i I Preparer Date Reviewed / Approved: [- # / 2 22 - 9 f"~~

Reviewer

' Date

/

Reviewed / Approved:

Chemistry superintaneent Date Reviewed / Approved: ( . b e--- /2k/

Manager, Plant Opetati'odp Date Reviewed / Approved - -" -3. /4# A~ / J/ f S~~

Chairmah Plant Safety Review Committee Date Reviewed / Approved: ( 4MAAAM/ Ol[ / 9//& /r Goheral Manager, Plant Operati

'Date i

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f GRAND GULF, UNIT 1 i Revision 17 - 03/95 l

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IFrRQDUCTION 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 CDCM also contains (1) the Radioactive Effluent Controls and Radiological Environmental Monitoring Programs required by Technical Specification (TS) 5.5.4, and Technical Requirement 7.6.3.2, (2) descriptions of the information that is included in the Annual Radiological Environmental Operating and Annual Radioactive Effluent Release Reports required by TS 5.6.2 and 5.6.3, (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 Wd4w A of the ODCM.

ODCM Revision 17 incorporates changes resulting from the Technical Specification Irgrovement Program (TSIP) . Changes includes e relocation of some information from Limiting conditions for operation (LCO) and Surveillance Requirements (SR) to the BASES, e deletion of redundant information (e.g. definitions, LCO/SR applicabilities, SR frequencies and information previously maintained in both the TS and the ODCM),

e reformatting the LCO and SR, e deleting blank pages, j e incorporating updated meteorological data into gaseous effluent dose l calculations.

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 the ODCM.

Changes to the ODOt shall be accomplished as specified in TS 5.5.1.

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Records of reviews performed for changes made to the ODCM shall be retained for the duration of the Unit operating License.

GRAND QULF, UNIT 1 11 Revision 17 - 03/95

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TABLE OF CONTENTS EASA

..... i MANUAL APPROVAL SHEET ....................................

INTRODUCTION ........................................ .......... 11 TABLE OF CONTENTS .............................................. iii LIST OF FIGURES ................................................ iv LIST OF TABLES ................................................. v LIST OF REFERENCES ............................................. vi EFFECTIVE PAGES ................................................ vii 1.0 LIQUID EFFLUENTS 1.1 Liquid Effluent Monitor Setpoints 1.1.1 Liquid Radwasto Iffluent Line Monitors ......... 1.0-1 1.2 Dose Calculations for Liquid Effluents 1.2.1 Maximum Rxposed Individual Model ............... 1.0-7 1.2.2 Dose Projection ................................ 1.0-8 1.3 Liquid Radwaste Treatment System . . . . . . . . . . . . . . . . . . . . . . . . . 1. 0-15 2.0 GASEOUS EFFLUENTS 2.1 Gaseous Effluent Monitor Setpoints 2.1.1 Continuous Ventilation Monitors ................ 2.0-1 l 1

2.0-3 2.1.2 Text Deleted ................................... {

2.2 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 2.2.3 Dose Projection ................................ 2.0-10b 2.3 Meteorological Model 2.3.1 Atmospheric Dippersion ......................... 2.0-24 2.3.2 Deposition ..................................... 2.0-25 l

2.4 Definitions of Gaseous Effluents Parameters .............. 2.0-27 2.5 Gaseous Radweste Treatment System ........................ 2.0-35 2.6 Annual Dose Coanniement .................................... 2.0-36 2.6.1 Direct Radiation Dose Measurement .............. 2.0-36 3.0 RADICIDGICAL ENVIRobSGNTAL MONITORING 3.1 S ampling I4 cations . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3.0-1 GRAND GULF, UNIT 1 iii Revision 17 - 03/95

9Et1 TAaLE OF CONTENTS F.ana APPENDIX A - RADIOLOGICAL EFFLUENT CONTROLS AND A-O RADIOIZX2ICAL ENVIRONWNTAL MONITonTNG PROGRAMS DEFINITICNS A-2 1.1 GASEOUS RADWASTE TREAIMENT (OFFGAS) SYSTEM 1.2 MEMBER (e) OF THE PUBLIC 1.3 OFFSITE DOSE CALCULATION MANUAL (CDCM) 1.4 PROCESS CONTROL PROGRAM (PCP) 1.5 SITE BCUNDARY 1.6 UNRESTRICTED ARIA 1.7 VENTILATION EXHAUST TREATMENT SYSTEM SURVEILLANCE FREQUINCY NOTATION (DELETED) ............................A-4  ;

l MODES OF OPERATION (DELETED) .........................................A-5 APPLICABILITY (DELETED) ..............................................A-6 ADMINISTRATIVE CONTROLS ..............................................A-8 5.6.2 Annual Radiological Environmental Operating Report ...........................................A-9 5.6.3 Annual Radioactive Effluent Release Report .............................................A-10 GRAND GULF, UNIT 1 iiia Revision 17 - 03/95

EH TABLE OF CONTENTS EASA LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS ..... A-12 6.3 INSTRUMENTATION MONITORING INSTRUMENTATION 6.3.9 Radioactive Liquid Effluent Monitoring Instrumentation ............................... A-13 6.3.10 Radioactive' Gaseous Effluent Monitoring Instrumentation ............................... A-18 6.11 RADIOACTIVE EFFLUENTS LIQUID EFFLUENTS 6.11.1 Concentration ................................... A-29 6.11.2 Dose / Total Dose ................... ............. A-34 6.11.3 Liquid Waste Treatment .......................... A-36 GASEOUS EFFLUENTS 6.11.4 Dose Rate ....................................... A-37 6.11.5 Dose - Noble Gases / Total Dose ................... A-42 6.11.6 Dose - Iodine-131, Iodine-133, Tritium, and Radionuclides in Particulate Fom/ Total Dose . . A-44 6.11.7 Gaseous Radwaste Treatment ...................... A-46 ,

6.11.8 Ventilation Exhaust Treatment ................... A-47 6.12 RADIOLOGICAL ENVIRONMENTAL MONITORING 6.12.1 MONITORING PROGRAM AND .

I INTERLABORATORY COMPARISON PROGRAM .............. A-48 6.12.2 LAND USE CENSUS ................................. A-59 i,

GRAND GULF, UNIT 1 iiib Revision 17 - 03/95

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TABLE OF CONTENTS I

P.asa gagn .............................................................. A-61 6.3 INSTRUMENTATION MONITORING INSTRUMENTATION 6.3.9 Radioactive Liquid Effluent Monitoring Instrumentation ............................... A-62 6.3.10 Radioactive Gaseous Effluent Monitoring Instrumentation ............................... A-62 6.11 RADIOACTIVE EFFLUENTS i

LIQUID EFFLUENTS l 6.11.1 Coucentration ................................... A-63 6.11.2 Dose / Total Dose ............................ .... A-63 l 1

6.11.3 Liquid Waste Treatment .......................... A-66 '

GASEOUS EFFLUENTS 1 I

6.11.4 Dose Rate ..................................... . A-66

. 6.11.5 Dose - Noble Gases / Total Dose ................... A-67 6.11.6 Dose - Iodine-131, Iodine-133 Tritium and Radionuclides in Particulate Form / Total Dose .. A-69 6.11.7/ Gaseous Radwaste Treatment and Ventilation 6.11.8 Exhaust Treatment ............................... A-71 6.12 RADIOLOGICAL ENVIRONMENTAL MONI'IORING 6.12.1 MONITORING PROGRAM AND INTERLABORATORY COMPARISON PROGRAM .............. A-72 6.12.2 LAND USE CENSUS ................................. A-73 GRAND GULF, UNIT 1 iiic Revision 17 - 03/95

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CDCM l

List OF FIGURES l

l Title Pace Fieure 1.0-1 Example Calibration Curve for Liquid Effluent Monitor.... . 1.0-6 1.0-16 1.3-1 Liquid Radwaste Treatment System..........................

Plume Depletion Ef f ect f or Ground-Level Releases. . . . . . . . . . 2.0-31 2.3-1 2.0-32 2.3-2 Vertical Standard Deviation of Material in a Plume........

2.3-3 Relative Deposition for Ground-Level Releases............. 2.0-33 Open Terrain Recirculation Factor......................... 2.0-34 2.3-4 l 2.0-35a l 2.5-1 Gaseous Radwaste Treatment System.........................

3.0-1 Collection Site Locations, 0-5 Mile Area Map.............. 3.0-7 3.0-2 Collection Site Locations, General Area Map, 3.0-8 0 10 Mile Area Map........................................

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GRAND GULF, UNIT 1 iv Revision 17 - 03/95

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LIST OF TABLES Table Title Pace 1.2-1 Bioaccumulation Factors................................... 1.0-9 f

1.2-2 Ingestion Dose Conversion Factors For Adults.............. 1.0-10 1.2-3 Site Related Ingestion Dose Comunitment Factor. . . . . . . . . . . . . 1. 0-13 2.1-1 Dose Factors for Exposure to a Semi-infinite Cloud of Noble Gases...................................... 2.0-6 2.2-la Pathway Dose Factors for LCO 6.11.4 and Section 2.2.1.b........................................ 2.0-11 2.2-1b Pathway Dose Factors for LCO 6.11.4 and Section 2.2.1.b........................................ 2.0-13 2.2-2a Pathway Dose Factors for LCO 6.11.6 and Section 2.2.2.b........................................ 2.0-15 2.2-2b Pathway Dose Factors for LCO 6.11.6 and Section 2.2.2.b........................................ 2.0-17 2.2-2c Pathway Dose Factors for LCO 6.11.6 and Section 2.2.2.b........................................ 2.0-19 2.2-2d Pathway Dose ~ Factors for LCO 6.11.6 and Section 2.2.2.b........................................ 2.0-21 i

I 2.2-3, Controlling Receptors, Locations and Atmospheric 2.2-3a, Dispersion Parameters for LCOs 6.11.4, 6.11.5, l 2.2-3b 6.11.6 and 6.11.8.......................................... 2.0-23 l

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i 2.3-1 Deleted.................................................... 2.0 26 3.0-1 Air Sampler Collection Sit es . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3 . 0-2 3.0-2 Miscellaneous Collection Sites............................ 3.0-3 3.0-4 3.0-3 TLD Locations.............................................

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GRAND GULF, IntIT 1 y Revision 17 - 03/95

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QEU LIST oF REFERENCIS

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 witn 10CFR50, Appendix I, U.S. NRC Regulatory Guide 1.109 (March 1976).

4 3. Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Congliance with 10CFR50, Appendix I, U.S. NRC Regulatory Guide 1.109, Rev. 1 (October 1977).

4. " Environmental Report," Mississippi Power and Light Company, Grand Gulf l Nuclear Station, Units 1 and 2.

5. " Final Safety Analysis Report," Mississippi Power and Light Company, Grand Gulf Nuclear Statica.

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 Effluents in Routine Releases from Light - Water - Cooled Reactors, U.S.

NRC Regulatory Guide 1.111, Rev. 1 (July 1977).

8. Age-Specific Radiation Dose Conunitment Factors for a One-Year Chronic Intake, NUREG-0172, November 1977.

9. EER 93-6246 *X/Q and D/Q Atmospheric Dispersion and Deposition , Factors".

10. NPE Calculation #XC-Q1111-G4002, Revision 0.

GRAND GULF, UNIT 1 vi Revision 17 - 03/95

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LIST dF EFFECTIVE PAGES PAGE REV PAGE REV L L L U2a.

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i 17 2.0- 16 17 11 17 2.0-17 17 iii 17 2.0-18 17 l

iiia 17 2.0-19 17 I iiib 17 2.0-20 17 l iiic 17 2.0-21 17 l iv 17 2.0-22 17 v 17 2.0-23 17 2.0-23a 17 2.0-23b 17 l vi 17 2.0-24 17 vii 17 2.0-25 17 viia 17 2.0-26 17 1.0-1 17 2.0-27 3 t

I 1.0-2 17 2.0-28 5

. 1.0-3 17 2.0-29 3 l 1.0-4 15 2.0-30 3 l 1.0-5 17 2.0-31 15 1.0-6 15 2.0-32 15 l

l 1.0-7 17 2.0-33 15 1.0-8 17 2.0-34 15 1.0-9 11 2.0-35 17 1.0-10 0 2.0-35a 8 1.0-11 11 2.0-36 17 1.0-12 0 2.0-37 17 1.0-13 2 1.0-14 11 3.0-1 17 l 1.0-15 8 3.0-2 17

! 1.0-16 17 3.0-3 15 3.0-3a 17 2.0-1 17 2.0-2 17 3.0-4 15 2.0-3 2 3.0-5 17 2.0-4 12 3.0-6 15 i 2.0-5 12 3.0-6a 17 2.0-6 0 3.0-6b 13 2.0-7 17 3.0-6c 15 l

2.0-8 17 3.0-6d 17 2.0-9 17 3.0-7 17

! 2.0-10 17 3.0-8 17

! 2.0-10a 17 2.0-10b 17 2.0-11 17 2.0-12 17 2.0-13 17 2.0-14 17 i

2.0-15 17 GRAND GtEF, UNIT 1 vii Revision,17 - 03/95

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M LIST OF trrscriVE M PAGE REV PAGE REV E L HL, E

Annandir A A-C 17 A-34 17 A-1 17 A-35 17 A-2 17 A-36 17 17 A-37 17 A-3 17 A-4 17 A-38 17 A-39 17 A-5 17 A-6 17 A-40 17 A-41 17 A-7 17 A-8 17 A-42 17 A-43 17 A-9 A-10 17 A-44 17 A-11 17 A-45 17 A-12 17 A-46 17 A-13 17 A-47 17 A-14 17 A-48 17 A-15 17 A-49 17 A-16 17 A-50 17 A-17 17 A-51 17 A-18 17 A-52 17 A-19 17 A-53 17 A-20 17 A-54 17 A-21 17 A-55 17 A-22 17 A-56 17 A-23 17 A-57 17 A-24 17 A-58 17 A-25 17 A-59 17 A-26 17 A-60 17 A-27 17 A-61 17 A-28 17 A-62 17 A-29 17 A-63 17 A-30 17 A-64 17 A-31 17 A-65 17 A-32 17 A-66 17 A-33 17 A-67 17 A-68 17 A-69 17 A-70 17 A-71 17 A-72 - 17 A-73 17 A-74 17 i

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I GRAND GULF, UNIT 1 viia Revision 17,- 03/95

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t 1.0 LIQUID EFFLUENTS 1.1 Liauld Effluent Manitor Setnoints 1.1.1 Licuid Radwaste Effluent Lina Monitors Liquid Radwaste Effluent Line Monitors provide alana and automatic termination of. release prior to exceeding ten times the concentration limits specified in 10CFR20, l Appendix B, Table 2, Column 2 at the release point to the ,

l unrestricted area. To meet this specification and for the f

urpose of implementation of LCO 6.3.9, the alarm / trip l l

setpoints for liquid effluent monitors and flow measurement l l

devices are set to assure that the following 1 i )

equation is satisfied:

1L s C F+f (1) where: j C= con times the offluent concentration limit (LCo 6.11.1) inglementing 10CFR20 for the site, in pCi/ml. )

I c= The setpoint, representative of a radioactivity  !

l concentration in pCi/m1, of the radioactivity monitor l

! i measuring the radioactivity in the waste tank effluent j line prior to dilution and subsequent release; the l

setpoint, which is inversely proportional to the volumetric flow of the effluent line and directly proportional to the volumetric flow of the dilution stream plus the waste tank effluent stream, represents a value which, if exceeded, would result in l

concentrations exceeding ten times the limits of 10CFR20 in the unrestricted area.

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I f= the waste tank effluent flow setpoint as measured at a

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 effluent concentration, l C. The method by which this is accoglished is as follows:

Step 1) The isotopic concentration for a waste tank to be released )

is obtained from the sum of the measured concentrations as determined by the analysis required in ODCM Table 6.11.1-1:

+C + EC +C +C (2)

EC i g=gEC9

• s a e f where:

EC = the sum of concentrations C gof each measured gama gg emitter observed by gansna-ray spectroscopy of the waste sagle.

C, = the concentration C, of gross alpha emitters in liquid waste 'as measured in the toonthly composite sample.

l E,C, = the measured concentrations of Sr-89 and Sr-90 in liquid waste as observed in the quarterly composite sample. -

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C = the measured concentration of H-3 in liquid waste as g

determined from analysis of the monthly composite l l

sample.

Cg = the concentration of Fe-55 in liquid waste as measured in the quarterly composite sample.

The C term will be included in the analysis of each waste g

tank batch to be released; terms for alpha, strontiums, tritium and iron are included if analysis of liquid waste has shown the presence of these isotopes.

l 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 effluent flow rate required to assure that ten times the limiting concentration of 10CFR20, W ad4w B, Table 2, Column 2 are met at the point of discharge.

D.F. = [E i ] x S.F.

1 EC g C C C C C

= (E 9+ *+E s, e, f] x S.F. (3) g EC a EC EC g EC, EC, where:

C -C and C ; measured concentrations as

,C,,C,,C g defined in Step 1. Terum C,, C,, Cg and C g will be included in the calculation as appropriate.

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l GRAND GULF, UNIT 1 1.0-3 Revision 1'7 - 03/95

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IC g- ICg, EC,, EC,,EC g and ECg are tan times the limiting concentrations of the appropriate radionuclide from 10CFR20, Appendix B, Table 2, Coluan 2. For dissolved or entrained noble gases, the concentration shall be limited to 2.0E-4 gci/mi total activity.

S.F. . an administrative safety factor normally applied at Grand Gulf which causes the calculated Dilution l Factor to be two (2) times larger than the dilution factor required for compliance with ten times 10CFR20 limits.

Step 3) The maximum pe:missible waste tank effluent flow rate prior to dilution, f' * ** *** ** "* * #****

• d the dilution flow rate, F

• d F + f F f s d d , d (4) d D.F. D.F. for Fd >>fd where:

F = 0.9 x minimum expected dilution flow rate d

f = maximum permissible waste tank effluent flow rate d #

D.F. = Dilution Factor from Step 2.

NOTE: Equation 4 is valid only for D.F.>1; for D.F.si, the waste tank effluent concentration meets the limits of ten times the limiting concentrations of 10CFR20 without dilution, and f may ta e n any es red 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 dilution flow rate (5) f=

0.9 x fd = 0.9 x cal mlated M aum waste t d n ow rate for the stated release conditions. (6)

GRAND GULF, UNIT 1 1.0-4 Revision 15 - 01/94

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 effluent flow rate, the release is terminated (manually or automatically).

Step 5) The radioactivity monitor setpoint may now be specified based on the values of EggC , F, and f which were specified to provide compliance with ten times the limits of 10CFR20, Appendix B, Table 2, Column 2. The monitor response is primarily to ganna radiation, therefore, the actual setpoint is based on E C . The setpoint concentration, Cm, is gg determined as follows:

f d EC (7)

C m

=

g g g (pci/ml) a waste tank where f, is the actual (or maximum expected) effluent flow rate. The value of C, (gC1/ml) is used to determine the monitor setpoint (CPM) from a calibration curve similar to CDCM Figure 1.0-1.

NOTE: Setpoint adjustments are not required if the existing setpoint corresponds to a lower count rate than the calculated value. The actual monitor setpoint is determined from the measured concentration plus background for the detector. 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 effluent flow rate margin, and the dilution flow rate margin. In practice, the actual waste tank effluent flow rate normally is many times less than the calculated tank flow rate, thus providing an additional conservatisa during release.

GRAND GULF, UNIT 1 1.0-5 Revision 17 - 03/95

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. '.r' .:j' ,

. . -t-1._ .

.g.

gg -, .... .

- 7.! ...! J . ' , ;

JM I

C '~C "~

... . . . .~".2; .

'*". 1 -".'.

+

1

. , . ..-. .-. .. .t.... _. -- s 1

1 ..a,. a a - .:. aa a a a 4-10 10 l 10 l Count Rate (Counts per Minute) 4 i

GRAND GULF, UNIT 1 1.0-6 Revision 15 - 01/94

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

(

i

~

1.2 Dese calculations for Lieuid Effluents l 1

1.2.1 Mari= = Exnosed Individuni 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 LCO 6.11.2, 6.11.3, and TS 5.6.3 using the following expression:

m (1)

U At g C gg F) (millirem) (8)

Tau " f A iTau f[g g where:

A = Site-related ingestion dose connaitment factor for radionuelide i, in millirem /hr per uC1/ml.

=K U, BFg DF g Atg = length of the time pedod our which Cif and Fg are averaged for all waste tank liquid releases, in j hours.

""#*I* * ""*""#** * #" "* * **"*

Cit "

the undiluted waste tank liquid offluent during time period Atg from any liquid release from the waste tank, in gCi/ml. Concentrations are determined primarily from a gansna isotopic analysis of the waste tank, liquid effluent sample. For Ye-55, 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 values are not used in dose calculations.

GRAND GULF, UNIT 1 1.0-7 Revision 17 - 03/95

F g = near field average dilution factor for Cg 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 froir. the site discharge structure to unrestricted receiving waters times the applicable factor of 2(5) ,

= averaae imd41uted lieruid waste flow average flow from site discharge x 2 K = units conversion factor 1.14 x 10'

= 10 ggi x 10 31 + 8766 hg i

gC1 kg yr U, = adult fish consumption (21 kg/yr) '.

BF g = Bioaccumulation factor for each nuclide, i, in fish, I in pCi/kg per pCi/1 from CDCM Table 1.2-1.

I DF g = Dose conversion factor for each nuclide, i, for i adults in preselected organ, Tau, in area /pci, fron l ODO4 Table 1.2-2.

Calculated values of A g for radionuclides which might be I observed in liquid effluents are given in ODCM Table 1.2-3.

1.2.2 Dose Proiaccion i

j Doses from liquid effluents to UNRESTRICTED ARIAS are projected at least every 31 days as required by LCO 6.11.3.

These projections are made by averaging the doses (Dhu}

from previous operating history (normally the previous six i

months) which is indicative of expected future operations.

k i

A i

,I . .

i GRAND GULF, UNIT 1 1.0 3 Revision 17 - 03/95

1 i

i 1

] Timf.r 1.2 1 IIQACCUMULATION FACTORS. (BFg )

(pC1/kg per pC1/11ter)

• FRESHWATER ,

ELEMENT flag INVIRTIERATE j i H 9.0E-01 9.0E-01 C 4.6E+03 9.1E+03 i 1.0E+02 NA 2.0E+02 P 1.0E+05 2.0E+04 CR 2.0E+02 2.0E+03 MN 4.0E+02 9.0E+04 FE 1.0E+02 3.2E+03 CO 5.0E+01 2.0E+02 NI 1.0E+02 1.0E+02 CU 5.0E+01 4.0E+02 ZN 2.0E+03 1.0E+04 BR 4.2E+02 3.3E+02 RB 2.0E+03 1.0E+03 1 SR 3.0E+01 1.0E+02 Y 2.5E+01 1.0E+03 ZR 3.3E+00 6.7E+00 NB 3.0E+04 1.0E+02 MO 1.0E+01 1.0E+01 TC 1.5E+01 5.0E+00 RU 1.0E+01 3.0E+02 RH 1.0E+01 3.0E+02 SB 1.0E+00 1.0E+01 l

,~

TE 4.0E+02 6.1E+03 '

I 1.5E+01 5.0E+00 ,

CS 2.0E+03 1.0E+03 l BA 4.0E+00 2.0E+02 LA 2.5E+01 1.0E+03 CE 1.0E+00 1.0E+03 i PR 2.5E+01 1.QE+03 l 1 ND 2.5E+01 1.0E+03 i W 1.2E+03 1.0E+01 NP 1.0E+01 4.0E+02 Values in Table 1.2-1 are taxon from Reference 3 Table A-1, except for SB which was taken from Reference 2, Table A-8.

4 GRAND GULF, UNIT 1 1.0-9 Revision 11' - 06/88

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

? l i

i l

l l TARM 1.2 2 . I

! INGESTION ppSE CONVIRSION FACTORS FOR ADULT 4. (DF ) i (mrom per pC1 ingested) l' i

j Page 1 of 3 l NUCLIDE BONE LIVER T. BODY THYROID KIDNEY LUNG GI-LLI 1 M 3 NO DATA 1.05E-07 1.05E-07 1.05E-07 1.05E-07 1.05E-07 1.C5E-07 l 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 1.703 06 1.70E-06 1.70E-06 4

P 32 1.93E-04 1.20E-05 7.46E-06 NO DATA NO DATA NO DATA 2.17E-05 1 CR 51 NO DATA NO DATA 2.66E-09 1.59E-09 5.86E-10 3.53E-09 6.69E-07 i MN 54 NO DATA 4.575-06 8.72E-07 NO DATA 1.36E-06 NO DATA 1.40E-05 MN 56 NO DATA 1.155-07 2.04E-08 NO DATA 1.46E-07 NO DATA 3.67E-06 f FE 55 2.75E-06 1.90E-06 4.43E-07 NO DATA NO DATA 1.06E-06 1.09E-06 4

FE 59 4.34E-06 1.025-05 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 4.025-05 NI 63 1.30E-04 9.01E-06 4.36E-06 NO DATA NO DATA NO DATA 1.885-06

...................................................................................... 1 NI 65 5.28E-07 6.86E-08 3.13E-05 NO DATA NO DATA NO DATA 1.745-06 i CU 64 NO DATA 8.33E-08 3.91E-08 NO DATA 2.10E-07 NO DATA 7.105-06 ZN 65 l 4.84E.06 1.54E-05 6.965-06 NO DATA 1.033-05 NO DATA 9.705-06 1 ZN 69 1.03E-08 1.975-08 1.37E-09 NO DATA 1.285-08 NO DATA 2.96E-09 BR 83 NO DATA NO DATA 4.02E-08 NO DATA NO DATA NO DATA 5.79E-08  !

BR 84 NO DATA NO DATA 5.21E-08 NO DATA NO DATA NO DATA 4.09E-13 BR 85 NO DATA NO DATA 2.14E-09 NO DATA NO DATA NO DATA LT E-24 RB 86 NO DATA 2.11E-05 9.83E-06 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 5.36E-19 RB 89 NO DATA 4.01E-08 2.82E-05 NO DATA NO DATA NO DATA 2.33E-21 SR 89 3.08E-04 NO DATA 8.84E.06 NO DATA NO DATA NO DATA 4.943-05 SR 90 7.58E-03 NO DATA 1.86E-03 NO DATA NO DATA NO DATA 2.19E-04 SR 91 5.67E-06 NO DATA 2.29E-07 NO DATA NO DATA NO DATA 2.70E-05 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 2.585-10 NO DATA NO DATA NO DATA 1.02E-04 Y 91M 9.09E-11 NO DATA 3.52E-12 NO DATA NO DATA NO DATA 2.67E-10 Y 91 1.41E-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.

GRAND GULF. UNIT 1 1.0 10 Revision 0 - 08/82

4 l

i t

, tant.w 1.2 2 f emi-M l INGESTION DOSE CONyIRSION FACTORS FOR ADULTS. (DF )

g (mrom per PC1 ingested)

• i Page 2 of 3 4 l

NUCLIDE SONE LIVER T. BODY THYROID KID 0 FEY LUNG GI-LLI Y 93 2.6tE-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-05 NO DATA 3.09E-05 ZR 97 1.68E-09 3.39E-10 1.55E-10 NO DATA 5.125-10 NO DATA 1.05E-04

, NB 95 6.22E-09 3.465-09 1.065-09 NO DATA 3.423-09 NO DATA 2.10E-05

! MO 99 NO DATA 4.31E-06 8.20E-07 NO DATA 9.763-04 NO DAM 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 6.595-09 1.87E-10 1.10E-21 RU103 1.85E-07 NO DATA 7.975-08 NO DATA 7.065-07 NO DATA 2.16E-05 RU105 1.54E-08 NO DATA 6.08E-09 NO DATA 1.995-07 NO DATA 9.42E-06 i

RU106 2.75E-06 NO DATA 3.48E 07 NO DATA 5.313-06 NO DATA 1.78E-04

, AQ110M 1.60E-07 1.485-07 8.795-05 NO DATA 2.91E-07 NO DATA 6.043-05 58124 2.80E-06 5.293-08 1.11E 06 6.795-09 0.0 2.18E-06 7.955-05

• SE125+D 1.79E-06 2.00E-08 4.26E-07 1.82E-09 0.0 1.38E-06 1.975-05 S5126 1.15E-06 2.34E-08 4.155-07 7.045-09 0.0 7.05E-07 9.403-05 53127 2.58E-07 5.65E-09 9.903-08 3.105-09 0.0 1.53E-07 5.90E-05 i TE125M 2.68E-06 9.71E.07 3.59E-07 0.063-07 1.095-05 NO DATA 1.07E-05 I TE127M 6.77E-06 2.42E-06 8.25E-07 1.735-06 2.75E-05 NO DATA 2.27E-05 TE127 1.10E-07 3.95E-08 2.383-08 8.15E-08 4.48E-07 NO DATA 8.68E-06 TE129M 1.15E-05 4.29E-06 1.825-06 3.95E-06 4.80E-05 NO DATA 5.79E-05

, TE129 3.14E-08 1.18E-08 7.65E-09 2.415-08 1.32E-07 NO DATA 2.371-08 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-06 8.63E-05 NO DATA 2.79E-09 2 TE132 2.523-06 1.63E-06 1.53E-06 1.80E-06 1.57E-05 NO DATA 7.71E-05

, I 130 7.56E-07 2.23E-06 8.80E-07 1.09E-04 3.48E-06 NO DATA 1.92E-06

! I 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 I 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 2.515-10 I 135 4.43E-07 1.16E-06 4.2SE 07 7.651-05 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 2.575-05 1.85E-05 NO DATA 1.43E-05 1.96E-06 2.92E-06 3

• Values taken from Reference 3, Table E 11, except for SB values which were taken 4

from Reference 8, Table 4.

4 i

GRAND GULF, UNIT 1 1.o.11 Revision 11<- 06/88

l

mat r 1.2 2 (Continued)

INGESTION DOSE CONVERSION FACTORS FOR ADULTS. (DF )

(mrom per pC1 ingested)

• Page 3 of 3 NUCLIDE BONE LIVER T. BODY THYROID KIDNEY LUN7, GI-LLI CS137 7.97E-05 1.09E-04 7.14E-05 NO DATA 3.70E-05 1.2IE-05 2.11E-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-11 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-11 1.59E-09 NO DATA 3.31E-11 2.02E-11 2.22E-17 BA142 2.13E-08 2.19E-11 1.34E-09 NO DATA 1.855-11 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-11 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 1.22E-06 1.35E-10 NO DATA 5.37E-10 NO DATA 4.56E-05 I CE144 4.88E-07 2.04E-07 2.62E-08 NO DATA 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-11 1.25E-11 1.53E-12 NO DATA 7.05E-12 NO DATA 4.333-18 ND147 6.29E-09 7.27E-09 4.35E-10 NO DATA 4.25E-0* 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 2-11 i

I l

GRAND GULF, UNIT 1 1.0-12 Revision 0 - 08/82

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I i

f I

i Tinte 1.2-3 SITE REIATED INGESTION (mrom/hr DOSE per gC1/ml)* COfG4I'D1Elff FAC"f0R. (AiTau)

Page 1 of 2 )

J l

\

NUCLIDE BONE LIVER T. BODY TRYROID KIDerEY LUNG GI-LLI l

..........................................................................-......... j l H-3 0.00E+00 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 6.26E+03 6.265+03 6.26E+03 6.26E+03 6.26E+03  !

Na-24 4.07E+02 4.07E+02 4.07E+02 4.07E+02 4.075+02 4.07E+02 4.07E+02

P-32 4.62E+07 2.875+06 1.79E+06 0.00E+00 0.00E+00 0.00E+00 5.19E+06 Cr-51 0.00E*00 0.00E+00 1.27E+00 7.615-01 2.81E-01 1.69E+00 3.20E+02 Mn-54 0.00E+00 4.385+03 8.35E+02 0.00E+00 1.30E+03 0.00E+00 1.34E+04 I Mn-56 0.00E+00 1.10E+02 1.95E+01 0.00E+00 1.40E+02 0.00E+00 3.51E+03

Fe-55 6.58E+02 4.55E+02 1.06E+02 0.00E+00 0.00E+00 2.54E+02 2.61E+02 Fe-59 1.04E+03 2.44E+03 9.36E+02 0.00E+00 0.00E+00 6.82E+02 8.14E+03

{ Co-58 0.00E+00 8.92E+01 2.00E+02 0.00E+00 0.00E+00 0.00E+00 1.81E+03 i Co-60 0.00E+00 2.56E+02 5.65E+02 0.00E+00 0.00E+00 0.00E+00 4.81E+03 Ni-63 3.11E+04 2.163+03 1.04E+03 0.00E+00 0.00E+00 0.00E+00 4.50E+02 Ni-65 1.26E+02 1.64E+01 7.49E+00 0.00E+00 0.00E+00 0.00E+00 4.175+02

. Cu-64 0.00E+00 9.975+00 4.68E+00 0.00E+00 2.51E+01 0.00E+00 8.50E+02 In-65 2.32E+04 7.37E+04 3.33E+04 0.00E+00 4.93E+04 0.00E+00 4.64E+04

{ Zn-69 4.93E+01 9.43E+01 6.565+00 0.00E+00 6.13E+01 0.00E+00 1.42E+01 i Br-83 0.00E+00 0.00E+00 4.04E+01 0.00E+00 0.00E+00 0.00E+00 5.82E+01 j Br-84 0.00E+00 0.00E+00 5.24E+01 0.00E+00 0.00E+00 0.00E+00 4.11E.04 )

Br-85 0.00E+00 0.00E+00 2.15E+00 0.00E+00 0.00E+00 0.00E+00 1.01E-15 l Rb-86 0.00E+00 1.01E+05 4.71E+04 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 0.00E+00 1.92E+02 1.35E+02 0.00E+00 0.00E+00 0.00E+00 1.12E-11 Sr-89 2.21E+04 0.00E+00 6.35E+02 0.00E+00 0.00E+00 0.00E+00 3.55E+03 I

, Sr-90 5.44E+05 0.00E+00 1.34E+05 0.00E+00 0.00E+00 0.00E+00 1.57E+04 l 4 Sr-91 4.07E+02 0.00E+00 1.64E+01 0.00E+00 0.00E+00 0.00E+00 1.94E+03 i Sr-92 1.54E+02 0.00E+00 6.68E+00 i

0.00E+00 0.00E+00 0.00E+00 3.06E+03 Y-90 5.76E-01 0.00E+00 1.54E-02 0.00E+00 0.00E+00 0.00E+00 6.10E+03 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 8.44E+00 0.00E+00 2.26E-01 0.00E+00 0.00E+00 0.00E+00 4.64E+03 4

Y-92 5.06E-02 0.00E+00 1.485-03 0.00E+00 0.00E+00 0.00E+00 8.86E+02 Y-93 1.60E-01 0.00E+00 4.43E-03 0.00E+00 0.00E+00 0.00E+00 5.09E+03 i Zr-95 2.40E-01 7.70E-02 5.21E-02 0.00E+00 1.21E-01 0.00E+00 2.44E+02 l Zr-97 1.33E-02 2.68E-03 1.22E-03 0.00E+00 4.04E-03 0.00E+00 8.30E+02 Nb-95 4.47E+02 2.40E+02 1.34E+02 0.00E+00 2.465+02 0.00E+00 1.51I+06 j Mo-99 0.00E+00 1.03E+02 1.96E+01 0.00E+00 2.34E+02 0.00E+00 2.39E+02 4

Tc-99m 8.87E-03 2.51E-02 3.19E-01 0.00E+00 3.81E-01 1.23E-02 1.48E+01 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 0.00E+00 1.91E+00 0.00g+00 1.69E+01 0.00E+00 5.17E+02 Ru-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.

GRAND GULF. UNIT 1 1.0-13 Revision 2". 05/84

Trate 1.2-3 (continued)

SITE REIATED INGESTION (mrem /hr DQSEper CCletI7 gC1/ml). MENT FACTOR. (AiTau)

Page 2 of 2 NUCLIDE BONE LIVER T. BODY TEYT.0ID KIDNEY LUNG GI-LLI Ru-106 6.58E+01 0.00E+00 8.33E+00 0.00E+00 1.27E+02 0.00E+00 4.26E+03 Ag-110m 8.81E-01 8.15E-01 4.84E-01 0.00E+00 1.60E+00 0.00E+00 3.30E+02 Sb-124 6.70E+00 1.27E-01 2.66E+00 1.63E-02 0.00E+00 5.22E+00 1.90E+02 Sb-125 4.29E+00 4.79E-02 1.02E+00 4.36E-03 0.00E+00 3.30E+00 4.72E+01 Sb- 12 6 2.75E+00 5.60E-02 9.94E-01 1.69E-02 0.00E+00 1.69E+03 2.25E+02 Sb-127 6.18E-01 1.35E-02 2.37E-01 7.42E-03 0.00E+00 3.66E-01 1.41E+02 Te-125m 2.57E+03 9.3CE+02 3.44E+02 7.72E+02 1.04E+04 0.00E+00 1.02E+04 Te-127m 6.48E+03 2.32E+03 7.90E-02 1.66E+03 2.63E+04 0.00E+00 2.17E+04 Te-127 1.05E+02 3.78E+01 2.28E+01 7.80E+01 4.29E+02 0.00E+00 8.31E+03 Te-129m 1.10E+04 4.11E+03 1.74E+03 3.78E+03 4.60E+04 0.00E+00 5.54E+04 Te-129 3.01E+01 1.13E+01 7.33E+00 2.31E+01 1.26E+02 0.00E+00 2.27E+01 Te-131m 1.66E+03 8.10E+02 6.75E+02 1.28E+03 8.21E+03 0.00E+00 8.04E+04 Te-131 1.89E+01 7.885+00 5.965+00 1.55E+01 8.26E+01 0.00E+00 2.675+00 Te-132 2.41E+03 1.565+03 1.47E+03 1.72E+03 1.50E+04 0.00E+00 7.385+04 I-130 2.71E+01 8 . 01E+0'A 3.16E+01 6.79E+03 1.25E+02 0.00E+00 f 895+01 I-131 1.49E+02 2 .14 E+'J 2 1.22E+02 7.00E+04 3.665+02 0.00E+00 5.64E+01 I-132 7.29E+00 1.95E+01 6.82E+00 6.82E+02 3.11E+01 0.00E+00 3.66E+00 I-133 5.10E+01 8.87E+01 2.70E+01 1.30E+04 1.55E+02 0.00E+00 7.975+01 I-134 3.81E+00 1.03E+01 3.70E+00 1.795+02 1.64E+01 0.00E+00 9.013-03 I-135 1.59E+01 4.17E+01 1.54E+01 2.75E+03 6.685+01 0.00E+00 4.70E+01 Cs-134 2.98E+05 7.09E+05 5.79E+05 0.00E+00 2.29E+05 7.61E+04 1.24E+04 Cs-136 3.12E+04 1.23E+05 8.865+04 0.00E+00 6.85E+04 9.38E+03 1.40E+04 Cs-137 3.82E+05 5.22E+05 3.42E+05 0.00E+00 1.77E+05 5.89E+04 1.01E+04 Cs-138 2.64E+02 5.22E+02 2.595+02 0.00E+00 3.84E+02 3.795+01 2.23E-03 ,

Ba-139 9.29E-01 6.62E-04 2.72E-02 0.00E+00 6.19E-04 3.75E-04 1.65E+00 '

Ba-140 1.94E+02 2.44E-01 1.27E+01 0.00E+00 8.30E-02 1.40E-01 4.00E+02 Ba-141 4.51E-01 3.41E-04 1.52E-02 0.00E+00 3.17E-04 1.93E-04 2.13E-10 Ba-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-02 0.00E+00 0.00E+00 0.00E+00 5.54E+03 La-142 7.66E-03 3.48E-03 8.68E-04 0.00E+00 0.00E+00 0.00E+00 2.54E+01 Ce-141 2.24E-02 1.52E-02 1.72E-03 0.00E+00 7.04E-03 0.00E+00 5.79E+01 Ce-143 3.95E-03 2.92E+00 3.23E-04 0.00E+00 1.29E-03 0.00E+00 1.09E+02 Ce-144 1.17E+00 4.88E-01 6.27E-02 0.00E+00 2.90E-01 0.00E+00 3.95E+02 Pr-143 5.51E-01 2.21E-01 2.73E-02 0.00E+00 1.27E-01 0.00E+00 2.41E+03 Pr-144 1.80E-03 7.40E-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 0.00E+00 2.54E-01 0.00E+00 2.09E+03 W-187 2.96E+02 2.47E+02 8.65E+01 0.00E+00 0.00E+00 0.00E+00 8.10E+04 Np-239 2.85E-02 2.80E-03 1.54E-03 0.00E+00 8.74E-03 0.00E+00 5.75E+02

• Calculated from Equation 8.

GRAND GULF, UNIT 1 1.0 14 Revision 11 - 06/88

l l

l l

i 1.3 Licruid Radwaste Treatment System l

The essential components of the liquid radwaste treatment system are '

l l indicated on the following page by an asterisk (*).

l NOTES fer Ficure 1.3-1 i

! (1) The essential components outlined on the following page are those l necessary to collect, process and sample liquid radwaste prior to l discharge to the environment.

l (2) Only one of the following is required in order to process liquid l

l waste.

a. Equipment drain filter l l

b. Floor drain filter l

c. Equipment drain domineralizer i i

d. Floor drain domineralizer (3) One of the Waste Surge Tanks may be used to replace the Floor Drain Waste Collection Tank.

l i 8

I i

1 i

1 i

1

?

GRAND GULF, UNIT 1 1.0-15 Revision 8 - 08/86

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

2.0 GASEOUS EFFLUENTS 2.1 ("-ameous Ef flu =nt Monitor Satooints 2.1.1 continuous Ventilation Monitors For the purpose of implementation of LCO 6.3.10, the alarm setpoint level for continuous ventilation noble gas monitors will be calculated as follows:

Sy = count rate (epm) above background of vent noble gas monitor at the alarm setpoint level PF x R8 xD 8

= the lesser of or PF x R s xD as 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 effluent release points, normally set at 0.25 SF = safety factor allowing for cumulative uncertainties of measurements, normally set at 0.4 D , = dose rate limit to the total body of an individual' at the SITE BOUNDARY or at UNRESTRICTED ARIAS inside the SITE BOUNDARY required to limit dose to 500 mrom in one year

= 500 mrom/yr D = dose rate limit to the skin of the body of an individual at the SITE BOUNDARY or at UNRESTRICTED AREAS inside the SITE BOUNDARY required to limit dose to 3000 mrom in one year

= 3000 mres/yr 4

GRAND GULF, UNIT 1 2.0-1 Revision 17 - 03/95

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

4 a

1 4 .

' R = count rate (cpm) per mres/yr to the total body a C+ ( X/6 E K,* Q'gl 1 1 wheres C = count rate (cpm) abcve background of the vent monitor corresponding to grah sample radionuclide i concentrations i

'- X/Q = highest sector annual average atmospheric dispersion f at the SITE BOUNDARY cr at UNRESTRICTED AREAS inside I the SITE BOUNDARY i 6* 3

' = 8.9 x 10 sec/m in the SW sector i

Kg - total body dose factor due to gamma emissions from l 3 each noble gas radionuclide 1 (mres/yr per gci/m )

) from ODCM Table 2.1-1 Q'g = rate of release of noble gas radionuclide 1 (gC1/sec)

! from the release point R, - count rate (cym) per mres/yr to the skin I

= c + X"/Q (Eg (Lg + 1.1 Mg) Q' g]

a 3

Lg = skin dose factor due to beta emissions from isotope 1 (mrom/yr per pCi/m ) from ODW Table 2.1-1 5 1.1 = mrom skin dose per arad air dose l

.j Mg j j - air dose factor due to ganas emissions from isotope i (mrad /yr per pCi/m ) from ODW Table 2.1-1 l

i

• The highsse annual average X/Q for the GGNS SITE BOUNDARY or UNRESTRICTED AREAS inside the SITE BOUNDARY is at the SITE BOUNDr.RY, (SW sector, 0.85 I miles). This value is taken from ODOt Reference 9, Table 2. -

i 4

)

ORAND GULF, UNIT 1 2.0-2 Revision 17 - 03/95

2.1.2 TEET DELETED l

l l

GRAND GULF, UNIT 1 2,0 3 Revision 2 - 05/84 e

I l

I l

l l

l NOTES For Section 2.1.1

1) The calculated setpoint values will determine the allowable bounds for the l actual setpoint adjusteents. That is, setpoint adjustments are not ,

required to be performed if the existing setpoint level corresponds to a  !

l l count rate that is less than or equal to + 25% of the calculated value. If radionuclides are not detected in the grab sample, then the previously I

l calculated setpoint.may remain as the valid setpoint.

2) A more conservative setpoint may be calculated using the conservative Kr-89 total body dose factor. This method may be used when there are no valid j isotopics available. The conservative setpoint will be calculated as follows:

1 S

y

= count rate (epm) above background of vent noble gas monitor at the I alarm setpoint level

• l

= PF' xD xR*

TB where:

PF = product of allocation factor (AF) and safety f actor (SF') , normally i set at 0.2 i

i AF = allocation factor allowing for a total of four normal effluent release points, normally set at 0.25 l

SF' = safety factor allowing for cumulative uncertainties of measurements, normally set at 0.8 R" = ceriuervative count rate per mrem /yr to the total body (Xe-133 detection, Kr-89 dose)

= (3.53r-s) (so) x75 (x) (v) (K)

I The setpoint calculation based on a Kr-89 skin dose is not required because the setpoint based on a Kr-89 total body dose will always be more conservative.

GRAND GULF, UNIT 1 2.0-4 Revision 12 - 08/88 a

I i

i i

l where:

X = Xe-133 volume efficiency factor of the detector system in l gC1/cc/cym as determined by the primary calibration

• v = maximum designed ventilation flow rate in cubic feet per minute (cfm) 3.53E-5 = conversion factor, ft per cc 60 = conversion factor, seconds per minute K = total body dose factor for Kr-89, the most restrictive isotope, from Table 2.1-1

= 1.66E + 04 mrom/yr per pCi/m l

l Other variables ar defined in SGCtion 2.1.1 l

l t

i i

1 The instrument calibration procedures will include checks to ensure that the detector efficiency does not vary by more than 2 25%.

i i

GRAND GUI.F, UNIT 1 2.0-5 Revision 12 - 08/88 9

l TAni_r 2,1-1 i l l l

DOSE FACTORS FQE EXPOSURE TO A SEMI-INFINITE CLOUD OF NOBLE GASES l Nuclide Y-Bodv**fK)i B-Skin **fL)i Y-Air *(M)i B-Air *fN)i Kr-85m 1.17E+03*** 1.4EE+03 1.23E+03 1.97E+03 Kr-85 1.61E+01 1.34E+03 1.72E+01 1.95E+03 Kr-87 5.92E+03 9.73E+03 6.175+03 1.03E+04 Kr-88 1.47E+04 2.37E+03 1.52E+04 2.93E+03 Kr-89 1.66E+04 1.01E+04 1.73E+04 1.06E+04 Kr-90 1.56E+04 7.2SE+03 1.63E+04 7.83E+03 Xe-131m 9.15E+01 4.76E+02 1.56E+02 1.11E+03 Xe-133m 2.51E+02 9.94E+02 3.27E+02 1.48E+03 Xe-133 2.94E+02 3.06E+02 3.53E+02 1.05E+03 Xe-135m 3.12E+03 7.11E+02 3.365+03 7.39E+02 Xe-135 1.81E+03 1.86E+03 1.92E+03 2.46E+03 Xe-137 1.42E+03 1.22E+04 1.51E+03 1.27E+04 Xe-138 8.83E+03 4.13E+03 9.21E+03 4.75E+03 l l Ar-41 8.84E+03 2.69E+03 9.30E+03 3.28E+03 l

i Values taken from Reference 3, Table B-1 l

t

• mrad - ma pC1 - yr

• • mrem - ma l gC1 - yr

• • • 1.17E+03 - 1.17 x 10 l

l

(

i.

GRAND GULF, UNIT 1 2.0-6 Revision 0 - 08/82

. ._ . _ _ _ _ . . . _ _ _ . _ . _ .___m_ - . . . __ . . _ _ _ . _ _ . _ _ . . _ _ _ ._ _ _ _

2.2 Gaseous Effinant Dese Calculations 2.2.1 t1nrestricted Area Bottnr4 mrv Dose Rate

a. For the purpose of implementation of LCO 6.11.4.a, the dose rate at the SITE BOUNDARY or at UNRESTRICTED AREAS within the SITI BOUNDARY due to noble gases shall be -

calculated as follows:

D eb = average t tal body dose rate in current year (mrem /yr)

= X/Q EKg Q'g D, = average skin dose rate in current year (mres/yr)

= X/Q C (L g + 1.1Mg ) Q'g

b. Organ dose rate due to tritium, I-131, I-133 and all radioactive materials in particulate form, with half-lives greater than eight days will be calculated for the purpose of iglementation of LCO 6.11.4.b as 1

follows:

D = average organ dose rate in current year (mrom/yr) ,

l i

where:

l GRAND GULF, UNIT 1 2.0-7 Revision 17 - 03/95

W = controlling sector annual anrsy atmospheti-dispersion at the SITE BOUNDAtY or UNRESTRICTED AREAS inside the SITE BOUNDARY for the appropriate pathway

~

X[6 = 8.9 x 10 sec/m for inhalation and all tritium pathways or

~

D/6 = 1.6 x 10"' " m for food and ground plane pathways i

P g = the total dose parameter for radionuclide i, (mres/yr per pci/m ) for inhalation and all 2

tritium pathways and (m , ,,,,jy,p,, egj,,c3 for food and ground plane pathways, from ODCM Tables 2.2-la-b Q'g = rate of release of noble gas radionuclide i (gCi/sec) from the release point 1

{ = average release rate of isotope i of tritium, I-131, I-133 or other radionuclide in particulate form, with half-lives greater than eight (8) days in the current year (gCi/sec)

• The highest annual average X/Q for the GGNS SITE SOUNDARY or UNRESTRICTED i

AREAS inside the SITE BOUNDARY is at the SITE BOUNDARY, in the SN sector l

l l

(0.85 miles). This value is taken from ODCM Reference 9, Table 2.

l

" The highest annual average D/Q for the GGNS SITE SOUNDARY or UNRESTRICTED AREAS insidd the SITE BOUNDARY is at the SITE BOUNDARY in the SSE se (0.46 miles). This value is taken from 0D04 Reference 9, Table 2.

i' i

l 2.0-8 Revision 17 - 03/95 GRAND GULF, UNIT 1 f

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f 2.2.2 Unrestricted Area Dome to Individuni l

a. For the purpose of implementation of LCO 6.11.5, the air dose at the SITE BOUNDARY or at UNRESTRICTED ARIAS within the SITE BOUNDARY shall be determined as follows:

D = air dose due to gansna emissions from noble gas

! Y radionuclide 1 (mrad) l

= 3.17 x 10" X/Q' Q where l

l l

X/Q* = relative concentration for the SITE BOUNDARY or at UNRESTRICTED AREAS within the SITE BOUNDARY.

3

= 8.9 X 10' sec/m Mg = air dose factor due to gasuna emissions from noble gas radionuclide 1 (mrad /yr per gCi/m )-

l l

from ODCM Table 2.1-1 ,

l The highest annual average X/Q for the GGNS SITE BOUNDARY or at l

UNRESTRICTED ARIAS within the SITE BOUNDARY is at the SITE I

BOUNDARf, SW Sector, 0.85 miles. This value is taken from ODCM t

Reference 9 Table 2.

i l

J GRAND GULF, UNIT 1 2.0-9 Revision 17.- 03/95

l l

l l

Qg = cumulative release of radionuclide i of noble gas, tritium, I-131, I-133, or material in particulate form over the period of interest (gCi)

Note: 3.17 x 10" is the inverse of the number of i

seconds per year, and Dg = air dose due to beta emissions from noble gas l

radionuclide i (mrad)

~

= 3.17 x 10 ENgX76' Q g i where Ng = air done factor due to beta emissions from noble gas radionuclide i (mrad /yr per gCi/m ) from ODCM Table 2.1-1 X/Q' = relative concentration the SITE BOUNDARY or at UNRESTRICTED AREAS within the SITE BOUNDARY.

! = 8.9 x 10~ sec/m og= cumulative relense of radionuclide i of noble gas, tritium, I- L31, I-133, or material in l

particulate fora over the period of interest (gC1) l t .

The highest annual average X/Q for the GGNS SITE BOUNDARY or at UNRESTRICTED AREAS within the SITE BOUNDARY is at the SITE BOUNDARY, SW Sector, 0.85 miles. This value is takan-from CDCM f

Reference 9 Table 2.

l GRAND GULF, UNIT 1 2.0-10 Revision 17 - 03/95 r

w

. .. _ _ _ __ .. - _ . . _ . = _ _ _ _ _ . . . ._ __ __. _. .m_ . . . _ . . . _ _.

2.2.2 Unrestricted Area Dese to Individua1"

b. Dose to an individual from tritium, I-131, I-133 and radioactive materials in particulate form, with half-lives greater than eight (8) days will be calculated for the purpose of implementation of LCO 6.11.6 as follows:

D = dose to an individual from tritium, I-131, I-133 and radionuclides in particulate form, with half-life greater than eight days (mrem)

~

= 3.17 x 10 ' ER g W' Q g

where:

W' = relative concentration at a controlling location for an individual

~*

X/F = 8.3 x 10 sec/m for inhalation and all tritium pathways or 57F = s.1 x 10* m"* for food and ground plane pathways R = the total dose factor fo.* radionuclide 1, 3

(mres/yr per gC1/m ) for inhalation and all tritium pathways and (m . mrom/yr per pCi/sec) for food and ground plana pathways from Tables 2.2-2a - d

• The highest annual average X/Q and D/Q at or beyond the SITE BOUNDARY is in the SW Sector (0.89 miles). These values are for the controlling offsite receptor. These values are taken from ODCM Reference 9, Table 2.

d GRAND GULF, UNIT

• 2.0-10a Revision 17 - 03/95 l

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

2.2.2 tinrestricted Area Dome to individuzi' Q = cumulative release of radionuclide i of noble gas, tritium, I-131, I-133, or material in particulate form over the period of interest (gC1) l i

' c. For the purpose of iglementing TS 5.6.3, 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.

2.2.3 Doea Proiection l

Doses from gaseous effluents to UNRESTRICTED AREAS are projected at least every 31 days as required by LCO 6.11.8.

l These projections are made by averaging the doses (D , Dg ,

D,) from previous operating history (normally the previous six months) which is indicative of future expected operations.

l l'

{

I l

1 4

GRAND GULF, UNIT 1 2.0-10b Revision 17 - 03/95

______O

TAnte 2.2 la PATHWAY DOSE FACTORS FOR LCO 6.11.4 and SECTION 2.2.1.b, (P )

Page 1 of 2 (INFANT) ( N.A. ) (INFANT)

AGE GROUP FOOD ISOTOPE INMu 2_ TION GROtJND PLANE 6.468E+02 0.000E+00 2.382E+03 H-3 2.340E+09 C-14 2.646E+04 0.000E+00 1.056E+04 1.979E+07 1.542E+07 NA-24 1.602E+11 P-32 2.030E+06 0.000E+00 1.284E+04 7.864E+06 4.700E+06 CR-51 3.900E+07 MN-54 9.996E+05 1.287E+09 7.168E+04 1.525E+06 2.862E+00 MN-56 1.351E+08 FE-55 8.694E+04 0.000E+00 1.015E+06 4.562E+08 3.919E+08 FE-59 6.055E+07 CO-58 7.770E+05 6.194E+08 4.508E+06 5.172E+09 2.098E+08 CO-60 3.493E+10 NI-63 3.388E+05 0.000E+00 5.012E+04 4.930E+05 3.020E+01 NI-65 3.807E+06 CU-64 1.4995+04 9.823E+05 6.468E+05 7.9075+08 1.904E+10 ZN-65 3.855E-09 ZN-69 1.322E+04 0.000E+00 3.808E+02 1.011E+04 9.339E-01 BR-83 1.256E-22 BR-84 4.004E+02 3.3765+05 2.044E+01 0.000E+00 0.000E+00 BR-85 2.234E+10 RB-86 1.904E+05 1.4785+07 5.572E+02 5.3995+04 1.874E-44 RB-88 4.193E-53 RB-89 3.206E+02 2.075E+05 2.030E+06 3.560E+04 1.258E+10 SR-89 1.216E+11 SR-90 4.088E+07 0.000E+00 7.336E+04 3.587E+06 3.215E+05 SR-91 5.005E+01 SR-92 1.400E+05 1.233E+06 2.688E+05 7.583E+03 9.406E+05 Y-90 1.876E-15 Y-91M 2.786E+03 1.658E+05 2.450E+06 1.702E+06 5.251E+06 Y-91 1.026E+01 Y-92 1.266E+05 3.060E+05 1.666E+05 3.620E+05 1.776E+04 Y-93 8.257E+05 2R-95 1.750E+06 3.975E+04 1.400E+05 4.921E+06 4.4465+04 2R-97 2.062E+08 NE-95 4.7885+05 2.291E+08 1.348E+05 6.608E+06 3.108E+08 MO-99 1.646E+04 TC-99M 2.030E+03 3.013E+05 8.442E+02 3.253E+04 1.423E-56 TC-101

• 1.055E+05 RU-103 5.516E+05 1.804E+08 4.844E+04 1.030E+06 3.204E+00 RU-105 1.445E+06 RU-106 1.1565+07 3.590E+08 3.668E+06 3.649E+09 1.4&iE+10 AG-110M 1

GRAND GULF, UNIT 1 2.0-11. Revision 17 - 03/95

r TABLE 2.2-la (continued)

PATHWAY DOSE FACTORS FOR LCO 6.11.4 and SECTION 2.2.1.b, (Pg)

Page 2 of 2 AGE GROUP (INFANT) ( N.A. ) (INFANT)

ISOTOPE INFifATION GROrwn prauw FOOD l TE-125M 4.466E+05 3.001E+06 1.500E+08 l TE-127M 1.312E+06 1.395E+05 1.037E+09 TE-127 2.436E+04 4.704E+03 1.359E+05 l

TE-129M 1.680E+06 3.290E+07 1.392E+09 TE-129 2.632E+04 4.395E+04 1.678E-07 TE-131M 1.988E+05 1.351E+07 2.288E+07 l

l TE-131 0.218E+03 4.929E+07 1.384E-30 TE-132 3.402E+05 7.098E+06 6.513E+07 ,

l 8.754E+08 I-130 1.596E+06 9.560E+06 l I-131 1.484E+07 2.985E+07 1.053E+12  ;

I-132 1.694E+05 2.075E+06 1.1885+02  !

I-133 3.5565+06 4.259E+06 9.601E+09 I-134 4.452E+04 7.578E+05 8.402E-10 I-135 6.958E+05 4.210E+06 2.002E+07 CS-134 7.028E+05 3.282E+09 6.801E+10 CS-136 1.345E+05 2.432E+08 5.795E+09 CS-137 6.1185+05 1.337E+09 6.024E+10 ,

CS-138 8.764E+02 5.860E+05 2.180E-22  !

RA-139 5.096E+04 1.705E+05 2.874E-05 EA-140 1.596E+06 3.352E+07 2.410E+08 BA-141 4.746E+03 6.762E+04 3.141E-44 BA-142 1.554E+03 7.234E+04 0.000E+00 LA-140 1.680E+05 3.114E+07 1.880E+05 LA-142 5.950E+04 1.269E+06 6.019E-06 CE-141 5.166E+05 2.199E+07 1.366E+07 CE-143 1.162E+05 3.753E+06 1.536E+06 l CE-144 9.842E+06 6.761E+07 1.334E+08 #

PR-143 4.326E+05 0.000E+00 7.845E+05 PR-144 4.284E+03 3.017E+03 1.171E-48 ND-147 3.220E+05 1.441E+07 5.743E+05 W-187 3.962E+04 3.915E+06 2.501E+06 NP-239 5.950E+04 2.823E+06 9.400E+04 Units: Inhalation 2and all tritium pathways - mrom/yr per gci/m Others - m . mrom/yr per gCi/sec Values based on standard NUREG-0133, Section 5.2.1 assug tions unless otherwise indicated.

l GRAND GULF, UNIT 1 2.0-12 Revision 17 - 03/95

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

i' 1

TABLE 2.2-lb

! PATHWAY DOSE FACTORS FOR LCO 6.11.4 and SECTION 2.2.1.b, (Pg)

Page 1 of 2

AGE GROUP ( cMTLD ) ( N. A. ) ( cMTLB )

l ISOTOPr IWarATION nantarn pr.in nait/ANL/ MEAT t

H-3 1.125E+03 0.000E+00 1.82EE+02 C-14 3.589E+04 0.000E+00 2.991E+08 NA-24 1.610E+04 1.385E+07 1.345E-03 P-32 2.605E+06 0.000E+00 5.781E+09 CR-51 1.6985+04 5.5065+06 3.636E+05 MN-54 1.576E+06 1.625E+09 6.249E+06 MN-56 1.232E+05 1.0683+06 1.901E-51 FE-55 1.110E+05 0.000E+00 3.566E+08 l

FE-59 1.269E+06 3.204E+08 4.943E+08 CO-58 1.106E+06 4.464E+08 7.485E+07 CO-60 7.067E+06 2.532E+10 2.993E+08 NI-63 0.214E+05 0.000E+00 2.272E+10 NI-65 8.3995+04 3.451E+05 3.167E-51 CU-64 3.670E+04 6.876E+05 1.087E-05 l EN-65 9.953E+05 8.583E+08 7.001E+08 ZN-69 1.0185+04 0.000E+00 0.000E+00 ER-83 4.736E+02 7.079E+03 7.425E-57 ER-84 5.4765+02 2.363E+05 0.000E+00 0.000E+00 i EA-85 2.531E+01 0.000E+00 RE-86 1.983E+05 1.035E+07 4.535E+08 RE-88 5.624E+02 3.7793+04 0.000E+00 RE-89 3.452E+02 1.452E+05 0.000E+00 SR-89 2.157E+04 2.509E+04 3.756E+08 SR-90 1.010E+08 0.000E+00 0.111E+09 SR-91 1.739E+05 2.511E+06 4.128E-10 l

SR-92 2.424E+05 8.631E+05 2.724E-48 Y-90 2.6795+05 5.3085+03 3.806E+05 Y-91M 2.812E+03 1.161E+05 0.000E+00 l

Y-91 2.627E+06 1.207E+06 1.872E+08 Y-92 2.390E+05 2.142E+05 5.428E-35 Y-93 3.885E+05 2.534E+05 1.207E-07 i ZR-95 2.231E+06 2.837E+08 4.763E+08 ZR-97 3.511E+05 3.445E+06 5.471E-01 NE-95 6.142E+05 1.405E+08 1.7385+09 i

MO-99 1.354E+05 4.626E+06 1.915E+05 TC-99M 4.810E+03 2.1095+05 5.394E-18 l TC-101 5.8463+02 2.2775+04 0.000E+00 RU-103 6.623E+05 1.265E+08 3.127E+09 RU-105 9.953E+04 7.212E+05 4.590E-25 RU-106 1.432E+07 5.049E+08 5.384E+10 AG-110M 5.476E+06 4.019E+09 5.2F9E+08 l

i I

GRAND GULF, UNIT 1 2.0-13 Revision 17 - 03/95 l

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

~

TABLE 2.2-ib (Continued)

PATHNAY DOSE FACTORS FOR LCO 6.11.4 and SECTION 2.2.1.b, (Pg)

Page 2 of 2 CHILD ) ( N. A. ) ( CHILD )

AGE GROUP (

ISOTOPE Iw u ATION annUriD PT EME GRS/ANL/ MEAT

• 4.773E+05 2.1285+06 4.438E+08 TE-125M TE-127M 1.400E+06 1.083E+05 3.947E+09 TE-127 5.624E+04 3.293E+03 1.254E-08 TE-129M 1.761E+06 2.305E+07 4.091E+09 TE-129 2.549E+04 3.0763+04 0.000E+00 TE-131M 3.078E+05 9.459E+06 7.656E+03 TE-131 2.054E+03 3.450E+07 0.000E+00 TE-132 3.774E+05 4.9685+06 7.274E+06 I-130 1.846E+06 6.692E+06 5.271E-04 I-131 1.624E+07 2.0095+07 4.293E+09 I-132 1.935E+05 1.452E+06 1.895E-57 I-133 3.840E+06 2.981E+06 1.017E+02 5.06SE+04 5.30$E+05 0.000E+00 I-134 I-135 7.918E+05 2.947E+06 8.104E-15 CS-134 1.014E+06 8.007E+09 1.180E+09 CS-136 1.709E+05 1.702E+08 3.452E+07 CS-137 9.065E+05 1.201E+10 1.040E+09 CS-138 8.399E+02 4.102E+01 0.000E+00 RA-139 5.772E+04 1.194E+0!, 0.000E+00 RA-140 1.743E+06 2.3465+G7 3.420E+07 RA-141 2.919E+03 4.7345404 0.000E+00 RA-142 1.643E+03 5.064E+04 0.000E+00 LA-140 2.257E+05 2.180E+07 4.204E+02 LA-142 7.585E+04 8.886E+05 0.000E+00 CE-141 5.439E+05 1.540E+07 1.070E+07 CE-143 1.273E605 2.6273+06 1.963E+02 CE-144 1.195E+07 0.032E+07 1.476E+08 PR-143 4.329E+05 0.000E+00 2.815E+07 PR-144 1.565E+03 2.112E+03 0.000E+00 ND-147 3.202E+05 1.00SE+07 1.174E+07 W-107 9.102E+04 2.740E+06 2.176E+00 NP-239 6.401E+04 1.9765+06 1.741E+03 Units: Inhalation and 2 all tritium pathways - mres/yr per pCi/m Others - m . mrom/yr per gCi/sec values based on standard NUREG-0133, Section 5.3.1 assumptions unless otherwise indicated.

• Meat consusqtion assumed 75 percent beef and 25 percent mutton.

GRAND GULF, UNIT 1 2.0-14 Revision 17 - 03/95

l TaufE 2.2-2a PATHWAY DOSE FACTORE FOR Lc0 E.11.6 AND SECTION 2.2.2.b, (Rg )

l Page 1 of 2 AGE anoUP ( INFANT ) ( N.A. ) (

uurarf ) ( INFANT ) ( INFANT )

ISOTCPr Imm ATION nontwn pt w a nas/c0W/MTLK nas/ cow / MEAT q qETATION..

H-3 6.468E+02 0.000E+00 2.382E+03 0.000E+00 0.000E+00 C-14 2.646E+04 0.000E+00 2.340E+09 0.000E+00 0.000E+00 NA-24 1.0565+04 1.385E+07 1.542E+07 0.000E+00 0.000E+00 P-32 2.030E+06 0.000E+00 1.602E+11 0.000E+00 0.000E+00 CR-51 1.284E+04 5.5065+06 4.700E+06 0.000E+00 0.000E+00 l

l MN-54 9.9965+05 1.625E+09 3.900E+07 0.000E+00 0.000E+00 MN-56 7.168E+04 1.068E+06 2.862E+00 0.000E+00 0.000E+00 FE-55 8.694E+04 0.000E+00 1.351E+08 0.000E+00 0.000E+00 FE-59 1.015E+06 3.204E+08 3.9195+08 0.000E+00 0.000E+00 l

CO-58 7.770E+05 4.464E+08 6.055E+07. 0.000E+00 0.000E+00 1 CO-60 4.508E+06 2.532E+10 2.0985+08 0.000E+00 0.000E+00 l NI-63 3.388E+05 0.000E+00 3.493E+10 0.000E+00 0.000E+00 l NI-65 5.012E+04 3.451E+05 3.020E+01 0.000E+00 0.000E+00 l CU-64 1.4985+04 6.876E+05 3.8075+06 0.000E+00 0.000E+00  ;

EN-65 6.4585+05 8.583E+08 1.904E+10 0.000E+00 0.000E+00 l KN-69 1.332E+04 0.000E+00 3.8555-09 0.000E+00 0.000E+00 BR-83 3.8085+02 7.0795+03 9.3393-01 04000E+00 0.000E+00 BR-84 4.004E+02 2.363E+05 1.2563-22 0.000E+00 0.000E+00 BR-85 2.044E+01 0.000E+00 0.000E+00 0.000E+00 0.000E+00 RB-86 1.904E+05 1.035E+07 2.234E+10 0.000E+00 0.000E+00 RB-88 5.572E+02 3.7793+04 1.874E-44 0.000E+00 0.000E+00 l RB-89 3.206E+02 1.452E+05 4.1935-53 0.000E+00 0.000E+00 l SR-89 2.030E+06 2.5095+04 1.2585+10 0.000E+00 0.000E+00 SR-90 4.088E+07 0.000E+00' 1.2165+11 0.000E+00 0.000E+00 SR-91 7.336E+04 2.511E+06 3.215E+05 0.000E+00 0.000E+00 SR-92 1.400E+05 8.631E+05 5.005E+01 0.00CE+00 0.000E+00 i

i Y-90 2.688E+05 5.3085+03 9.406E+05 0.000E+00 0.000E+00 Y-91M 2.786E+03 1.161E+05 1.8763-15 . 0.000E+00 0.000E+00 Y-91 2.450E+06 1.2075+06 5.251E+06 0.000E+00 0.000E+00 l Y-92 1.2665+05 2.142E+05 1.026E+01 0.000E+00 0.000E+00 ,

Y-93 1.666E+05 2.534E+05 1.7763+04 0.000E+00 0.000E+00 i ZR-95 1.750E+06 2.8375+08, 8.257E+05 0.000E+00 0.000E+00 l ZR-97 1.400E+05 3.445E+06 4.4465+04 0.000E+00 0.000E+00 NS-95 4.7885+05 1.605E+08 2.042E+08 0.000E+00 0.000E+00 MO-99 1.340E+05 4.626E+06 3.108E+08 0.000E+00 0.000E+00 TC-99M 2.030E+03 2.109E+05 1.6465+04 0.000E+00 0.000E+00 i TC-101 8.442E+02 2.2773+04 1.423E-54 0.000E+00 0.000E+00 i RU-103 5.5163+05 1.265E+08 1.055E+05 0.000E+00 0.000E+00 RU-105 4.844E+04 7.212E+05 3.204E+00 0.000E+00 0.000E+00 RU-106 1.1565+07 5.049E+08 1.445E+06 0.000E+00 0.000E+00 AG-110M 3.6683+06 4.019E+09 1.461E+10 0.000E+00 0.000E+00 I

l i  !

I t

I GRAND GULF, UNIT 1 2.0-15 Revision 17 - 03/95 a

1.

. - -- - . - .- . . . . - . . - . . ~ ~ . . ~ . - . . . . . - . ~ - - - . . . . - ~-. - . . -

).

4

} -

- TABLE 2.2-2a ( cont i m* =d )

PATHWAY DOSE FACTORS FOR Lc0 6.11.6 AND j

SECTION 2.2.2.b, (Ag)

Page 2 of 2 l

AGE GROUP ( INFANT ) ( N.A. ) ( INFANT ) ( INFANT ) ( INFANT )

ISOTOPE I_hrukT 2 TION GROrntn PT khfR MDE/ COW / MILE dDS/ COW /lGAT VEu m TION TE-125M 4.466E+05 2.128E+06 1.508E+08 0.000E+00 0.000E+00 TE-127M 1.312E+06 1.083E+05 1.037E+09 0.000E+00 0.000E+00 TE-127 2.436E+04 3.293E+03 1.359E+05 0.000E+00 0.000E+00 TE-129M 1.600E+06 2.305E+07 1.392E+09 0.000E+00 0.000E+00 4

TE-129 2.632E+04 3.076E+04 1.670E-07 0.000E+00 0.000E+00 TE-131M 1.988E+05 9.459E+06 2.2885+07 0.000E+00 0.000E+00 i 0.000E+00 TE-131 8.215E+03 3.450E+07 1.3545-30 0.000E+00 TE-132 3.402E+05 4.9683+06 6.513E+07 0.000E+00 0.000E+00 i 0.000E+00 I-130 1.596E+06 6.692E+06 8.754E+08 0.000E+00 I-131 1.484E+07 2.0895+07 1.053E+12 0.000E+00 0.000E+00 j 0.000E+00 0.000E+00 I-132 1.694E+05 1.452E+06 1.1885+02 4

I-133 3.5565+06 2.981E+06 9.601E+09 0.000E+00 0.000E+00 i

I-134 4.452E+04 5.305E+05 8.4025-10 0.000E+00 0.000E+00 1 I-135 6.9585+05 2.S475+06 2.002E+07 0.000E+00 0.000E+00 I i

CS-134 7.020E+05 8.0075+09 6.801E+10 0.000E+00 0.000E+00 1 l

4 CS-136 1.345E+05 1.702E+08 5.795E+09 0.000E+00 0.000E+00 l CS-137 6.1185+05 1.201E+10 6.024E+10 0.000E+00 0.000E+00 i i CS-138 8.764E+02 4.102E+05 2.1805-22 0.000E+00 0.000E+00 i 0.000E+00 RA-139 5.096E+04 1.194E+05 2.8745-05 0.000E+00 l RA-140 1.5965+06 2.3465+07 2.410E+00 0.000E+00 0.000E+00 1 RA-141 4.746E+03 4.734E+04 3.1415-44 0.000E+00 0.000E+00 4

RA-142 1.554E+03 5.064E+04 0.000E+00 0.000E+00 0.000E+00

]

i LA-140 1.600E+05 2.180E+07 1.880E+05 0.000E+00 0.000E+00 LA-142 5.950E+04 8.886E+05 6.0195-06 0.000E+00 0.000E+00 i

CE-141 5.166E+05 1.540E+07 1.366E+07 0.000E+00 0.000E+00 l CE-143 1.162E+05 2.627E+06 1.5365+06 0.000E+00 0.000E+00 l CE-144 9.842E+06 8.032E+07 1.334E+08 0.000E+00 0.000E+00 l PR-143 4.326E+05 0.000E+00 7.845E+05 0.000E+00 0.000E+00 PR-144 4.204E+03 2.112E+03 1.1713-40 0.000E+00 0.000E+00

' ND-147 3.220E+05 1.0095+07 5.743E+05 0.000E+00 0.000E+00 W-187 3.962E+04 2.740E+06 2.501E+06 0.000E+00 0.000E+00 i j NP-239 5.950E+04 1.976E+06 9.400E+04 0.000E+00 0.000E+00 l i

Units: Inhalatf.on2and all tritium pathways - mres/yr per pCi/m Others - m . mrom/yr per pCi/sec values based on standard NUREG-0133, Section 5.3.1 assumptions unless otherwise i indicated.

I l

1 1

} . .

1 i

l l'

GRAND GULF, UNIT 1 2.0 16 Revision 17 - 03/95

._ .- _ _ . _ _ _ ___. _ ._ _ - . _ _ . ~ . . . - . - - _ _ . _ _ _ _ , _ _ _ _ . _ _ _ _ . _ __m I

i j

a i

T_antz 2.2-2b t'

PATHWAY DOSE FACTORS FOR LCO 6 1 6 i SECTION 2.2.2.b, (Rg)

Page 1 of 2 AGE GROUP t ENTLD ) ( N.A. ) ( ENTLD ) ( CHILD ) ( EMILD ) l

{ nantnrn pr an GRs/ cow / Mitt non/ COW / MEAT VEum-iATION l 1 ISOTOPE INH _1t ATION H-3 1.125E+03 0.000E+00 1.570E+03 2.341E+02 4.0085+03

C-14 3.589E+04 0.000E+00 1.195E+09 3.834E+08 8.894E+0S NA-24 1.610E+04 1.385E+07 8.853E+06 1.725E-03 3.729E+05 P-32 2.605E+06 0.000E+00 7.775E+10 7.411E+09 3.366E+09

, CR-51 1.690E+04 5.506E+06 5.398E+04 4.661E+05 6.213E+06 MN-54 1.576E+06 1.625E+09 2.097E+07 8.011E+06 6.648E+08

l. 1.068E+06 1.865E+00 2.437E-51 2.723E+03 l MN-56 1.232E+05 FE-55 1.110E+05 0.000E+00 1.1183+0S 4.571E+08 8.012E+08 l FE-59 1.269E+06 3.204E+08 2.025E+08 6.338E+08 6.693E+08 CO-58 1.1065+06 4.464E+08 7.080E+07 9.5965+07 3.771E+08 4

Co-60 7.0673+06 2.532E+10 2.391E+0S 3.830E+08 2.095E+09 i NI-63 8.214E+05 0.000E+00 2.964E+10 2.912E+10 3.949E+10 I NI-65 8.399E+04 3.451E+05 1.9093+01 4.061E-51 1.211E+03 CU-64 3.670E+04 6.876E+05 3.502E+06 1.3935-05 5.159E+05 ,

i

! ZN-65 9.953E+05 S.583E+08 1.101E+10 1.000E+09 2.164E+09 l 4 ZN-69 1.0185+04 0.000E+00 1.1235-09 0.000E+00 9.8935-04 l BR-83 4.736E+02 7.0795+03 4.3993-01 9.519E-57 5.3693+00 l

} 3.8223-11 BR-84 5.4765+02 2.363E+05 6.500E-23 0.000E+00 1

BR-85 2.531E+01 0.000E+00 0.000E+00 0.000E+00 0.000E+00 RS-06 1.903E+05 1.035E+07 0.804E+09 5.815E+08 4.584E+08 R5-88 5.624E+02 3.7795+04 7.150E-45 0.000E+00 4.374E-22 RB-89 3.452E+02 1.452E+05 1.715E-53 0.000E+00 1.6425-26 j 3.593E+10

~

SR-89 '2.1575+06 2.5095+04 6.618E+09 4.815E+08 SR-90 1.010E+08 0.000E+00 1.1173+11 1.040E+10 1.243E+12 l 1.157E+06 j SR-91 1.739E+05 2.511E+06 2.8785+05 5.292E-10 SR-92 2.424E+05 8.631E+05 4.134E+01 3.492E-48 1.378E+04 Y-90 2.679E+05 5.3085+03 9.171E+05 4.8795+05 6.559E+07 Y-91M 2.812E+03 1.161E+05 5.1985-16 0.000E+00 1.737E-05

2.484E+09 1 Y-91 2.627E+06 1.207E+06 5.1995+06 2.400E+08 Y-92 2.390E+05 2.142E+05 7.310E+00 6.9595-35 4.5765+04 l 1.573E+04 1.547E-07 4.482E+06 Y-93 3.885E+05 2.534E+05 i

ZR-95 2.231E+06 2.8375+08 8.786E+05 6.106E+08 0.843E+08 1 ZR-97 3.511E+05 3.445E+06 4.199E+04 7.0155-01 1.240E+07 NS-95 61142E+05 1.605E+08 2.2073+0S 2.2285+09 2.949E+0S

$ 1.6475+07 MO-99 1.354E+05 4.6265+06 1.738E+0S 2.4565+05

{

TC-99M 4.810E+03 2.109E+05 1.474E+04 6.915E-18 5.255E+03 l

TC-101 5.8465+02 2.277E+04 5.5935-58 0.000E+00 4.123E-29 RU-103 6.623E+05 1.265E+00 1.108E+05 4.009E+09 3.971E+08 j 5.981E+04

RU-105 9.953E+04 7.212E+05 2.493E+00 5.8855-25 RU-106 1.432E+07 5.0495+0S 1.437E+06 6.902E+10 1.159E+10 i 2.581E+09

! AG-110M 5.4765+06 4.019E+09 1.678E+10 6.742E+01 i

l 1

i a

k j . .

1 i

GRAND GULF, UNIT 1 2.0-17 Revision 17 - 03/95 I

1

TABLE 2.2-2b (continued)

PATHWAY DOSE FACTORS FOR LCO 6.11.6 AND SECTION 2.2.2.b, (R )

Page 2 of 2 i

CHILD ) ( N.A. ) ( cMILD ) ( CHILD ) ( FMTLD )

i AGE GROUP (

VEGETATION ISOTOPE INH _17ATION GROrnrn PLANE nna/ cow / MILK num/ COW / MEAT

' 4.773E+05 2.128E+06 7.377E+07 5.690E+08 3.506E+08 TE-125M 5.060E+09 3.7695+09 TE-127M 1.480E+06 1.083E+05 5.932E+08 5.624E+04 3.293E+03 1.191E+05 1.607E-08 3.903E+05 TE-127 5.245E+09 2.460E+09 TE-129M 1.761E+06 2.305E+07 7.961E+08 2.549E+04 3.076E+04 6.166E-08 0.000E+00 7.204E-02

! TE-129 9.815E+03 2.163E+07 TE-131M 3.078E+05 9.459E+06 2.244E+07 2.054E+03 3.450E+07 8.489E-32 0.000E+00 1.349E-14 TE-131 9.325E+06 3.111E+07 TE-132 3.774E+05 4.9685+06 4.551E+07 I 6.692E+06 3.845E+08 6.758E-04 1.370E+08 l I-130 1.846E+06 4.754E+10 1.624E+07 2.089E+07 4.333E+11 5.503E+09 l I-131 2.4295-57 7.314E+03 I-132 1.935E+05 1.452E+06 5.129E+0L 2.981E+06 3.945E+09 1.304E+02 8.113E+08

- I-133 3.848E+06 6.622E-03 5.0695+04 5.305E+05 3.624E-10 0.000E+00  ;

i I-134 9.973E+06 I-135 7.918E+05 2.947E+06 8.607E+06 1.0398-14 l 8.007E+09 3.715E+10 1.513E+09 2.631E+10 CS-134 1.014E+06 2.247E+08 1

CS-136 1.709E+05 1.702E+08 2.773E+09 4.426E+07 j 1.334E+09 2.392E+10 CS-137 9.065E+05 1.201E+10 3.224E+10 8.399E+02 4.102E+05 5.5285-23 0.000E+00 9.1333-11 j CS-138 0.000E+00 2.950E+00 BA-139 5.772E+04 1.194E+05 1.231E-05 2.767E+08 d

'RA-140 1.743E+06 2.346E+07 1.171E+08 4.384E+07 2.919E+03 4.734E+04 1.2105-45 0.000B+00 1.605E-21 i RA-141 4.105E-39

j. BA-142 1.643E+03 5.064E+04 0.000E+00 0.000E+00 2.180E+07 1.894E+05 5.492E+02 3.166E+07 LA-140 2.257E+05 1.582E+01 l

7.585E+04 8.886E+05 2.9045-06 0.000E+00 1 LA-142 1.382E+07 4.082E+08 CE-141 5.439E+05 1.540E+07 1.361E+07

-l 2.627E+06 1.488E+06 2.516E+02 1.364E+07 CE-143 1.273E+05 1.039E+10 CE-144 1.195E+07 8.032E+07 1.3265+08 1.893E+08 l 0.000E+00 7.754E+05 3.609E+07 1.575E+08 PR-143 4.329E+05 3.829E-23 i

PR-144 1.565E+03 2.112E+03 2.040E-50 0.000E+00 1.009E+07 5.712E+05 1.505E+07 9.197E+07 ND-147 3.282E+05 5.380E+06 W-187 9.102E+04 2.740E+06 2.420E+06 2.790E+00 4

1.975E+06 9.138E+04 2.232E+03 1.357E+07 NP-239 6.401E+04 l Units: Inhalation 2and all tritium pathways - mrom/yr per gCi/m 1 Others - m . mrom/yr per pC1/sec i

! Values based on standard NUREG-0133, Section 5.3.1 assumptions unless otherwise indicated.

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T_ tate 2.2-2c a

PATHWAY DOSE FACTORE FOR LCO 6.11.6 AMD i

SECTION 2.2.2.b, (R )

Page 1 of 2 i

i AGE GROUP OreF4Anre) ( N.A. ) Orm-6 Ante) haa inrR) OrmeeldRB)

ISOTOPE Ibruar ATION nantfMD PT We dBB/ COW / MILK MBR/ COW / MEAT VEGETATION H-3 1.272E+03 0.000E+00 9.941E+02 1.930E+02 2.588E+03 j 3.690E+0S

C-14 2.600E+04 0.000E+00 4.859E+08 2.040E+0S NA-24 1.376E+04 1.385E+07 4.255E+06 1.0845-03 2.389E+05 l

i P-32 1.888E+06 0.000E+00 3.153E+10 3.931E+09 1.608E+09 CR-51 2.0965+04 5.5065+06 8.3875+06 9.471E+05 1.037E+07 1.984E+06 1.625E+09 2.875E+07 1.436E+07 9.320E+0B

! MK-54 9.451E+02 MN-56 5.744E+04 1.068E+06 4.8565-01 8.302E-52 l

1.240E+05 0.000E+00 4.454E+07 2.382E+08 3.259E+0S FE-55 9.895E+08 l

FE-59 1.528E+06 3.204E+08 2.061E+08 1.171E+09 1.344E+06 4.464E+08 1.095E+08 1.942E+08 6.034E+08 CO-58 3.238E+09

' CO-60 8.720E+06 2.532E+10 3.621E+08 7.600E+0S 5.800E+05 0.000E+00 1.182E+10 1.5195+10 1.606E+10

! NI-63 3.966E+02

' NI-65 3.672E+04 3.451E+05 4.692E+00 1.3053-51 CU-64 6.144E+04 6.876E+05 3.293E+06 1.7135-05 6.465E+05 ZN-65 1.240E+06 0.583E+08 7.315E+09 8.688E+08 1.471E+09 1

ZN-69 1.584E+03 0.000E+00 1.7605-11 0.000E+00 2.0675-05

. 1.7905-01 5.0665-57 2.911E+00 BR-83 3.440E+02 7.079E+03 i

RR-84 4.328E+02 2.363E+05 2.8773 23 0.000E+00 2.2515-11 l

ER-85 1.832E+01 0.000E+00 0.000E+00 0.000E+00 0.000E+00 l

RB-86 1.904E+05 1.035E+07 4.746E+09 4.101E+08 2.772E+08 1

RB-88 5.456E+02 3.7795+04 3.884E-45 0.000E+00 3.168E-22 RB-89 3.520E+02 1.452E+05 9.774E-54 0.000E+00 1.247E-26 l

2.416E+06 2.509E+04 2.674E+09 2.545E+08 1.513E+10 l SR-89 7.507E+11 SR-90 1.000E+08 0.000E+00 6.612E+10 8.049E+09 l

SR-91 2.592E+05 2.511E+06 2.4093+05 5.794E-l's 1.291E+06 l

1.192E+05 8.631E+05 2.277E+01 2.5165-48 1.012E+04 j SR-92 1.025E+08 Y-90 5.592E+05 5.3085+03 1.074E+06 7.470E*05 3.200E+03 1.161E+05 5.1295-18 0.000E+00 2.285E-07

! Y-91M 3.212E+09 Y-91 2.9363+06 1.2073+06 6.475E+06 3.910E+0S l

1.648E+05 2.142E+05 2.8285+00 3.522E-35 2.360E+04 Y-92 4.983E+06 j Y-93 5.792E+05 2.534E+05 1.312E+04 1.6885-07 2.6805+06 2.8375+08 1.201E+06 1.092E+09 1.253E+09 j ZR-95 1.673E+07

• ZR-97 6.304E+05 3.445E+06 (.225E+04 9.231E-01 7.512E+05 1.605E+08 3.3385+08 4.251E+09 4.551E+08 l NE-95 1.293E+07

MO-99 2.688E+05 4.626E+06 1.023E+08 1.892E+05 6.1285+03 2.109E+05 1.055E+04 6.471E-18 5.011E+03 b TC-99M 3.229E-29 TC-101 6.672E+02 2.277E+04 3.287E-50 0.000E+00 1.265E+08 1.513E+05 7.162E+09 5.706E+08 1 RU-103 7.832E+05 4.039E+04 RU-105 9.040E+04 7.212E+05 1.263E+00 3.900E-25 1.6083+07 5.049E+08 1.7995+06 1.130E+11 1.484E+10 l RU 106 4.031E+09

AG-110M 6.752E+06 4.019E+09 2.559E+10 1.345E+0F t

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i TABLE 2 . 2 -2 e (Continued)

PATHWAY DOSE FACTORS FOR LCO 6.11.6 AND SECTICN 2.2.2.b, (R )

Page 2 of 2 h -- =nen ) (1--atarn) (TE_n_r_an ER)

AGE GROUP (Tie 4GER) ( N.A. )

INH _17.ATION GROtarn yt_i_wrv nam / COW /MTiK C#4/ COW / MEAT VEGETATION ISOTOPE l

5.360E+05 2.128E+06 8.863E+07 8.941E+08 4.375E+08 TE-125M 2.236E+09 TE-127M 1.656E+06 1.083E+05 3.420E+08 3.816E+09 8.080E+04 3.293E+03 9.572E+04 1.689E-08 4.100E+05 l TE-127 1.50SE+09 TE-129M 1.976E+06 2.305E+07 4.602E+08 3.966E+09 3.296E+03 3.076E+04 2.196E-09 0.000E+00 3.418E-03 i TE-129 3.240E+07 TE-131M 6.200E+05 9.4595+06 2.529E+07 1.447E+04 TE-131 2.336E+03 3.450E+07 2.8795-32 0.000E+00 6.099E-15 4.632E+05 4.9685+06 8.581E+07 2.300E+07 7.818E+07 TE-132 8.276E+07 I-130 1.4883+06 6.692E+06 1.742E+08 4.005E-04 1.464E+07 2.009E+07 2.195E+11 3.645E+09 3.140E+10 I-131 4.262E+03 i

I-132 1.512E+05 1.452E+06 2.242E+01 1.389E-57 i

2.920E+06 2.981E+06 1.674E+09 7.234E+01 4.587E+08 I-133 3.054E-03 I 134 3.952E+04 5.305E+05 1.583E-10 0.000E+00 j 5.832E+06 I-135 6.2085+05 2.9473+06 3.777E+06 5.9635-15 4

1.128E+06 8.007E+09 2.310E+10 1.231E+09 1.671E+10 CS-134 1.700E+08 CS-136 1.936E+05 1.702E+08 1.759E+09 3.671E+07 CS-137 8.480E+05 1.201E+10 1.781E+10 9.634E+08 1.3485+10 CS-138 8.560E+02 4.102E+05 3.1495-23 0.000E+00 6.9355-11 RA-139 6.464E+03 1.194E+05 7.741E-07 0.000E+00 2.4725-01

! 2.130E+08

BA-140 2.032E+06 2.346E+07 7.483E+07 3.663E+07 BA-141 3.288E+03 4.734E+04 4.9225-46 0.000E+00 8.6995-22 RA-142 1.912E+03 5.064E+04 0.000E+00 0.000E+00 2.269E-39 4.872E+05 2.180E+07 2.291E+05 8.689E+02 5.104E+07 i LA-140 1.868E+00 LA-142 1.200E+04 8.886E+05 2.5745-07 0.000E+00 6.136E+05 1.540E+07 1.696E+07 2.252E+07 5.404E+08 CE-141 2.040E+07 CE-143 2.552E+05 2.627E+06 1.671E+06 3.695E+02 1.336E+07 8.032E+07 1.655E+08 3.089E+08 1.326E+10 CE-144 2.310E+08 PR-143 4.832E+05 0.000E+00 9.553E+05 5.817E+07 PR-144 1.752E+03 2.112E+03 1.238E-53 0.000E+00 3.097E-26 3.720E+05 1.009E+07 7.116E+05 2.452E+07 1.424E+08 ND-147 7.8395+06 W-187 1.768E+05 2.740E+06 2.646E+06 3.9895+00 l

1.320E+05 1.9765+06 1.060E+05 3.3875+03 2.097E+07

! NP-239 Units: Inhalation 2and all tritium pathways mrom/yr per gCi/m Others - m . mrom/yr per pCi/sec Values based on standard NUREG-0133, Section 5.3.1 assumptions unless otherwise indicated.

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Timrm 2.2-2d PATmtAY DORE FAcrORE FOR fro E.11.6 AND sacTION 2.2.2.b, (Rg) l Page 1 of 2 N. A. ) ( WTf T ) ( ADtfLT ) ( ADtfLT )

Ada GROUP t AD ET ) (

MDR/ COW /" 1T F - mTION l INF1TATION Gb - PT *" n#8/ COW /MTI.E ISOTCPn 3.2485+02 2.260E+03 i

H-3 1.264E+03 0.000E+00 7.6293+02 I

0.000E+00 2.634E+08 2.414E+08 2.2765+08 l C 14 1.8165+04 1.3563 03 2.690E+05 NA 24 1.024E+04 1.385E+07 2.4385+06 j

0.000E+00 1.7095+10 4.651E+09 1.403E+09 P 32 1.320E+06 1.772E+06 1.1685+07 i

CR 51 1.440E+04 5.5065+06 7.1875+06 I

1.625E+09 2.5785+07 2.812E+07 9.585E+08 MN 54 1.400E+06 5.082E+02 2.024E+04 1.0683+06 1.3285 01 4.958E 52 l MN 56 2.933E+08 2.0965+08 FE-55 7.2095+04 0.000E+00 2.511E+07 3.204E+08 2.3265+08 2.080E+09 9.875E+08 FE-59 1.0162+06 6.252E+08 9.280E*05 4.464E+08 9.565E+07 3.703E+04 CO-58 1.413E+09 3.1395+09 CO 60 5.96Sg+06 2.532E+10 3.042E+08 l 0.000E+00 6.7295+09 1. 8885+2.0 1.040E+10 l

! NI 63 4.320E+05 7.4055-52 2.0265+02 NI 65 1.232E+04 3.451E+05 1.2195+00 l

6.8763+05 2.031E+06 2.3075 05 7.841E+05

. CU 64 4.8965+04 1.132E+09 1.0095+09 ZN 65 8.540E+05 8.583E+08 4.365E+09 j

0.000E+00 5.2073 12 0.000E+00 1.2025 05 j ZN 69 9.200E+02 8.6483-57 4.475E+00 BR 43 2.4085+02 7.0795+03 1.3995 01 2.363E+05 1.6095 23 0.000E+00 2.4753 11 ER 84 3.124E+02 0.000E+00 0.000E+00 ER 85 1.280E+01 0.000E+00 0.000E+00 1.035E+07 2.604E+09 4.914E+08 2.217E+08 j RE 86 1.352E+05 0.000E+00 3.4285 22 RE 88 3.872E+02 3.7795+04 2.1395-45 i

1.452E+05 5.5235 54 0.000E+00 1.3455 26

( RE-89 2.560E+02 9.961E+09 SR 89 1.400E+06 2.5095+04 1.4515+09 3.014E+04

}

0.000E+00 4.680E+10 1.244E+10 6.0465+11 j SR 90 9.920E+07 7.2333-10 1.4515+06 SR 91 1.912E+05 2.511E+06 1.3775+05 8.631E+05 9.675E+00 2.3345 48 8.452E+03 SR 92 4.304E+04 1.410E+08 i

Y 90 5.0565+05 5.3085+03 7.5115+05 1.1415+06 j

1.161E+05 1.7435-19 0.000E+00 1.527E 08 Y-91M 1.920E+03 2.814E+09 s

1.704E+06 1.2075+06 4.7265+06 6.231E+08 Y-91 2.6575 35 1.603E+04 l

Y-92 7.352E+04 2.142E+05 9.7723-01 i

2.534E+05 7.384E+03 2.0755 07 5.5175+06 Y-93 4.2165+05 1.194E+09

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ZR 95 1.768E+06 2.8375+08 9.5875+05 1.903E+09 3.445E+06 2.7075+04 1.292E+00 2.1083+07

' ZR 97 5.232E+05 4.790E+08 NE-95 5.0485+05 1.605E+08 2.7865+08 7.7485+09 l 4.6263+06 5.741E+07 2.3185+05 1.426E+07 MD 99 2.480E+05 5.1875+03 TC-99M 4.160E+03 2.109E+05 5.553E+03 7.4395 18 3.992E+02 2.277E+04 1.813E 58 0.000E+00 3.5023-29 TC 101 1.2295+10 5.577E+08 RU 103 5.0483+05 1.265E+08 1.1895+05 7.212E+05 5.2405-01 3.5335 25 3.294E+04 RD-105 4.8165+04 1.2475+10 RU 106 9.360E+06 5.0495+08 1.320E+06 1.811E+11 4.0193+09 2.1983+10 2.523E+09 3.9793+09 AG 110M 4.632E+06 GRAED GULF, UNIT 1 2.0-21 Revision 17 - 03/95

TAntz 2.2-2d (Continued)

PATHWAY DOSE FACTORS FOR LCO 6.11.6 AND SECTION 2.2.2.b, (Rg)

Page 2 of 2 ADULT ) ( N. A. ) ( ADULT ) ( ADULT ) ( ADULT )

AGE GROUP (

ISOTOPE INFafATION nanfarn Pf Anff can/ COW / MILK non/ COW / MEAT VEwi ATION TE-125M 3.136E+05 2.128E+06 6.626E+07 1.460E+09 3.927E+08 TE-127M 9.600E+05 1.003E+05 1.860E+08 4.531E+09 1.418E+09 TE-127 5.736E+04 3.293E+03 5.274E+04 2.034E-08 4.532E+05 TE-129M 1.160E+06 2.305E+07 3.020E+08 5.690E+09 1.261E+09 TE-129 1.936E+03 3.076E+04 9.167E-10 0.000E+00 2.806E-03 5.560E+05 9.459E+06 1.753E+07 2.190E+04 4.42SE+07 TE-131M 6.575E-15 TI-131 1.392E+03 3.450E+07 1.5785-32 0.000E+00 TE-132 5.096E+05 4.968E+06 7.324E+07 4.287E+07 1.312E+08 I-130 1.136E+06 6.692E+06 1.050E+08 5.272E-04 9.809E+07 I-131 1.192E+07 2.0895+07 1.3885+11 5.034E+09 3.785E+10 I-132 1.144E+05 1.452E+06 1.342E+01 1.816E-57 5.016E+03 I-133 2.152E+06 2.951E+06 9.891E+00 9.3365+01 5.331E+08 I-134 2.984E+04 5.305E+05 9.4915-11 0.000E+00 4.544E-03 l 4.480E+05 2.9473+06 2.2173+06 7.644E-15 6.731E+06 I-135 CS-134 8.480E+05 8.007E+09 1.345E+10 1.565E+09 1.110E+10 1.464E+05 1.702E+08 1.0365+09 4.724E+07 1.675E+08 CS-136 8.6965+09 CS-137 6.200E+05 1.201E+10 1.010E+10 1.193E+09 CS-138 6.2085+02 4.102E+05 1.7065-23 0.000E+00 7.7305-11 RA-139 3.760E+03 1.194E+05 0.322E-00 0.000E+00 5.2255-02 BA-140 1.272E+06 2.346E+07 5.535E+07 5.9175+07 2.6465+08 BA-141 1.936E+03 4.734E+04 2.677E-46 0.000E+00 9.3055-22 1.192E+03 5.064E+04 0.000E+00 0.000E+00 2.463E-39 RA-142 7.327E+07 LA-140 4.504E+05 2.100E+07 1.672E+05 1.305E+03 LA-142 6.325E+03 8.4863+05 3.503E-00 0.000E+00 4.999E-01 3.616E+05 1.540E+07 1.253E+07 3.632E+07 5.097E+08 CE-141 2.758E+07 CE-143 2.264E+05 2.627E+06 1.1495+06 5.547E+02 CE-144 7.776E+06 5.032E+07 1.209E+08 4.920E+08 1.112E+10 2.808E+05 0.000E+00 6.923E+05 9.204E+07 2.748E+08 PR-143 3.3035-26 PR-144 1.016E+03 2.112E+03 6.716E-54 0.000E+00 2.2085+05 1.009E+07 5.231E+05 3.935E+07 1.853E+08 ND-147 1.0465+07 W-187 1.552E+05 2.740E+06 1.796E+06 5.512E+00 1.192E+05 1.9765+06 7.385E+04 5.152E+03 2.872E+07 NP-239 3

Units: Inhalation 2and all tritium pathways - mres/yr per pCi/m others - m . ares /yr per gci/sec values based on standard NUREG-0133, Section 5.3.1 assumptions unless otherwise indicated.

GRAND GULF, UNIT 1 2.0-22 Revision 17 - 03/95 i

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TABLE 2.2-3 CONTROLLING RECEPTORS. LOCATIONS. AND A*INOSPHERIC DISPERSION PARAMETERS

• for LCO 6.11.5. 6.11.6. AND 6.11.8 l NEAREST NEAREST RESIDENCE, GARDEN, SEC"f0R DIRECTION MILES ** x/O MILES ** D/Q A N 0.92 3.30E-6 >5 N/A B NNE 0.75 2.95E-6 >5 N/A NE 0.66 2.305-6 4.78 2.18E-10 C

ENE 2.67 2.00E-7 2.8 4.90E-10 D

E E 0.61 1.60E-6 0.81 2.96E-09 F ESE 2.3 2.575-7 >5 N/A G SE 2.11 3.10E-7 >5 N/A-H SSE 1.13 1.40E-6 4.16 3.92E-10 J S 3.11 4.95E-7 25 N/A I

K SSW 2.17 1.40E-6 2.17 1.30E-9 W

SW 0.89 8.30E-6 0.89 6.70E-9 4 L

M WSW >5 N/A >5 N/A N W >5 N/A >5 N/A T

P WNW 4.78 4.735-7 4.78 2.30E-10 NW 35 N/A 35 N/A Q

R NNW 1.08 2.60E-6 >5 N/A i

Table 2.2-3 based on 1994 Land Use Censua The most limiting age group, child, is assumed.

1

• Values from ODCM Reference 9. ~

• • Distances shown are actual miles in each sector. In cases where dispersion parameters were not available for a location they were taken from the closest distance interval to the plant.

j N/A: No residence / garden within 5 miles.

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T1Bf f 2.2-3a SITE BotsmanY ATMOSP8ffBTC DISPfBRION PARAMETERE*

' for LCO 6.11.4

,i j SITE BOUNDARY DISTANCE, j SECTOR DIRECTION MILES ** x/Q D/Q j l

1 A N 0.79 4.15-6 8.2E 9 4

5 NNE 0.66 3.6E-6 7.7E 9 C NE 0.63 2.5E-6 6.6E-9 1

D ENE 0.63 2.05-6 5.8E-9 l

E I 0.55 1.9E-6 4.9E-9 F ESE 0.55 2.05-6 5.9E-9 j

j G SE 0.51 2.8E-6 8.2E-9

't H SSE 0.46 5.EE-6 1.65-8 l 5.sE-6 1.2E-s j J S 0.61 x SSN 0.65 s.4E-6 1.0E-s l ,

i L SW 0.85 8.95-6 7.25-9 4

I M WSW 1.07 8.43-6 5.1E-9 i

N W 1.14 5.45-6 3.4E-9 P WNW 1.34 2.65-6 1.9E-9 f

! Q NW 1.37 1.6E-6 1.6E-9

't 2.85 6 4.0E-9 R NNW 1.02

}

1 The most limiting age group, infant, is assumed.

• Values from CDCM Reference 9.

• • Distances shown are actual miles in each sector.

GRAND GULF, UNIT 1 2.0-23a Revision 17 - 03/95 i

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i TABLE 2.2-3b ADDITIONAL RECEPTOR LOCATIONS WITHIN THE SITE BOUNDARY l

SECTOR DIRECTION MILES DESCkIPTION x/Q D/Q B NNE 0.5 Recreational 5.438E-6 1.204E-8 Vehicle Laydown Area R NNW 0.5 Energy 8.422E-6 1.310E-8 Services Center' Q NW 0.75 Gin Lake' 3.958E-6 4.531E-9 P WNW 0.75 Hamilton Lake' 6.266E-6 5.215E-9

'These locations occupy multiple sectors. In each case the SITE BOUNDARY locations used in the dose calculation was limiting.

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- l 2.3 Mateorolooiemi is~4 1 1 l

2.3.1 h = =harie Dianarmion The atmospheric dispersion for gaseous releases may be i calculated using a ground level, wake-split fem of the  ;

straight line flow model. l X/Q = atmospheric dispersion (sec/m*)

2.01 ak rur where r = distance (m) fr a release point to location of interest 1

8 = plume depletion factor at distance r from ODCM Figure 2.3-1 u = wind speed at ground level (m/sec) l k = open terrain recirculation factor at distance r, from CDCM Figure 2.3-4 (not used)

E = the lesser of (a8 + E) or /3 a w

where:

a = vertical standard deviation (m) of the plume at distance r for ground level releases under the stabilitycategoryindicatedbyh,fromCDCM Figure 2.3-2 h = toeperature differential with vertical separation (*K/100m) b = height of the reactor building = 53.3m GRAND GULF, UNIT 1 2.0 24 Revision 17 - 03/95

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2.3.2 Decosition 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' )

. L.f1 (D )

r 9 where:

i D = relative deposition rate at distance r for ground l g level releases from ODCM Figure 2.3-3 t

i x/Q and D/Q values were calculated using the methodology of NUREG/CR-2919 axnoDoQ: computer Program for the Meteorological Evaluation of Routine Effluent Releases at Nuclear Power Stations".

f GGNS gaseous releases are ground level.

Additional infomation on the X/Q and D/Q calculations can be found in l CDCM References 9 and 10. i k

I 4

GRAND GULF, UNIT 1 2.0-25 Revision 17 - 03/95 F

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l GRAND GULF, UNIT 1 2.0-26 Revision 17 - 03/95 l

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

2.4 Definitiaa= of rimmeous Effluents Par ===ters b = 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 )

C' = count rate of station vent monitor corresponding to a 1.0

1. Ci/ml concentration of Xe-133 (2.1.2)

D = relative deposition rate for ground level releases from Figure 2.3-3 (m" ) (2.3.2)

D, = average organ dose rate in current year (arem) ( 2 . 2 .1. b)

D = dose to an individual from radiciodines and radionuclides in P

particulate form, with half-life greater than eight days (area)

(2.2.2.b)

D, = average skin dose rate in current year (area) (2.2.1.a)

D = average t tal body dose rate in current year (mram) ub (2 . 2 .1. a )

D,

- air dose due to beta emissions from noble gas radio-nuclide i (mrad) (2.2.2.a)

D = air dose due to gansna emissions from noble gas radio-nuclide i (mrad) (2.2.2.a)

D/Q = relative deposition per unit area (m" ) (2.3.2) a = 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 = fraction of current year elapsed at time of calculation (2.1.1) k - open terrain recirculation factor at distance r from Figure 2.3,1 (2.3.1)

GRAND GULF, UNIT 1 2.0-27 Revision 3 - 05/84

2.4 Defin4tiana of naaeous Effluents Para- ters (Continued)

K = total body dose factor for Kr-89, the most restrictive isotope (mrem /yr per gCi/m ), from Table 2.1-1 (2.1.2)

K = total body dose factor due to ganuma emissions from i 3 isotope 1 (arem/yr per pC1/m ) from Table 2.1-1 (2.1.1)

D = limiting dose rate to the total body based on the limit 3

of 500 mrom in one year. (2.1.1)

D,, = limiting dose rate to the skin based on the limit r,f 3000 mrem in one year. ( 2 .1.1)

L = skin dose factor for Kr-OS, the most restrictive isotope (mree/yr per gCi/m8) from Table 2.1-1 (2.1.2)

L = skin dose factor due to beta emissions from isotope i (mrom/yr per gC1/m8 ) , from Table 2.1-1 (2.1.1)

M = air dose factor for Kr-SS, tha most restrictive isotope (mrad /yr per gc$/m8) from Table 2.1-1 (2.1.2)

Mg = air dose factor due to gamma emissions from isotope 1 (mrad /yr per pCi/m8) from Table 2.1-1 (2.1.1)

N = air dose factor due to beta emissions from noble gas radionuclide 1 (mrad /yr per gCi/m8) from Table 2.1-1 (2.2.2.a)

P = dose parameter for radionuclide i, (mram/yr per gCi/m s ) for J

inhalation from (m8 mrem /yr per gci/sec) for other pathways, from Table 2.2-1 (2.2.1.b). .

O*g

= rate of release of noble gas radionuclide 1 (gCi/sec) (2 .1.1)

{= average release rate for the current year (gci/sec) of isotope i of tritium, I-131, I-133 or other radionuclide in particulate form, with half-life greater than eight (t) days (2.2.1.b)  ;

Qg = cumulative release of radionuclide i of noble gas, tritium, I-131, I-133, or material in particulate form over the period of interest (gCi) (2.2.2.a) (2.2.2.b)

GRAND GULF, UNIT 1 2.0-28 Revision 5 - 01/85 1

., l

2.4 Def4"4tians of ammeous Effluents Parameters (Continued)

Q'g = assigned release rate value of, for example, 1.0 gC1/sec, Xe-133; related to definition of C' for the vent. (Note 3)

R = dose factor for radionuclide i, (mrom/yr per Ci/m8) or (m mres/yr per gCi/sec)

R, = count rate per mrom/yr to the skin. (2.1.1)

R = coat rate per mem/g to the total W. (2.1.1) t ,

l R", = conservative count rate per mres/yr to the skin. (2.1.2) l R" = conservative count rate per mrom/yr to the total body (Xe-133 detection, Kr-89 dose). ( 2 .1. 2 )

l r - distance (m) from release point to location of interest for

- dispersion calculation. ( 2 . 3 .1)

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GRAND GULF, UNIT 1 2.0-29 Revision 3 - 05/84 ,

l i

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

2.4 Definitiene of Mm=eous Effluents Paramatars (Continued)

J S y

= count rate of station vent noble gas monitor at alarm setpoint level. (2.1.1)

E = vertical standard deviation of the plume with building wake correction (m). (2.3.1) a - vertical standard deviation (m) of the plume at distance r for effective height under stability category indicated by T(m)

, from Figure 2.3-2. (2.3.1)

T = temperature dif ferential with vertical separation (*K/100m) .

(2.3.1) i u = wind speed at ground level (m/sec). (2.3.1) l W = controlling sector annual average atmospheric dispersion at the site boundary for the appropriate pathway (sec/m8). (2.2.1.b)

W' = relative concentration for unrestricted areas (sec/m s ).

(2.2.2.b)

X/Q = atmospheric dispersion (sec/m s ) (2.3.1) ,

E76 = highest sector annual average atmospheric dispersion at the unrestricted area boundary (sec/m8) ( 2 .1.1) 275 = relative cone ntration for unrestricted areas (sec/m8)

(2.2.2.a) l l

l GRAND GULF, UNIT 1 2.0-30 Revision 3 - 05/04

Fimire 2 . 3 - 1 Plo= Denistion Effect for Ground.Laval Relemmes (All Atmospaaric Stability Classes) o S .1 ll 2 .

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. _...__ .....__._. m. ._.____._ ..._.- _.- . . . _ . . _ _ ._.__._ _ __ __.-__-__ ___________ ____.

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Piaura 2.3-2 j vertieni standard Deviation of Material in a plu==

l (Letters denote Pasqu111 Stability Class) i j 1000 , , , . .- - -

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.l.3 to .0.1 D g N'g*,*,,I gg; ,,y,

.o.s = t.s I3 , y, " O carumWy e Graph taken from Reference 7 Figure 1 GRAND GULF, UNIT 1 2.0-32 Revision 15 - 01/94

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

d Fiaure 2.3 3 Relative Daemition for Ground. Level Relammes (All Atmosphenc Stability classes) 104 a

N \

W 104 g 'm '

a Nu W '

u b N W T m T

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+ 104 ,

f . .

177 .t L 0.1 1.0 10.0 100.0 200.0 r, PLUME TRAVEL DISTANCE (KILOMETERS)

Graph taken from Reference 7, Figure 6 GRAND GULF. UNIT 1 2.0-33 Revision 15 - 01/94

Fimira 2. 3 -4 Onen Terraint Racirculation Facter E

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- d" k, CORRECTION FACTOR raph taken fross Reference 6, Figure 2 GRAND GULF, UNIT 1 2.0-34 Revision 15 - 01/94

l

~ 1

)

2.5 cameous Radwaste Treatment System The instruments required to be checked by LCO 6.11.7 to ensure that

! the GASEOUS RADWASTE TREATMENT (Offgas) SYSTEM is functioning are: ,

i I 1. Adsorber train bypass switch (1N64-HS-M611) j

2. Bypass valve indication (1N64-F045) d When the adsorber train bypass switch is in the TREAT position and the bypass valve indicates closed, the GASEOUS RADWASTE TREATMENT j (Offgas) SYSTEM is functioning.

I J

NOTES for ODCM Fiau h b A flow diagram for the Gaseous Radwaste Treatment System is provided on the following page. Notes for the diagram are listed below.

' (1) The charcoal beds are bypassed during startup until an adequace dowpoint is obtained in the process stream.

(2) This pathway may be utilized for power levels s St. l

\

(3) Standby Gas Treatment System not norlaally operated. 1 l

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GRAND GULF, UNIT 1 2.0-35 Revision 17 - 03/95

. \

Ficrura 2. 5 1 Gameous lladwasta Treatment SYEtem to AmoePet W 0*8 PDAdB LJet (t) , '. .*

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G M GUI.F. UNIT 1 2.0-35a Revision 3 - 08/86

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

e a

4 2.6 Annumi Dome c - 4tment If required, the annual (calendar year) dose or dose comitment to i' any MEMBER OF ' DIE PUBLIC will be calculated by suming the following doses for the calendar years f

• Direct radiation dose t

i e Liquid effluent dose (D )

) e Noble gas dose (D , D )

l

• Particulate dose (D )

1 These calculations are required only if the liquid or gaseous effluents exceed twice the limits of LCOs 6.11.2, 6.11.5 and 6.11.6.

4 i 2.6.1 Direct Pad 4mtion Dose W==ur--- t LCOs 6.11.2, 6.11.5 and 6.11.6 require the determination

of cumulative dose contributions to a MEMBER OF THE PUBLIC 4

from direct radiation from the reactor units and from i

radwaste storage tanks. This requirement is applicable

+

' only under conditions set forth in Action B.1 of the I

i applicable LCo. This determination is made by the i

utilization of direct radiation measurements from indicator thermoluminescent dosimeters (TLDs) located near the GGNS property line in each of the 16 meteorological sectors.

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l GRAND GULF, UNIT 1 2.0-36 Revision 17 - 03/95

J a

Measurements frosi these TLDs represent the direct radiation generated by the facility plus normal background radiation. The locations are identified in ODCM Table 3.0-3 by the following TLD numbers:

M-16 M-22 M 41 M 86 M 20 M 25 M-23 M 92 M 19 M-27 M-17 M-93 M 21 M-28 M-45 M 94 f Centrol TLDs are also utilised to differentiate between l background radiation and direct radiation front the facility. The following two TLDs are designated as controls based on the criterica that they are located ten miles or greater from the facility. Exact locations are

, identified in 00 3 Table 3.0-3.

M 14 M 33 The difference between the averaged quarterly radiation measurements of the indicator TLDs and the centrol TLDs represents the direct radiation dose to a MERSIR OF 7EE PUBLIC from the operating facility.

GRAND GULF, UNIT 1 2.0 37 Revision 17 - 03/95 4

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. 1 3.0 RADIOttX2ICAL ENVIRONheNTAL MONITORING l 3.1 Samolina Locations I

Sampling locations to fulfill the requirements of LCO 6.12.1, as  ;

1 l

described in ODCM Table 6.12.1-1, are identified in ODCM Tables  ;

l l

i 3.0-1 through 3.0-3 and shown on maps in ODCM Figures 3.0-1 and l

! 3.0-2.

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i GRAND GULF, UNIT 1 3.0-1 Revision 17 - 03/95

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

1 3

t

• E TAat_2 3.0-1 s

AIR SAMPLER Cot.tTCTION SITES l

AIR SAMPLERS s

m FIGURE IDCATION AS-1 PG 3.0-2 Southeast of GGNS at the Port Gibson City Barn i

(Sector G Radius, 5.5 miles) l AS-3 61VA 3.0-2 NNE of GGNS on Hwy. 61, north of the vicksburg Airport (Sector B Radius, 18 miles)

J AS-5 TC 3.0-1 S of GGNS at the former Training Center l (Sector J Radius, 0.4 miles) s i AS-6 BF 3.0-1 SSN of GGNS at the GGNS Ball Field (Sector K Radius, 0.4 miles)

! AS-7 UH 3.0-1 SSE of GGNS at the IEEN Union Hall (Sector E Radius, 0.5 miles) i a

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GRAND GULF, UNIT 1 3.0-2 Revision 17 - 03/95

~

~ . . . .. - ~ . . .

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TARI2 3.0-2 l l

MISCZ1LANIQUS COLLECTION SITES i i

Page 1 of 2  !

MILK SAMPLES (CONTROL LOCATION) M 1

ALCONT 3.0-2 Located SSW of GGNS at Alecrn i State University (Sector K Radius 10.5 miles)

CISTERN WATER McGee Cistern 3.0-1 Located north of GGNS at the McGee house on Frasier Road I (Sector A Radius 0.9 miles)

Willis Cistern 3.0-2 Located at the C. E. Willis house on Shiloh Road INE of GGNS near l the Shiloh Baptist Church (Sector l D Radius 6 miles)

GROUND WATER I

PGWELL 3.0-1 PORT GIBSON WILLS - Taken from distribution system or one of the five wells (Sector G Radius 5.0 miles)

AAWELL 3.0-1 Arnold Acres Well (Sector J Radius 1.1 miles)

GRAND GULF, UNIT 1 3.0-3 Revision 15 - 01/94

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M TABLE 3.0 2 (continued)

MISCELLANEOUS COMFCTION SITES Page 2 of 2 4

SURFACE WATER FIGURE 3.0-1 At least 4500 ft upstream of the ,

Upstream

' GGNS discharge point into the l Mississippi River to allow adequate mixing of the Mississippi and Big Black Rivers 1 (Sector Q-R, 1.8 miles) l Downstream 3.0-1 At least 5000 ft downstream of I s

the GGNS discharge point into the  !

I Mississippi River near Radial Well No. 1 (Sector N, 1.G miles)

Discharge Basin 3.0-1 WNW of GGNS in 3

parking lot. YRD-133-PKG-LOT A (Sector P, 0.2 miles) 4 SEDIMENT SAMPLES SEDHAM 3.0-1 Downstream of the GGNS discharge l l point in the Mississippi River l near Hamilton Lake outlet (Sector

' N, 1.6 miles)

VEGETATION Broadleaf Vegetation 3.0-1 S of GGNS near former Training Center on Bald Hill Road 4 (Sector J, 0.4 miles) 4 4

SSE of GGNS between the former 2

training center and the IBEW Union Hall on Bald Hill Road (Sector H, 0.4 miles)

The above locations are gardens E223: maintained by GGNS inside the SITE BOUNDARY. These two saspling sites exceed the requirements of LCO 6.12.1.

Alcorn State University SSW of GGNS (Sector K, 10.5 miles) when available, otherwise a location 15-30 km distant FISH SAMPLES Fish and Invertebrates Downstream of the GGNS discharge point into the Mississippi River Upstream of the GGNS discharge point into the Mississippi River uninfluenced by plant operations GRAND GULF, UNIT 1 3.0-3a Revision 17 - 03/95 a

M Tant.w 3.0-3 TLD LOCATIONS Page 1 of 7 I

TLD NO. LOCATION M SECTCR M

M-01 Across the road from Lake 3.0-2 E 3.5

Claiborne entry gate

.1 M-07 AS-1 PG, Port Gibson City Barn 3.0-2 G 5.5 M-09 Warner Tully Y-Camp 3.0-2 D 3.5 4

M-10 Grand Gulf Military Park 3.0-1 A 1.5 i

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GRAND GULF, UNIT 1 3.0 4 Revision 15 - 01/94 a

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l E l TAaLE 3.0-3 icmit h"ad)

TLD IDCATIONS Page 2 of 7 l

l TLD NO. IDCATION Z1331 SECTOR M i

AS-3 61VA, Hwy. 61, north of 3.0-2 B 18.0 M 14 i (CONTROL) Vicksburg Airport Me":eorological Tower 3.0-1 A 0.9 M-16 S Side, Grand Gulf Road 3.0-1 C 0.5 M 17 1 3.0-1 E 0.5  !

M 19 Eastern SITE BOUNDARY property line,1015 of HWSA Hasardous waste storage area (HWSA) 3.0 1 F 0.5 l M-20 l

AS-5-TC, near former Training 3.0-1 J 0.4 l M 21 center Building, on Bald Mill Road Former RR entrance crossing on 3 . 0 - l' G 0.5 M 22 Bald Mill Road Gin Lake Road 50 yards north of 3.0-1 Q 0.5 M 23 l

Heavy Haul Road on power pole 3.0-1 N 1.6 M 25 Radial Well Number 1 3.0-1 M 1.5 M 27 WSW near SITE BOUNDARY property line, (Near Bucksnort Road)

Former Glodjo residence 3.0-1 L 0.9 l M 28 l

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l GRAND GUIX, UNIT 1 3.0-5 Revision 17 03/95

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, M l TABLE 3.0-3 (continued) f TLD LOCATIONS i

Page 3 of 7 TLD No. LOCATION M M g M-33 Newellton, Louisiana, Water 3.0-2 P 12.5 j (Control) Tower M-36 Curve on HW 608, point nearest 3.0-2 P 5.0 GGNS at power pole j M-38 Lake Bruin State Park, entrance road 3.0-? M 9.5 1 M-39 St. Joseph, Louisiana, Aux. 3.0-2 M 13.0

, Water Tank M-40 International Paper Road, 3.0-2 M 5.0 South of River Mile Marksr M-41 Radial Well Nwaber 4 3.0-1 P 1.3 M-45 Old Visitor Center gate 3.0-1 D 0.5 is a i 4

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1 GRAND GULF, UNIT 1 3,o.6 Revision 15 - 01/94 f

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9221 TARTE 3.0-3 (Centinued)

TLD LOCATIONS Page 4 of 7 LOCATION FIGURE SECTOR ti1LE TLD NO.

i M-47 Bridge 0.6 miles west of Rodney- 3.0-2 L 5.2 Westside Road /Mont Gomer Road

intersection, north side i

3.0-2 K 4.8 M-48 0.4 miles South on Mont Gomer Road on west side 3.0-2 H 4.5 j M-49 Fork in Bessie Weathers Road /

Shaifer Road  !

4 3.0-2 B 5.3  ;

M-50 Panola Hunting Club entrance j

i 4.2 j M-51 Ingeleide Karnac Ferry Road 3.0-2 C )

a between Deer Camp Road and i

! Y-camp Road D 5.0 j M-55 Near Ingelside Karnac Ferry Road / 3.0-2 Ashland Road Intersection H. W. Watson Elementary ard 3.0-2 G 4.2 M-56 Junior High School J

F 4.5 l M-57 Hwy. 41, behind the Welcome 3.0-2 4

to Port Gibson sign at Glensdale 9 j

Subdivision

,\

) 5.0 M-58 Hwy. 61, Big Bayou Pierre bridge, 3.0-2 E J

• southeast and l 3.0-2 N 5.1 l M-59 Off levee at Winter Quarters I Hunting Camp i  !

4

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' GRAND GULF, UNIT 1 3.0-6a Revision 17 - 03/95 l t

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9 GRAND GULF, UNIT 1 3,0 6b Revision 13 - 01/92

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l 2 21 TABLE 3.0-3 (Continu A) j TLD !.XX*.ATIONS Page 6 of 7 ,

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TLD NO. LOCATION M M g M-86 North Site Access Road 3.0-1 B 0.5 entrance near SITE BOUNDARY l M-88 River mile marker 409.5 3.0-1 A 4.2 I l

M-89 Middle Ground Island 3.0-1 R 4.4 1 M-90 Acrone from Middle Ground Island, 3.0-1 Q 3.5 j near Louiaiana State Line j (Yucatan cutoff of 1929) i l

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i GRAND GULF, UNIT 1 3,0.Gc Revision 15 - 01/94 1-

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I 9221 TABLE 3.0-3 (Centinued)

TLD LOCATIONS I

Page 7 of 7 TLD No. LOCATION FIGURE SECTOR g M-91 Transmission line by pond 3.0-1 J 4.5 (Off Shaifer Road near Widows Creek)

M-92 Fence behind orchard 3.0-1 K 0.4 (Bald Hill Road)

M-93 Underground cable sign 3.0-1 H 0.4 l

(Bald Hill Road) ,

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l M-94 Sector R near 3.0-1 R 0.8 Meterological tower l l

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

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OFFSITE DOSE CALCULATION MANUAL APPENDIX A RADIO!4GICAL EFFLUElfr CONTROLS AND RADICI4GICAL INVIRCISBNTAL MONITORING PROGRAMS I

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" TEXT DEIJETED" GRAND GULF, UNIT 1 A-1 Revision 17 - 03/95

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1.0 DEFINITIONS  !

GASEOUS RADWASTE TREATNENT (OFFCAS) SYSTEM 1.1 The GASEOUS RADWASTE TREND 4ENT (OFFGAS) SYSTEM is the system designed 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. l MEMBER ( S ) OF THE PUBLIC 1.2 MEMBER (S) OF THE PUBLIC shall include individuals in a centrolled or unrestricted area. However, an individual is not a member of the public during any period in which the individual receives an occupational dose.

I OF'? SITE DOSE CALCULATION MANUAL (ODCM) 1.2 The OFFSITE 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 calculation of gaseous and liquid effluent monitoring Alarm / Trip Setpoints, and in the conduct of the Environmental Radiological Monitoring Program. The ODCM shall also contain (1) the Radioactive Effluent Controls and Radiological Environmental Monitoring Programs required by Technical Specification 5.5.4 and Technical Requirement

7. 6. 3.2 and (2) descriptions of the information that should be included in the Annual Radiological Environmental Operating and Annual Radioactive Effluent Release Reports required by Technical

. Specifications 5.6.2 and 5.6.3.

PROCESS ColfrROL PROGRAM (PCPI 1.4 The PROCESS CONTROL PROGRAM (PCP) shall contain the current formulas, sampling, analyses, test, and determinations to be made to ensure that  ;

processing and packaging of solid radioactive wastes based on demonstrated processing 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 wasts GRAND GULF, UNIT 1 A-2 Revision 17 - 03/95

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J j SITE BotMDARY 1.5 The SITE BOUNDARY shall be that line beyond which the land or property is not owned, leased, or otherwise controlled by the licensee.

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! UNRESTRIgTED ARIA I 1.6 An UNRESTRICTED AREA shall be any area, at or beyond the SITE BOUNDARY, access to which is not controlled by the licensee for the purposes of protection of individuals from exposure to radiatico and radioactive materials, or any area within the SITE BOUNDARY used for residential quarters or for industrial commercial, institutional, and/or i recreational purposes. The UNRESTRICTED ARIA and SI'IE BOUNDARY are synonymous with the exception of areas over bodies of water.

VErffLATION rrunneT Teek'P*8Nr BYSTmf 1,7 A VIEFTILATION EINADST TREA'HIElfr SYSTEM is any system designed and

] installed to reduce gaseous radiciodine or radioactive material in

{

1 particulate form in effluents kr/ passing ventilation or vent exhaust j gases through charcoal adsorbers and/or HEPA filters for the purpose of

]

j removing iodines or particulates from the gaseous exhaust stream prior l to the release to the environment (such a system is not considered to f l

f have any effect on noble gas effluents). Engineered Safety Feature j (ESP) atmospheric cleanup systems are not considered to be VIIrrIZATION l

EZMADST TRIKDIElfr SYSTEtt components, i,

! Additional Definitions are listed in Technical Specification Section l I

j 1.1.

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GRAND GUI.F, UNIT 1 A-3 Revision 17 - 03/95

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1 TAntz 1.1 SURVEILLANCE FRROiiENCY NOTATION i

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Surveillrace Frequencies are specified in individual LCOs. For more information see Technical Specificaiton Section 1.4.

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GRAND GULF, UNn 1 A-4 Revision 17 - 03/95

TABLE 1.2 dQDEI Modes of operation are shown in Technical Specification Table 1.1-1 i

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GRAND GULF, IDfIT 1 A-5 Revision 17 - 03/95 a

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3.0 APPLICABILITY l

L NTTING C N ITION POR OPERATION (LCol See Technical Specification Section 3.0 for LCO Applicability.

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l APPLICABILITY munftIt t amCE REOUIsr---is (SR) l 4

1 See Technical Specification Section 3.0 for SR applicability.

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SECTION 5.0 ADIEINISTRATIVE COIrTROLS o

GRAND GULF, UNIT 1 A-8 Revisico 17 - 03/95 i

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s.o s .,6 nreatrva A -i ate s.s.2 m--.a aan nuwstr at urvr -- - -ca openserno mennee Routine radiological enviremanatal operating reports covering the operation of the unit during the previous calendar year shall be submitted before May 1 of each year.

The annual radiological environmental operating reports shall include suusmries, incorpretations, and an analysis of trends of the results of the radiological environmental surveillance activities for the report period, including a cagarison with preoperational studies, operational controle (as appropriatel, sad 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 LCO 6.12.2. If harmful 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 susmarised and tabulated results in the format of Regulatory Guide 4.8, December 1975 of all from Deviations radiological environmental samples taken during the report period. In the event that the sampling program identified in LCO 6.12.1 shall be reported.

some results are not available for inclusion with the report, the report shall be The missing submitted noting and emplaining the reasons for the missing results.

data shall be submitted as soon as possible in a supplementary report.

The reports shall also include the following:

1) a stamary description of the radiological environmental monitoring program

2) a map of all saspling locations keyed to a table giving distances and directions from one reactors

3) and the results of licensee (or offsite laboratory's) participatica in the Interlaboratory Cooperison Program, required by LCO 6.12.1.

GRAND GULF, tDrIT 1 A.9 Revision 17 - 03/95 a

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5. O ANTNISTRATIVE tumJJt 5.6.3 ANNtIAL R&DIMIVE EFFLtfENT Rgiracg ggponT A Radioactive Effluent Release Report covering the operation of the unit during the previous year shall be autanitted before May 1 of each year.

a. The Radioactive Effluent Release Report 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 i 1974, with data summarised on a quarterly basis following the format of Appendix l B thereof. For solid wastes, the format for Table 3 and Appendix B shall be supplemented with three additional categories: class of solid wastes (as defined by 10 CFR Part 61), type of container (e.g., Steel Liner, High Integrity Container) and SOLIDIFICATION Agent or absorbent (e.g., cement, urea forma 1dehyde).

The Radioactive Effluent Release Report 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 on magnetic tape of wind speed, wind direction, atmospheric stability, and precipitation (if measured), 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 MERSERS OF THE PUBLIC due to their activities inside the SITE BOUNDARY during the reporting period. All assusptions used in making these assessments, i.e., specific activity, esposure time, and location, shall be included in these reports. The meteorological conditions concurrent with the time of release of radioactive materials in gaseous effluents, as determined by sangling frequency and measurement or historical annum 1 average meteorological conditions, shall be used for determining the gaseous pathway doses. The assessment of radiation doses shall be performed in accordance with the methodology and parameters in the OFFSITE DOSE CALCUZATION MANUAL (CDCM) .

The Radioactive Effluent Release Report shall also include an assessment of radiation doses to the likely most esposed MBSER 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 calendar year to show conformance with 40 CFR Part ISO, " Environmental Radiation Protection Standards for Nuclear Power Operation." Acceptable methods for calculating the dose contribution frcun liquid and gaseous effluents are given in Regulatory Guide 1.109, Rev 1, October 1977 and NUREG 0133.

The Radioactive Effluent Release Report shall include a list and description of unplanned releases from the site to UNRESTRICTED ARIAS of radioactive materials in gaseous and liquid affluents made during the reporting period.

The Radioactive Effluent Release Report shall include any changes made during the reporting period to the OFFSITE DOSE CAZEUIATICE MANURL (ODCM), pursuant to Technical Specification 5.5.1, as well as any major change to Liquid, Gaseous, or Solid Radwaste Treatment Systems. It shall also include a listing of new locations for dose calculations and/or environmental monitoring identified by the Land Use Census pursuant to LCO 6.12.2.

• In lieu of submission with the Radioactive Effluent Release Report, the licensee has the option of retaining this ousmary of required meterological data ensite in a file that shall be provided to the NRC on request.

GRAND GULF, UNIT 1 A-10 Revision 17 - 03/95 2

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! s.s.3 Annu t omnicacfivs nFFffErf Pat wun nasony (Continued) a The Radioactive Effluent Release Report shall also include the following: an i explanation as to why the inoperability of liquid or gaseous effluent monitoring j

instrumentation was not corrected within the time specified in LCOs 6.3.9 or 4 6.3.10, and description of the events leading to liquid holdup tanks exceeding the limits of Technical Specification 5.5.8.b.

J 1 j b. Major changes to the Radioactive vaste Treatment System (liquid, gaseous and I solid") shall be reported to the Commission in the Annual Radioactive Effluent l t

Release Report for the period in which the evaluation was reviewed by the PSRC.

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2 (1) A summary of the evaluation that led to the determination that the change

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could be made in accordance with 10 CFR 50.59 I E

i (2) sufficient detailed information to totally support the reason for the change l i

without benefit of additional or supplemental intformations l i

l (3) A detailed description of the equipment, ce=Panants and processed involved I and the interf aces with other plant systems; (4) An evaluation of the change which shows the predicted releases of radioactive materials in liquid and gaseous effluents and/or quantity of i solid waste that differ from those previously predicted in the license '

j application and ===a h ats thereto;

=a=4== exposures to l (5) An evaluation of the change which shove the expected MERSERS OF THE PUBLIC in the UNRESTRICTED ARIA and to the general population

{

' that differ from those previously estimated in the license application and

==aad==ats thereto; j.

! (6) A comparison of the predicted releases of radioactive materials, in liquid j

and gaseous effluents and in solid waste, to the actual releases for the i period before when the changes are to be meds; t

(7) An estimate of the.axposure to plant operating personzel as a result ol' the

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j change; and i

j (8) Documentation of the fact that the change was reviewed and found acceptable 4 by the PSPC.

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" The information called for in this Specification may be submitted as part of the j next UFSAR update.

GRAND GULF, UNIT 1 A-11 Revision 17 - 03/95 4

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I SECTICH 6.O L M ING CONDITION 3 FOR OPERATION l AMD SURVIIZ1ANCE RaggI m l

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l 6.3 INSTRt3EEFTATION 6.3.9 RADICACTIVE LIQUID EFFLUENT MONI'ICRING INSTRUMENTATION LCO 6.3.9 The radioactive liquid effluent monitoring instrumentation channels shown in Table 6.3.9-1 shall be OPERABLE with their alarm / trip setpoints set to ensure that the limits of LCO 6.11.1 are not exceeded. 'nte alarm / trip setpoints of these channels shall be determined in accordance with the OFFSITE DOSE CALCULATION MANUAL l (ODC31) .

APPLICABILITI: At all times.

l ACTIONS

' ...........................................myrgg......................................

1. Separate Condition entry is allowed for each Channel.

2. The provisicas of ICO 3.0.3 are not applicable.

l i CCBIPLETION TIES CONDITION REQUIRED ACTION l

A.1 Suspend release of Immediately A. One or more required channels inoperable. radiactive effluent via affacted pathway.

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Once required Action A.2 is entered the Completion Time ,

for Condition 5 or C can not be restarted by reentering Required Action A.1.

A.2 Enter the Condition Imediately referenced in Table 6.3.9 1 for the channel.

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A.13 Revisica 17 03/95 GRAND GULF, UNIT 1

ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME

5. As required by Required 5.1 At least two independent Prior to each easeles are analysed in release, Action A.2 and referenced in Table 6.3.9 1. accordance with LCO 6.11.1.

M B.2 At least two technically Prior to each l qualified members of the release.  :

Facility Staff l' independently verify the release rate calculations and discharge path valve line-up. J M

B.3 Restore channel to 14 days operable.

C. As required by Required C.1 Estimate the flow rate for Once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> Action A.2 and referenced the affected pathway during in Table 6.3.9-1. actual releases. Puup curves may be used to estimate flow.

M C.2 Restore channel to 30 days operable.

D. Required Action and D.1 Suspend release of Zamediately associated Completion Time radiactive effluent via of Condition 3 or C not affected pathway.

met.

D.2 Initiate action to esplain Immediately why this inoperability was j not corrected in a timely l manner in the next Annual

• l Radioactive Iffluent Release Report.

GRAND GULF, UNIT 1 A.14 Revision 17 03/95

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SURVEILLANCE REQUIRE 3EElfrS

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l j Refer to Table 6.3.9 1 to determine which SRs apply to each channel, t ......................................................................................

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SURVEILLANCE FREQUENCY d

.....--...-..-..-..IR7FE.-----. - ----.-......

i i SR 6.3.9.1 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> j For flow rate measurement devices a CHANNEL CHECK {

l shall consist of verifying indication of flow j

during periods of rolsase. A CHANNEL CHECK shall be made at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> on days which

! batch releases are made. ,

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1 Perform CHAIIIIEL CHECK.

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Perform a source check, a qualitative assessment Prior to each f f SR 6.3.9.2 of chmanal response when the channel sensor is release.

j exposed to a radioactive source.

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The CHAINEEL FUNCTICIEAL TEST sha.11 also demonstrate 92 days

, that automatic isolation of this pathway and j

control room alarm maanneistion occur if any of the following conditions exists:

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1. Instrument indicates measured levels above the l alare/ trip setpoint. 1

2. Circuit failure.

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3. Instrument indicates a downscale failure.

4 8 4. Instrument controle not set in operate mode.

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Perform CHANNEL FUNCTICIEAL TEST.

1 (continued)

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GRAIED G'JLF, UNIT 1 A-15 Revision 17 - 03/95 i

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SURVIILIANCE FREQUINCY SR 6.3.9.4 Perform CHANNEL FONCTIONAL TEST. 92 days SR 6.3.9.5 ... -.*................N0TE.......................

The initial CHANNEL CALIBRATION shall be performed 12 scnths using one or more of the reference standards certified by the National Institute of Standards i I

and Technology (NIST) or using standards that have been obtained frost suppliers that participate in measurement assurance activities with NIST. These standards shall permit calibrating the eyetest 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.

Perform a CHANNEL CALIBRATION.

Perform a CHANNEL CALIBRATION 18 months SR 6.3.9.6 I

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GRAND GULF, UNIT 1 A.16 Revision 17 03/95

TABLE 6.3.9-1 j

RADIO 3CTIVE LIOUID EFFf 2mr amaEI10RIIIG INSTm=*rrATION CONDITIOIES REFEREIOCED MINIIEnt PRON Cd35 EELS REQUIRED SURVEILLANCE OPERAB12 ACTIObl A.1 REQUIRE M IMRTEREmarr

1. GROSS RADIOACTIVITY ROSEITORS PROVIDIt0G ALA5108 ABID NTIC TBattIIIATIOgl OF RELEASE 1 B 6.3.9.1

a. Liquid Radweste Effluent Line 6.3.9.2 6.3.9.5 6.3.9.3

2. FIDet RATE REASman-r DEVICES 1 C 6.3.9.1

s. Liquid Radweste Effluent Line 6.3.9.6 6.3.9.4 1 C 6.3.9.1

b. Discharge Canal or Circulating Water Blowdown 6.3.9.6 ,

6.3.9.4 s

• t GRAse GULF, UltIT 1 A-17 Revision 17 - 03/95

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6.3 INSTRUMIFTATION l

l 6.3.10 RADICACTIVE GASEOUS IFFLUENT NONITORING INSTRUMENTATION 4

i LCO 6.3.10 The radioactive gaseous effluent monitoring instrumentation channels shown in Table 6.3.10 1 shall be OPERABLE with their alarm / trip setpoints set to ensure that the limits of LCO 6.11.4 are not l

4 exceeded. The alarm / trip setpoints of these channels shall be i determined in accordance with the OFFSITE DOSE CALCtHATION MANUAL (ODCM).

d T

, APPLICABILITY: As shown in Table 6.3.10 1 ,

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ACTICNS

...........................................NgtEs...................................... f i 1. Separate Condition entry is allowed for each Channel. l I

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2. The provisions of Specification 3.0.3 and 3.0.4 are not applicable. l

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CONDITION REQUIRED ACTION COMPLETION. TIME I

t A. One or more required A.1 Suspend release of Immediately '

channels inoperable, radiactive effluent via

- affected pathway.

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Once required Action A.2 is i entered the Completion Time 1 for condition Referenced on '

}

Table 6.3.10 1 can not be

' restarted by reentering Required Acticut A.1.

A.3 Enter the Condition Immediately referenced in Table 6.3.10 1 for the channel.

(continued)

GRAND GULF, UNIT 1 A.18 Revision 17 - 03/95

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I ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME i B. As required by Required 8.1 Take grab saagles during Once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> Action A.2 and referenced release.

in Table 6.3.10 1.

M B.2 Analyse the above required within 24 heure of a samples for gross taking the easple i activity.

M 30 days

3.3 Restore channel to 1 operable.

C. As required by Required C.1 Eetablish an alternate Immediately Action A.2 and referenced reans to collect samples in Table 6.3.10-1. required by Table 6.11.4-1.

M C.2 Restore channel to 30 days operable.

D. As required by Required D.1 Estimate flow rate. Once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> Action A.2 and referenced in Table 6.3.10 1. M D.2 Restore channel to 30 days operable.

(continued)

GRAND GUI.F, UNIT 1 A.19 Revision 17 - 03/95 a

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l ACTIONS (continued)

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CONDITION REQUIRED ACTION COMPI.ETION TIME 1

E. As required by Required E.1 Place the inoperable 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />

! channel in downscale trip.

j Action A.2 and referenced

in Table 6.3.10 1.

E

. . . . . . . . . . . . . . . myrE . . . . . . . . . . . .

With both required monitors 1 inoperable take Required Actions E.2.

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E.2.1 Take grab sasqples during Once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> release.

M I.2.2 Analyse the above Within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of required samples for taking the sample gross activity.

! M E.2.3 Restore channel to 30 days operable.

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. F. As required by Required F.1 Verify the offgas system is Issmediately i Action A.2 and referenced not bypassed, except for in Table 6.3.10 1. filtration system bypass j

during plant startups.

! F.2 Verify by administrative Issmediately i means that the offgas post.

j treatment monitoring system

• is operable.

l F.3 Restore channel to 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> operable.

(continued)

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GRAND GULF, UNIT 1 A.20 Revision 17 03/95 i

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ACTIONS (continued)

REQUI m M I N CMMIM M

, CONDITION i

G. As required by Required G.1 Take grab esegles during Once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> Action A.2 and referenced release.

in Table 6.3.10-1.

M 4

i G.2 Analyse the above required Within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of seeples for gross taking the sample l

4 activity.

i M 20 daye G.3 Restore channel to operable.

i Required Actions and H.1 Suspend release of Inunediately H.

J associated Completion radiactive effluent via Times of Condition B,C,D,I this pathway.

! or G not met.

E f

H.2 Initiate action to amplain Immediately why this inoperability was not corrected in a timely menner in the next Annual Radioactive Iffluent Release Report.

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I. Required Action and I.1 Be in 2005 3 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> 4

associated Completion Time

! of Condition F not met. M i

1.2 Be in RCDE 4 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> I

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GRAND GUI.F, UNIT 1 A-21 Revision 17 03/95 i

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

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j SURVIILIANCE REQUIREME3FFS i .

--- -- ==- -- * - ............

l ........................................ NOFES -*

} 1. Refer to Table 6.3.10 1 to determine which SRs apply to each chann61.

J

2. When a monitor is placed in an inoperable status solely for performance of

, required Surveillance's, entry into associated Conditions and Required Actions in

accordance with LCO 6.3.10 may be delayed for up to 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.

i i

4 , SURVIILIANCE FREQUENCY i SR 6.3.10.1 Perform CHAaGrEL CHECK. 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> 1

5

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! SR 6.3.10.2 Perform CHANNEL CHECK. 7 days

}

2 j SR 6.3.10.3 ---- ---------- --- -NUFB--------- ---- -- --- -

1 l

1. Not required to be performed in IE3 DES 1 and 2 1

for the offgas pre treatment monitor if 4 inaccessibile due to a high radiation area.

i

. 2. Not required to be performed for the offgas

pretreatment monitor when entering IE3 DIS 3 and 4

from 3C053 1 or 2 until 8 hocre after entering i - 3005 3 or 4 if monitor was inaccessible due to a

! high radiation area. l l

t Perform SOURCE CHECK , a qualitative assessment of i channel response when the channel sensor is 31 days i exposed to a radioactive source.

4 A

! -- --------------- ----NUTI.- -- ---- ------------

SR 6.3.10.4 i The CHAIDfEL FUNCTICIEL TEST shall also demonstrate 4 the automatic isolation capability of the i instrumentation for this pathway and the control j room alarm annunciation capability, if any of the

following conditions exists:

i

1. Instrusent indicates measured levels abog the alarm / trip setpoint, j 2. Circuit failure.

4 j 3. Instrusent indicates a downscale failure.

t

! 4. Instrument controls not set in operate mode. -

l 92 days a Perform CHAISIEL FUNCTIONRL TEST.

1 (continued) 3 4

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i f GRAND GULF, UNIT 1 A.22 Revision 17 - 03/95 4

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SURVIILIANCE REQUIPWS (continued) .

SURVIILIANCE FREQUENCY SR 6.3.10.5 ------.---------NCPTB------.--------

The CHANNEL FUNCTIONAL TEST shall also desenstrate that control room alarm annunciation occur if any of the following conditions exists:

1. Instrument indicates measured levels above the alare/ trip setpoint.

2. Circuit failure.

l

3. Instrument indicates a downscale failure.

4. Instrument controla not set in operate mode.

92 days Perform CHANNEL FUNCTIONAL TEST.

SR 6.3.10.6 ---.------.-----.NCFFE----..------...---

Compare the measured flow rate to the espected design flow rate for existing plant conditions. l Perform CHANNEL FUNCTIONAL TEST.

92 days I

SR 6.3.10.7 ---..........--........N0TR-.............---..---.

1. '!he initial CHANNEL canan w!ON shall be performed using one or more of the reference standards certified by the National Institute of Standards and Technology (NIET) or using standards that have been obtained from suppliers that participate in measurement assurance activities ,

with NIST. These standards shall permit calibrating the system over its intended range of energy and measurement range. For subsequent CHANNEL CALIBRATICW, sources that have been related to the initial calibration shall be used.

2. The offgas pre treatment and offgas post-treatment sensors will be calibrated for ar/hr or cps irom the calibration standard. The conversion to release rate will be performed during subsequent unit operation, but within one week.

Perform a CHANNEL CALIBRATION. 12 months SR 6.3.10.8 Perfarm a CHANNEL CALIBRATION 18 eenthe GRAND GULF, UNIT 1 A.23 Revision 17 - 03/95

TABLE 6.3.10-1 r RADIQAcrIVE GASROUS EFFL2 EM IONI*IDEi1NG INSTRIBGEtrTATION i

CONDITIONS .

REFERENCED FROM MINIBRAE CHARWIELS REQUIRED SURVEILLANCE l OP"" " " APPLICABILITY AcrIOtt A.2 REQUIRERENFS INSTIIEEENT l

1. RADetASTE BUIIDIIeG VENTILATIOtt i IOIIITORIIeG SYSTERE .

a. Noble Gas Activity tecnitor 6.3.10.1 Providing Alarm 1 la) B 7 6.3.10.3 6.3.10.5  !

r 6.3.10.7 1 fa) C 6.3.10.2

b. Iodine Sampler 1 la) C 6.3.10.2

c. Particulate Sampler

d. Effluent System Flow Rate 6.3.10.1 Measuring Device 1 fa) D 6.3.10.6 6.3.10.8 i 1 (a) D 6.3.10.1

e. Sampler Flow Rate IIsasuring Device 6.3.10.8 i

2. COtrTAIIREIrf VEttrIIATIOtt IOGIITORIIGG j SYSTEtt  !

a. Isoble Gas Activity geonitor 6.3.10.1 i Providing Alarm 1 (a) B 6.3.10.3 6.3.10.5 6.3.10.7 t s e g.2, Revision 17 - 03/95 o W, UNI'r 1

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TABLE 6.3.10-1 (Continued)

RADIOACTIV(GASEOUS EFFrimarr 3ONI"f0 RING INSTRIBEElfrATION CONDITIONS REFERENCED FROM MINIDEst CHANNELS REQUIRED SURVEILIANCE OPenmaLE APPLICABILITY ACTION A.2 REOUIRE M INST m 1 (a) C 6.3.10.2 .

b. Iodine Sampler 1 (a) C 6.3.10.2

c. Particulate Segler 1 (a) D 6.3.10.1

d. Effluent System Flow Rate 6.3.10.6 30easuring Device 6.3.10.8 1 (a) D 6.3.10.1

e. Sampler Flow Rate 6.3.10.8

.sesseuring Device

3. 1URBINE BIEG. VEarrIIATIOIE BOMITORING SYSTEbf 1 (a) B 6.3.10.1

a. Noble Gas Activity 6.3.10.3 Providing Alarm 6.3.10.5 6.3.10.7 1 (a) C 6.3.10.2

b. Iodine Sampler 1 (a) C 6.3.10.2

c. Particulate Sampler l 1 (a) D 6.3.10.1

d. Efflutnt System Flow Rate 6.3.10.6 30easuring Device 6.3.10.8 1 (a) D 6.3.10.1

e. Sampler Flow Rate 6.3.10.8 IIsamuring Device A-25 Revision 17 - 03/95 GRAND GULF, UNIT 1

TABLE 6.3.10-1 (Continued)

RADIQACTIVE GASEOUS EFFU_1EMT BK)NI'KMtING INSTRtBEENTATION COtO1TIONS REFERENCED FROM MINIDEBt CHA35ELS REQUIRED SURVEILIJueCE ,

OPERAB12 APPLICABILI?"1 /fTIOtt A.2 REQUIREMENTS IN

4. FUBL HAIOLIBOG AREA VElfrILkTIOtt K)MI'IORING SYSTEM Isoble Gas Activity 1 (al B 6.3.10.A

a. 6.3.10.3 Providing Alarm 6.3.10.5  !

6.3.10.7 1 (a) C 6.3.10.2

b. Iodine Sampler 1 (a) C 6.3.10.2

c. Particulate Sampler 1 (a) D 6.3.10.1

d. Effluent Flow Rate 6.3.10.6 Itoasuring Device 6.3.10.8 I

1 (a) D 6.3.10.1

e. Sampler Flow Rate 6.3.10.8 temasuring Device

5. OFFGAS PRS-TREA'11ENT taOttI'!OR 1 (c) F 6.3.10.1

a. Bloble Gas Activity teonitor 6.3.10.3 ,

Providing Alarm 6.3.10.5 ,

6.3.10.7 i

l A-26 Revision 17 - 03/95 GRAlm GULF, UNIT 1

TABLE 6.3.10-1 (Continueg itADIQAcrIVE ca_c_EMJS EFFr_i_mmrr geog 4ITORING INSTRlREENTATION CONDITIONS REFERENCED FROM i

MINIDERE CHAISEELS REQUIRED SURVEILIANCE Im OPERABIE MPLICABILITY ACTION A.2 REQUIREMartS I

6. OFFGAS POST-TREAMBrr BK)tEITOR

a. Moble Gas Activity Itonitor Providing l Alarm and Automatic Termination of Release 2 (b) E 6.3.10.1 6.3.10.3 6.3.10.4 6.3.10.7

7. STAND 8Y GAS TREAMarr EXHAUST BOIIITORIIIG SYSTEtt (Adal

a. Isoble Gas Activity teonitor 1/ system (al G 6.3.10.1 6.3.10.3 Provding Alarm 6.3.10.5 6.3.10.7 GRAas GULF, UNIT 1 A-27 Revision 17 - 03/95

1 1

1 TsuntJ g.3.16 1 (carit 4 miad) l RADIMTVE CARIOUS EFFffENT - =liGLTiet2 i Wi r-i -- 1 ATION i

TABLE M7FATION (a) At all times.

(b) During main condenser offgas treatment system operation. i (c) When any steam jet air ejector (SJAI) is in operation.

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e GRAND GULF, UNIT 1 A.28 Revision 17 03/95

6.11 RADIOACTIVE IFFLUIartS 6.11.1 LIQUID EFFLUENTS CONCE2rrRATION Lc0 6.11.1 The concentration of radioactive material released in liquid ef fluents to UNRESTRICTED ARIAS shall be limited to ten times the effluent concentrations specified in 10 CFR Part 20, Appendix 3, l Table 2, 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*4 microcuries/ml total activity.

APPLICABILI'IY: At all times.

ACTIONS CONDITION REQUIRED ACTICN CCMPLETION,, TIME A. The concentration of A.1 Restore the concentration. Issmediately radioactive material to within the abcve limits, released in liquid effluents to UNRESTRICIED &E AREAS exceeds the above limits. A.2 Declare the liquid effluent waste treatment systest ia e rable.

GRAND GULF, UNIT 1 A.29 Revision 17 - 03/95

4 l

SURVII11AalCE REQUIRE 3EEIrrS seRVIILLAllCE FREQUENCY l

SR 6.11.1.1 The radioactivity content of each batch of Per (ODG)

I radioactive liquid waste shall be determined Table 6.11.1 1.

before release by sampling and analysis in accord-ance with (ODCIE) Table 6.11.1-1.

SR 6.11.1.2 Post release analyses of samples ccamposited front Per (CDCM) i batch releases shall be perfonsed in accordance Table 6.11.1 1.

with (ODCSE) Table 6.11.1 1.

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t GRARED GULF, UNIT 1 A 30 Revisica 17 .03/95

(

l Tamf.m g,11,1 1 I manin1M TVE t.I NID wants *===ftm *=n *==fYsis pannumw 1 Minianan Type of Lower Limit Liquid Release Sangling Analysis Activity of Detection Type Frequency Frequency Analysis (LLD)

(gCi/al) (a)

A. Batch Waste Prior to Prior to Principal Gamma 5x10*7 Release Release Release Emitters (d)

Tanks (c) Each Batch Rach Batch I 131 1x10-6 j Prior to 31 days Dissolved and 1x10 5 j Release Entrained Gases  ;

one Batch /M (Gamma emitters) i Prior to 31 days M3 1x10-5 Release composite (b)

Each Batch Gross Alpha 1x10 7 Prior to 92 days Sr 89, Sr-90 5x10*8 Release Composite (b)

Each Batch Fe 55 1x10 6

5. SSW Basin Prior to Prior to Principal Gamma 5x10*7 (before Release Release Raitters (d) blowdown) Each Iach Batch Blowdown I 131 1x10*8 l

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GRAND GULF, UNIT 1 A 31 Revision 17 - 03/95

Tint.m g .11.1 1 (cant 4nuAdi RADIMIVE LIOUID WASTE emeLYNG AND _1Mif.YSIS PROGRAM TAgLE NOTATION

a. The LLD is the smallest concentration of radioactive material in a sample that will yteld a not count (above system background) that will be detected with 95%

probability with only 5% probability of falsely concluding that a blank observation represents a "real" signal.

For a particular measurement system (which may include radiochemical separation):

4.66 ab LLD =

I

• V e 2.22 x 106 . y ,,p ( agg) where LLD is the 'a priori

• lower limit of detection as defined above (as gCi per unit mass or volume) . (Current literature defines the LLD as the  !

detection capability for the instrumentation only, and the MDC, minisaan detectable concentration, as the detection capability for a given instrument, procedure, and type of semple.)

sb is the standard deviation of the background counting rate or of the f i counting race of a blank sample as appropriate (as counts per minute)

I E is the counting efficiency (as counts per disintegration) v is the sample sine (in units of mass or volume) 2.22 x 106 is the number of disintegrations per minute per microcurie l

Y is the fractional radiochastical yield (when applicable)

A is the radioactive decay constant for the particular radionuclide at is the elapsed time between sample collection (or and of the sample collection period) sad time of' counting The value of ab used in the calculation of the LLD for a particular measurement 4

system should be based on the actual observed variance of the background counting l rate or of the counting rate of the blank semples (as appropriate) rather than on an unverified theoretically predicated variance.

i Typical values of I, V, Y and At should be used in the calculation.

It should be recognised that the LLD is defined as an a griggi (before the fact) limit representing r.he capability of a measurement system and not as a costeriori

[ (after the fact) limit for a particular measurement.

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GRAND GULF, UNIT 1 A-32 Revision 17 03/9!

p l

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

}

l b .

TABLE 6.11.1 1 (C e tinuad)

RADICAf"fTVE LIOtfID WASTE *__W8tTIE AND WitYSIS PRM82 4

Tint 2 10CYPATION (C etinued)

) b. A composite sasple is one in which the quantity of liquid sangled is proportional 1 to the quantity of liquid waste discharged and in which the method of sangling espicyed results in a specimen which is representative of the liquids released.

i

]

c. A batch release is the discharge of liquid wastes of a discrete voluse. Before 1 4

sasipling for analyses, each batch shall be isolated, and then thoroughly mixed to assure representative sampling. .

1

d. The principal genusa emitters for which the LLD specification applies exclusively are the following radionuclides: 1k1-54, Fe-59, Co 58, Co 60, Zn-65, Mo 99, Cs.

134, Cs 137, Co-141, and Co 144. This list does not mean that only these nuclides are to be detected and reported. Other peaks which are measurable and identifiable, together with the above nuclides, shall also be identified and reported.

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G11AIID GULF, UNIT 1 A 33 Revision 17 03/95

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4 6.11 RADICACTIVE EFFLUI3rrS 4

6.11.2 LIQUID IFFUENT DOSE 1 I i LCO 6.11.2 The dose or dose commaitment to a MEMBER OF THE PUBLIC from radioactive materials in liquid effluents released to UNRESTRICTED l ARIAS shall be j i i a

a. 5 1.5 area to the total body and 5 5 ares to any organ, during

any calendar quarter, and i

b. 5 3 ares to the total body and 5 10 ares to any organ, during any calendar year.

APPLICABILITY

At all times.

ACTIONS l

...........................................ptyrI3.......................................

1. The provisions of Specification 3.0.3 are not applicable.

i 2. Separate condition entry is allowed for each of the above limits.

CONDITIQB REQUIRED ACTION CGIPLETION TIME i l A. The calculated dose from A.1 Initiate action to prepare Isradiately i

che release of radioactive and submit a special Report materials in liquid within 30 days. ,

effluents greater than any of the above limits. 43 A.2 Declare the liquid effuent waste treatment system inoperable.

(continued) 9 GRAND GULF, UNIT 1 A 34 Revision 17 03/95 a

Immediately B. The calculated doses from B.1 Initiate action to the release of radioactive calculate the direct materials in liquid radiation contributions affluents greater than from the reactor unit and from outside storage tanks twice any of the above limits. to determine whether the total annual dose or dose comunitment to any usassa CF THE FUBLIC greater than:

a) 25 arem to the total body or any organ, except the thyroid.

91 b) 75 ares to the thyroid.

scavsILuNCE F3_ innumrrs FREQUENCY SURVEILLANCE Cumulative dose contributions from liquid 31 days SR 6.11.2.1 effluents for the current calendar quarter and the current calendar year shall be detemined in accordance with the methodology and parameters of the 00m.

4 4 A 35 Revision 17 03/95 03 Amp acLF, UNIT 1

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

)

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6.11 RADICACTIVE IFFLUEartS 6.11.3 LIQUID EFFLUElff WASTE TREATMElff Lc0 6.11.3 The liquid radwaste system shall be used to reduce the radioactive materials in liquid wastes before their discharge when the projected doses due to the liquid affluent to UNRESTRICTED ARIAS would be >

0.06 arem to the total body or > 0.2 arem to any organ, in a 31. day period.

APPLICARILITY: At all times.

ACTIONS

...........................................yecrrES.......................................

The provisions of Specification 3.0.3 are not applicable.

CONDITIOIE RNQUIRED ACTION CCBIPLETION TIME A.1 Initiate action to prepare Immediately A. Radioactive liquid waste being discharged without and submit, a Special treatment and ire excess of Report within 30 days.

the above limits.

SURVIILLANCE REQUIREMEIFFS _

SURVEILLANCE FREQUENCY SR 6.11.3.1 Doses due to liquid releases to UIERESTRICTED AREAS 31 days shall be projected in accordance with methodology and parameters in the ODCM.

hE .

.......................Nort..... .... ..- .....-.

Not required to be met when the projected dose less than or equal to the above limit.

Verify the liquid effluent waste treatment system is being used to reduce radioactive materials before discharge.

E t

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! GRA3tD GULF, UNIT 1 A.36 Revision 17 03/95 l

I 6.11 RADIOACTIVE EFFLUE3rfS 6.11.4 GASEOUS IFFLUI3rts DOSE RATE LCO 6.11.4 The dose rate due to radioactive materials released in gaseous effluents from the site to areas at and beyond the SITI SOUNDARY shall be:

a. For noble gases: 5 500 ares /yr to the total body and 5 3000 mres/yr to the skin, and

b. For all iodine 131, iodine 133, tritium and all radionuclides in particulate form with half lives greater than 8 days: 5 1500 mres/yr to any organ.

APPLICJ3ILITY: At all times.

ACTIONS CONDITION REQUIRED ACTION Ct3EPLETION TIME Dose rate exceeding the A.1 Decrease the release rate Immediately A.

above limits. to within the above limit (s).

&E1 A.2 Declare the ventilation exhaust treatment system inoperable.

I oRAmD aGLr, UNIT 1 A 27 **'i**** 17 - "'

SURVEILLANCE REQUIREMENTS SURVIILLANCE FREQUENCY

'Ihe dose rate due to noble gases in gaseous Per (CDCM)

SR 6.11.4.1 effluents shall be determined to be within the Table 6.11.4 1.

above limits by obtaining representative sangles and performing analyses in accordance with (CDCM) Table 6.11.4 1.

l l

The dose rate due to iodine 131, iodine 133, Per (CDCM)

SR 6.11.4.2 tritium and to radionuclides in particulate form Table 5.11.4 1.

with half 12.ves greater than 8 days in gaseous efflusuts shall be determined to be within the above limits by c.btaining representative samples and performing analyses in accordance with (CDCM) Table 6.11.4-1.

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GRAND GULF, UNIT 1 A 38 Revision 17 - 03/95

_ _ . . . _ . . . _ _ _ _ . _ .. .__.m._. . _ _ . . . . _ . _ . . . . _ _ _ _ _ _ . _ - - . _ _ _ . . _ _ _ - . . . - - _ _ _ __ _ _ _ . . . _ .

1 4

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J Taaf_m g.11.4-1 RADIQACTIVE GASEOUS WASTE emeLING AND 1mYSIS PRcr1 RAM i

Minimum Type of Lower Liste Sasgling Analysis Activity of Detection Gaseous Release (LLD)

• Frequency Frequency Analysis 3 Type (sci /ml) (a) a 31 days 31 days Principal Gasuna 1x10*4 i A. (1) Radwaste Emittere(b,e) l Building Grab Sample (f) j Ventilation Exhaust H3 1x10 6

[

1 1

(2) Fuel Handling Continuous (d) 7 days (c) I-131 1x10-12 j

3 Area Ventila- (f) Charcoal Sample I 133 1x10 10 l tion Exhause 1

I Continuous (d) 7 days (c) Principal Gamma 1x10*11 (3) Containment Ventilation (f) Particulate Emitters (e)

Sample (I-131, Others)

Exhaust (4) Turbine Continuous (d) 31 days Gross Alpha 1x10*ll Building (f) Composite Ventilatica Particulate Exhaust Sample Continuous (d) 92 days Sr-89, Sr 90 1x10*11 (f) Composite Particulate Sample l l

Continuous (f) Noble Gas- Noble Gases 1x10-6 Monitor Gross seta i or Gasma l 31 days 31 days Principal Gamma 1x10*4 B. (1) Offgas Pest Treatment Grab Sample (f) Emitters (e)

Exhaust, whenever .

there is flow (2) Standby Gas Treatment A Exhaust, whenever there is flow (3) Standby Gas Treatment B Exhaust, whenever there is flow See " Table Notation" which follows. ,

GRAND GULF, UNIT 1 A 39 . Revision 17 - 03/95

_.__.._ . _ _ ...__ . _ _ . _ _ . _ _ . . _ . _ _ _ . . . - _ . - _ - . _ . . . _ _ . . - . . _ __m _ _ _ _

Tant m 6.11.4 1 (cantinued)

RAntoAcTIva casacas WASTE emof.Tled AND m tYSIs PROGRAM TABLE NOTATION

a. The LLD is the smallest concentration of radioactive material in a sample that l will yield a not count (above system background) that will be detected with 95% .

probability with only 5% probability of falsely concluding that a blank f observation represents a 'real" signal.

For a particular measurement system (which may include radiochemical separation) :

4.56 sb l i LLD =

j Iev* 2.22 x 10'

• Y

• emp ( Lit) where LLD is the 'a prioria lower limit of detection as defined above (as gCi per unit mass or volm e). (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.)

is the standard deviation of the background counting rate or of the ab counting rate of a blank sample as appropriate (as counts per minute)

I is the counting efficiency (as counts per disintegratica) l l

V is the sample sise (in units of mass or volume) 2,22 x 106 is the number of disintegrations per minute per microcurie Y is the fractional radiochemical yield (when applicable) 1 A is the radioactive decay constant for the particular l l

radionuclide At is the elapsed time between sample collection (or and of the sample l

collection period) and time of counting The value of ob used in the calculation of the LLD for a particular measurement i

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 I, V, Y and At should be used in the calculation.

l It sh:.mid be recognised that the LLD is defined as an a 3g13g1 (before the fact)

. . limit representing the capability of a measurement system and not as a nosteriori

! (after the fact) limit for a particular measurement.

h GRAND GULF, UNIT 1 A 40 Ret!sica 17 03/95

i~

i B

TAaLE 6.11.4-1 (cane 4 m=d)

RADI&un niemmS WARTE **=f.TMG AltD ""YSIB Pamsaw TABLE NOTATIQW (Continued)

b. Analyses shall also be performed following startup from cold shutdown, or a THERKE POWER change exceeding 15 percent of the RATED THERMhL power within a one hour period. This requirement does not apply if:

(1) routine analysis required by the Surveillance Requirements of LCO 3.4.8 shows that the DOSE EQUIVALENT I 131 concentration in the primary coolant has not increased more than a factor of 3; and l

(2) the noble gas monitor shows that effluent 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 l' within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> after changing or after removal from sempler. Sampling and analyses shall be performed at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> for at least 7 days following each shutdown. startup or 'HEREIIRL POWER change enceeding 15 percent of ,

I RATED THERIEE POWER in one hour. When segles collected for 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> are This analysed, the corresponding LID's may be increased by a factor of 10.

requirement does not apply if: l (1) routine analysis required by the Surveillance Requirements of LCO l 3.4.8 shove that the DOSE EQUIVALENT I 131 concentration in the primary coolant has not increased more than a factor of 3; and (2) the noble gas monitor eowe that effluent activity has not increased more than a factor of 3. I

d. The ratio of the sample flow rate to the sampled str*w flow rate shall be known for the time period covered by each dose or dose rats M culation made in accordance with LCOs 6.11.4 and 6.11.6.

e. The principal gamma emitters for which the LLD specification applies exclusively are the following radienuclides: Kr 87, Kr 88, Ze 133, Ze 133m, Ze 135, and Ze-138 for gaseous emissions and Ik 54, Fe 59, Co 58, Co 60, 2n-65, 300-99, Cs 134, Cs 137, Co 141 and Co 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 identifiable, together with the above nuclides, shall also be identified and reported,

f. When a monitor is placed in an inoperable status solely for performance of required Surveillance's, entry into associated conditions and Required Actions in i

accordance witit LCO 6.3.10 may be delayed for up to 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.

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GRAIID GULF, UNIT 1 A-41 Revision 17 - 03/95

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

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l 6.11 RADICAC" RIVE EFFLUENTS 6.11.5 GASEOUS EFFLUBIrr DOSE NOBLE GASIS i'

LCO 6.11.5 The air dose due to noble gases released in gasecue effluents, from

• the site to areas at and beyond the SITE BOUNDARY shall be:

I

a. 5 5 mrad for gasuna radiation and 5 10 mrad for beta radiation,during any calendar quarter and l i

b. 510 arad for gasuna radiation and 5 20 mrad for beta radiation i during any calendar year.

{ APPLICABILITY: At all times. l i

l I ACTIONS

\

1 ...........................................ngrE3.......................................

l 1. The provisions of Specification 3.0.3 are not applicable. ,

1

2. Separate condition entry is allowed for each of the above limits.

a l

1 CONDITION REQUIRED ACTIM C NPLETION TIME l i  !

i k

A.1 Initiate action to prepare Ismediately j A. The calculated air dose

from the radioactive noble and autunit, a Special 4 gases in gaseous effluents Report within 30 days. l I greater than any of the l above limits. Agt i

$ A.2 Declare the ventilation exhaust treatment system i

inoperable. 1

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(Continued) l 1

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i GRAND GULF, UNIT 1 A.42 Revision 17 - 03/95 9

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Irmediately i

5. The calculated doses from 5.1 Initiate action to 7

calculate the direct j the release of radioactive materials in gaseous radiation contributions affluents greater than from the reactor unit and ,

twice any of the above from outside storage tanks limits. to determine whether the *-

total annual dose or dose ccumitment to any MERSER OF THE DOBLIC greater thans a) 25 ares to the total body or any organ, except the thyroid.

QR b) 75 mrom to the thyroid. ,

SURVII" "CI 89 -_C -L SURVIILLANCE FREQUENCY Cumulative dose centributions for noble gases for 31 days SR 5.11.5.1 the current calendar quarter and current calendar year shall be determined in accordance with the methodology and parameters in the CDQt. _

i GRAND GULF, UNIT 1 A-43 Revision 17 - 03/95 W

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6.11 RADICACTIVE IFFLUENTS 6.11.6 GA35003 IFFLUIErr DOSI . IODINE.131, IODINE.133, TRITIUM AND RADIONUCLIDES IN PARTICUIATE FOIOi LCO 6.11.6 The dose to a MERSER OF 'IMI FUBLIC from iodine.131, iodine.133, tritium and radionuclides in particulate form with half lives greater than a daye in gaseous effluents released, from the site to areas at and beyond the SITE BOUNDARY shall be:

a. 5 7.5 mrom to any organ during any calendar quarter, and

b. 5 15 area to any organ during any calendar year.

APPLICABILITY: At all times.

ACTICNS

.......................................... 3pprIS.......................................

1. The provisicas of Specification 3.0.3 are not applicable.

2. Separate Condition entry is allowed for each of the above limits.

REQUIRED ACTICII CCalFLETION TIME CoalDITION A.1 Initiate action to prepare Ismediately A. The calculated dose frcus and submit, a Epocial the release of iodine.131, iodine 133, tritius and Report within 30 days, radionuclides in particulate form, with Agt half. lives greater than 8 days, in gaseous effluents A.2 Declare the ventilation greater than any of the exhaust treatment system above limits. inoperable.

(continued)

GRAIED GULF, UNIT 1 A.44 Revision 17 03/95

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2 s

N i

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4 4

e B.1 Initiate action to Ismediately

} B. The calculated doses from the release of radioactive calculate the direct i

materials in gaseous radiation contributions r

l effluents greater than front the reactor unit and twice any of the above frcui outside storage tanks

! limits. to determine whether the i

total annual dose or dose '

coensitment to any MEISER OF j THE FUBLIC greater than:

J

!. a) 25 arem to the total j body or any organ,

except the thyroid.

j

! QR I b) 75 ares to the l thyroid.

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SURVIILLMICE FREQUENCY

'4 31 days SR 5.11.E.1 Cumulative does 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 parametere in the QDQt.

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'W GRAND QULF, UNIT 1 A 45 Revision 17 - 03/95 l

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i 6.11 RADIOACTIVE EFFLUEFr$

6.11.7 GASEQUS RADifASTE TREATMENT LCO 6.11.7 The GASEOUS RADttASTE TREATMENT (OFFGAS) SYSTEM shall be in operation, i

APPLICASILITY: When the steam jet air ejector (SJAE) is in operation.

f l ACTIONS

( ........................................... NOTES.......................................

l The provisions of Specification 3.0.3 are not applicable.

l l CONDITION REQUIRED M ON NWOR TIME l

A. Gaseous radweste from the A.1 Restore treatment to this 7 days SJAE being discharged discharge.

without treatment.

l Raquired Action A.1 and 5.1 Initiate action to prepare Immediately l

S. l Associated Completion Time and submit a Special Report '

not met. to the Cosetission within 30 days.

SURVEILLANCE REQUIREMEFFS SURVIILLANC3 FREQUENCY SR 6.11.7.1 Ensure that the GASEOUS RAD 11ASTE TREATMENT 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> (OFFGAS) SYSTEM is operating.

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i GRAND GULF, UNIT 1 A 46 Revision 17 03/95

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f i,

t 6.11 RADIOACTIVE EFFLUEES a

6.11.8 VIIrfIZATION EINADST TRIAISEEarf SYSTERE j LCO 6.11.8 The VIIrfILATION EXHADST TREATMEIrr SYSTEM shall be used to reduce radioactive materials in gaseous waste before their discharge when l the projected dose due to gaseous effluent releases to areas at and i

beyond the SITE BOUNDARY in a 31 day period would exceed 0.3 mrom to j any organ.

t a APPLICABILITY: At all times.

! ACTIONS

h. ...........................................ncyggs.......................................

The provisions of Specification 3.0.3 are not applicable.

]

REQUIRED ACTICE CCIEFLETION TIME I; COIEDITION k

Gaseous waste being A.1 Initiate action to prepare Isumediately j A.

i discharged without and submit a Special Report j treatment and greater than to the cosmission within 4 the above limit. 30 days.

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j SURVEILLANCE REQUIRIntEIrfS SURVEILLANCE FREQUERICY v

j Doses due to gaseous releases to areas at and 31 days SR 6.11.8.1 beyond the SITE BOUNDARY shall be projected in 1

" accordance with the methodology and parameters in the ODCM.

M

.......................NCrfE --- - --- -- -

1. Not required to be met when the ventilation exhaust treatment system is undergoing routine maintenance.

2. Not required to be met when the projected dose less than or equal to the above limit.

l . .............................................

Verify the ventilation exhaust treatment 4

system is operating.

4 GRAIID GULF, UNIT 1 A-47 Revision 17 03/95

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l 6.12 RADICIDGICAL ENVIROIRIE3rfAL 3CNITORIIIG l 6.12.1 ICIIITORING PROGRAM 1

i LCO 6.12.1 The radiological environmental monitoring program shall be conducted as specified in ODCM Table 6.12.1 1. The results of this program l shall be validated by use of an Interlaboratory Ccaparison Program corresponding to samples required by 0008 Table 6.12.1 1.

APPLICABILITY: At all times.

' ACTIONS l

...........................................ggyrg3......................................

The provisions LCO 3.0.3 are not applicable.

l ...................................................................................... ,

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REQUIRED ACTI M CCBIPLETICII TIME l i COIIDITION 1

l A. The radiological A.1 Initiate action to include Immediately environmental mitoring in the next Annual i'

program not being Radiological Environmental conducted as specified in Operating Report, a ODCM Table 6.12.1 1. description of the reasons for not conducting the 93 program as required and the i

plans for preventing a The required recurrence.

l Interlaboratory Ccuparison Program not performed.

i 1

The level of radioactivity B.1 Initiate action to prepare Immediately i l 3.

as the result of plant and submit a special 4

effluent in an Report within 30 days.

. enviran=antal sagling 4 medium at a specified location exceeding the reporting levels of CDCK

Table 6.12.1 2 when averaged over any calendar quarter, i

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i d GRAND GULP, UNIT 1 A.48 Revision 17 03/95

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I l ACTIONS fcentinued) 1

. CONDITION REQUIRED ACTION COMPLETION TIME l* C. Milk or broad leaf C.1 Initiate action to identify Inunediately vegecation sempling is this changed location (s) in

, relocated freet one or more the next Annual Radioactive j of the sample locations Effluent Release Report.

< required by ODCM Table i 6.12.1 1. M l C.2 Add this location (s) to the 30 daye radiological environmental annitoring program. l

{ l 1

i SURVIII. LANCE REQUIn=""wr5

! SURVEILLANCE FREQUENCY

}

f SR 6.12.1.1 Radiological envi m atal monitoring eenples Per ODQE

ehall be collected pursuant to 0008 Table 6.12.1 1 Table 6.12.1 1.

i from the locatione given in the table and figurse

! in the ODCM and shall be analysed pursuant to the requirements of ODCM Tables 6.12.1-1 and 6.12.1-3.

j SR 6.12.1.2 Conduct an Interlaboratory Comparison Program and 365 daye l include a sumanary of the results in the Annual Radiological Environmental Operating Report.

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j GRAND GULF, UNIT 1 A 49 Revision 17 03/95

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T_ARn.E 6.12.1-1 OPERATINat RADIOS _u:IcaL anyIw - mi.L neangI1gtING PROGRAM Sampling and Type and Frequency Esposure Pathway Number of Samples (a) of Analysis Collection Frequency (a) and/or Sample and Locations Ala m Continuous sampler Radiolodine Cannister:

Radioiodine and Samples from 5 locatione: -

operation with sample I-131; 7 days Pr.rticulates collection per 7 days or as 3 samples close to the SITE required by dust

- mY (in different sectoral loading, whichever is having the highest calculated more frequent annual average groundlevel D/Q.

Particulate Sampler:

1 sample from the vicinity of a Gross beta radio-cammunity having the highest activity following calculated annual average filter change (b),

groundlevel D/Q. composite (by location) for gamma isotopic (c);

1 sample from a control location 92 days 15-30 km (10-20 mileel distance (d) 92 daye Gamma dose; 92 days CIRECT RADIATICE(e) 40 stations with two or more dosimetere or one instrisment for measuring and recording does rate continuously to be placed in each accessible

• esctor as follows:

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

2) an outer ring approximately

• 3 to 5 miles from the site.

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

A-50 Revision 17 - 03/95 GRAND GULF, UNIT 1

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TABLE 6.12.1-1 (Continuedi OPERATIL**'. RADIOMX3ICAL ENVIROtedEstrAL MONITORING PROGRAN Sampling and Type and Frequency Exposure Pathway ID e r of Samples (a) of Analysis Collection Frequency (a) and/or Sample and Locations NATERBORNE 31 days Gasuna isotopic (c) ; I Surface (f) 1 sample upstream 31 days. Composite I sample downstream for tritium analyses: 92 days Composite sample over t

Discharge Basin 31 day period (g) 92 days n - isotopic (c) and Ground Samples from 2 sources tritium; 92 days '

I-131, Gross p and gasuna l 1 sample of the nearest source 31 days Cistern Water isotopic (c); 31 days that could be affected Composite for tritium; 92 days 1 sample from a control location 184 days n - isotopic (c);

Sediment from I sample from downstream area 184 days Shoreline INGESTION 15 days when Gamuna isotopic (c) and asilk Samples from milking animals animals are on pasture, I-131; 15 days.

in 3 locations within 5 las 31 days at other times when animals distant having the highest are on pasture; 31 days dose potential. If there are none then, 1 sample from milking at other times.

A-51 Revision 17 - 03/95 GRAND GULF, UNIT 1

l TABLE 6.12.1-1 (Continuedi OPERATIONAL RADIOLOGICAL ENVImmerarrAL SKIRGI1T) RING PltOGRAM 4

Sampling and Type and Frequency Emposure Pathway Number of Samples (a) of Analysis Collection Frequency (a) and/or Sample and Imcations Milk (cont'd) animals in each of 3 areas between 5 to S km distant where doses are calculated to be greater than 1 mrom per year (h) i 1 sample from milking animals at a control location (15-30 km distant) 184 days n==== isotopic (c)

Fish and 1 sample of one species of on edible Invertebrates casumercially or recreationally portions; 184 days important fish in vicinity of discharge point 1 sample of same species in areas not influenced by plant discharge 31 days when available Gamme isotopic (c)

Food Products Samples of 3 different kinds of and I-131; 31 days broad leaf vegetation grown nearest each of two different offaite locations with highest anticipated annual average groundlevel D/Q if milk sospling is not performed 31 days when available n - isotopic (c) 1 sample of each of the similar and I-131; 31 days vegetation grown 15-30 km distant if milk sampling is not performed  !

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A-52 Revision 17 - 03/95 GRAND GULF, UIIIT 1

_ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ ____m - - _ y _ m_ __--__ ___._m - __-_m_ _ _ _- . _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ . ._ __ _ _ _ _

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1 r m a s.12.1 1 (canefanad) 4 opema rinwar. nacionicar. anvr=c - cit.i-- w ima p=r:mu l

TARI.E NOTATIQE 1

j

• As described in r.he ODCM.

a Specific paramersrs of distance and direction sector from the centerline of one reactor, and af.ditional description where pertinent, shall be provided for each and every sample location in Table 6.12.1 1 in the table (s) and figure (s) in the ODCM, Refet to NUREG 0133, "Freparation of Radiological Effluent Technical l

i Spectfications for Nuclear Power Plants," October 1978, and to Radiological 1

a.sessment Branch Technical Position, Revision 1, November 1979. Deviations are i permitted frosi che required sampling schedule if specimens are unobtainable due to j hasardous conditions, seasonal unavailability, malfunction of automatic sampling i equipment and other legitimate reasons. If specimens are unobtainable due to sampling equipment, malfunction, every effort shall be made to ecuplete corrective action before the end of the next sampling period. All above deviations frosi the j sa:pling schedule shall be documented in the Annual Radiological Environmental a Operating Report.

It is recognised that, at times, it may not be possible or practicable to continue i

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 l

particult. pathway in question and appropriate substitutione made within 30 days in the radiological environmental monitoring program. Identify the cause of the unava'. lability of sasples for that pathway and identify the new location (s) for ahen ning replacement easples in the next Annual Radioactive Effluent Release i

r. c rt and also include in the report a rievised figure (s) and table (s) for the

ODCM reflacting the new location (s) .

j b Particulate sample filters should be analysed for grose beta 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or more

after sampling to allow for raden and thoron daughter decay. If groes beta j activity in air or water is greater than ten times the yearly mean of control 2

samples for any medium, gamma isotopic analysis should be performed on the individual samples.  ;

4 l c Gamma isotopic analysis means the identification and quantification of gamma-

)

emitting radionuclides that may be attributable to the effluents frcus the i facility.

1 l d The puzpose of this sample is to obtain background information.

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GRAND GUIE, UNIT 1 A 53 Revision 17 - 03/95 I

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T_intm g.12.1 1 (cmef mtad)

Open1TTonf. RADIdiadICAL ENVTun-- -ia --i-10pTier2 pomanu

- Tinf.m NCyf'1 TION (C etinuad) e One or more instruments, such as a pressurised ion chamber, for measuring and recording dose rate continuously may ' e used in place of, or in addition to, integrating dosimeters. For the purp<.x 1 of this table, a thermoluminescent dosimeter may be considered to be ces phosphor and two or acre phosphors in a packet may be considered as two or more dosimeters. Film badges should not be used for measuring direct radiation.

f The " upstream sample" should be taken at a distance beyond significant influence of the discharge. The

• downstream" semple should be taken in an area beyond but near mixing zone, g Cog osite samples should be collected with equipment (or equivalent) which is i capable of collecting an aliquot at time intervals which are very short (e.g.,

l hourly) relative to the compositing period (e.g., monthly) .

! h The dose shall be calculated using methodology contained in the ODCM.

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GRAND GULF, tarIT 1 A-54 Revision 17 03/95

TABLE 6.12.1-2 REPORTING LEVELS FOR RADIQACTIVITY tust-JsATIONS IN ENVIF ~ -inL

• m e _

Reporting Levels b Fish Milk Food Products Water AirborneParticugate or Gases (pCi/m ) (pCi/Kg, wet) (pCi/1) (pCi/Kg, wet)

Analysis (pCi/1)

NA NA NA H-3 2 x 10 MA 3 x 10 NA NA th-54 1 x 10 MA 1 X 10 NA NA Fe-59 4 x 10 MA 3 x 10 NA NA Co-58 1 x 10 MA 1 x 10 NA NA Co-60 3 x 10 MA 2 x 10 NA NA En-65 3 x 10 MA MA NA NA 4 x 10 MA Er-h-25 MA 3 1 x 10 I-131 2 0.9 10 1 x 10 60 1 x 10 Cs-134 30 3

2 x 10 70 2 x 10 Cs-137 50 20 NA 3 x 10 MA 2 x 10 MA Ba-La-140

• 1his is a 40 CFR Part 141 value. If no drinking water pathway exists, a value aFordrinkjngwatersamples.

of 3 x 10 pC1/1 may be used.

b E e BASES 6.12.1 for reporting requirements when multiple or unlisted radionuclides are detected.

A-55 Revision 17 - 03/95 GRAND GULF, UNIT 1

TABLE 6.12.1-3 namwinans ymisnra yon FHg vnnarn I.TMYTS OF DETECTION (f f al (a.bl Airborne Particulate Broad Leaf Fish Milk Vegetation Sediment Water orGag (pci/m ) (pci/kg, wet) (pci/1) (pci/kg, wet) (pC1/kg, dq)

Analysis (pC1/11 NA NA MA 4 1 % AO' MA Gross beta NA NA MA NA H-3 2 x 10 (d) MA gg gg 15 MA 1.3 x 10 2 gg ski-54 2.6 x 10 2 gg ga na Fe-59 3u MA NA 15 MA 1.3 x 10 2 MA MA Co-58,60 gg pg 30 MA 2.6 x 10 2 gg Ea-65 NA MA NA MA NA Er 93 30 NA NA NA 15 MA NA h 95 1 60 MA I-131 lic) 7 x 10-2 MA 1.3 x 10 2 15 60 1.5 x 10 2 Cs-134 15 5 x 10-2 1.8 x 10 2 1.5 x 10 2 18 80 ,

Co-137 18 6 x 10-2 60 NA NA MA NA Ba-140 60 15 MA NA 15 MA NA La-140 s

A-56 Revision 17 - 03/95 GRAle GULF, UNIT 1

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Timfm g.12.1 3 (continued)

MaYmrni VATEMS FOR THE frwtR f mTTS OF DETECTION (f in)

• TABLE NOTATION l

. a. Acceptable detection capabilities for thermoluminescent dosimeters used for i environmental measurements are given in Regulatory Guide 4.13.

b. Table 6.12.1 3 indicates acceptable detection capabilities for radioactive materials in envirnanantal samples. These detection capabilities are tabu 1&ted in I

• terms of the lower limits of detection (LIms) . The LLD is defined, for purposes j of this guide, as the smallest ecacentration of radioactive material in a sample that will yield a not count (above system background) that will be detected with i 95% probability with only 5% probability of falsely concluding that a blank d observation represents a "real* signal.

For a particular measurement system (which may include radiochemical separation):

4.66 s b

I e V

• 2.22

• Y

• exp (- AAt) where LLD is the *a 9ritri" lower limit of detection as defined above (as pCi per unit mass c.r volume). (Current literature defines the LLD as the detection capab2lity for the instrumentation only, and the lec, minimum detectablu concentration, as the detection capability for a given instrument, procedure, and type of sample.)

o is the standard deviation of the background counting rate or of the b counting race of a blank sample as appropriate (as counts per minute)

E is the counting efficiency (as counto per disintegration)

V is the sample eine (in units of mse or volume) 2.22 is the number of disintegrations per minute per picoeurie Y is the fractional radiochemical yield (when applicable) 1 is the radioactive decay constant for the particular radienuclide at is the elapsed time between sample collection (or end of the sample collection period) and tis of counting The value of a used in the calculation of the LLD for a particular measurement system should 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.

GRARD GULF, UNIT 1 A-57 Revision 17 03/95 a

Timf2 s.12.1-1 (c meinued) trarmrw yarnsts FOR Tim fatrER LNTTS OF DETEcff0N fffn)

TABLE EDI1TICE (Continued)

Typical values of I, V, Y and At should be used in the calculation.

It should be recognised that the LIA is defined as an a ggiggi (before the fact) limit representing the capability of a measurement system and not as a neateriori (after the fact) limit for a particular measurement. Occasionally background fluctuations, unavoidable maall sample sise, the presence of interfering nuclides, or other uncontrollable circumstances may render these LLDs unachievable. In such cases, the contributing factors should be identified and described in the Annual Radiological Environmental Operating Report.

c. LLD for drinking water samples. If no drinking water pathway exists, the LLD of gassa isotopic may be used.

3

d. If no drinking water pathway exists, a value of 3 x 10 pC1/1 may be used.

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i GRAND GULF, UNIT 1 A.58 Revision 17 - 03/95

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1 6.12 RADICI4GICAL ENVIROIOtElffAL IONI'ICRING l 6.12.2 LAND USI CENSUS LCO 6.12.2 A land use census shall be conducted and shall identify within a distance of 8 km (5 miles) the location in each of the le meteorological sectors 7f Yne' hearest mi1k animal, the nearest reAidence and the nearest garden of greater than 50 m 2 (500 ft2) producing broad leaf vegetation. Broad leaf vegetation saepling of l

at least three different kinds of vegetation may be performed at the 1 l

SITE BOUNDARY in each of two different direction sectors with the I highest predicted D/Qs in lieu of the garden census.

i APPLICAEILITY: At all times.

ACTIONS l ...........................................ptrr33.......................................

I The provisions of LCO 3.0.3 are not applicable.

l .......................................................................................

l CONDITION REQUIRED ACTION COMPLETION TIME A.1 Initiate action to identify Ismediately l A. A land use census l identifies a location (s) the new location (s) in the which yields a calculated next Annual Radioactive l Effluent Release Report, i

dose or dose comunitment greater than the values

! currently being calculated l in LCO 6.11.6.

3.1 Initiate action to identify Iomediately

, B. A land use census l identifies a location (s) these higher dose which ytelds a calculated location (s) in the next dose or dose comunitment Annual Radioactive Effluent l Release Report.

(via the same exposure

pathway) 20 percer.t ,

greater than at a location &gt from which samples are currently being obtained 3.2 Add these location (s) to 30 days in accordance with LCO the radiological 6.12.1. enviraneantal monitoring program.

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GRAND GULF, UNIT 1 A.59 Revision 17 - 03/95 l

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I SURVEILLANCE REQUIRatEIrrS SURVIILIJutCE FREQUINCY f SR 6.12.2.1 Conduct a land use census during the growing 366 days season. The land use census shall verify the appropriateness of the sample location used to fulfill the requirements of LCO 6.12.1 i

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GRAaED GUIX, UNIT 1 A.60 Revision 17 - 02/95

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1 RASES FCE SBCTION 6.0 LIMITING CCEDITIONS FCE OPERATION AND SURVIILLANCE REQUm W l

l GRAND GULF, UNIT 1 A 61 Revision 17 - 03/95

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6.3 INSTRD)lEIrfATIQE 1 mAsas j

t 6.3.9 RADICACTIVE 1.IODID EFFTITmff immhGiifMG Tibi- --iATION The LCO for 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 alaru/ trip i

setpoints for these instruments shall be calculated in accordance with the procedures l

' in the ODCat to ensure that the alans / trip will occur before exceeding ten times the j effluent concentration limits of 10 CFR Part 20. The OPERABILITY and use of this

' instrumentation is consistent with the requirements of General design Criteria 60, 63 and 64 of Appendix A to 10 CFR 50.

1 6.3.10 nADIntraftvt namw?B IFFTfferf ^--116 T1W1 t u i - ---- i i'PT ON I

i The LCO for radioactive gaseous effluent monitoring instrumentation is provided to monitor and ccatrol, as applicable, gaseous effluents during actual er potential J releases. 'ntose instzusments that monitor the activity of gaseous effluents being ,

released to the environment shall have their alazm/ trip setpoints calculated in I I

accordance with the methods in the ODC3R to ensure that the alarm / trip will occur d before exceeding the limits of 10 CFR Part 20. Other instruments that monitor offgas processing, (i.e. , Offgas Pre Treatment Idenitor and Offges Post Treatment Monitor) are calibrated according to plant procedures. *1he OPERABILITY and use of this i

instrumentation is consistent with the requirements of General Design Criteria 60, 63 l

and 64 of Appendix A to 10 CFR Part 50.

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t GRAND GULF, UNIT 1 A-62 Revision 17 - 03/95 i

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6.11 RADIoafTIVE EFFLtTElfi'$

i RASES LIQUID IFFLUElfr5 ,

i 6.11_1 CQm mm =ATION i

This LCO is provided to ensure that the concentration of radioactive materials  ;

released in liquid waste effluents to UNRESTRICTED AREAS will be less than ten times the effluent concentration values specified in 5:=;aadia B, Table 2, Column 2 to 10 CFR 20.1001 20.2402. It provides operational flexibility for releasing liquid effluents in concentrations to follow the Section II.A and II.C design objectives of Appendix I to 10 CFR Part 50. This limitation provides reasonable assurance that the levels of radioactive materials in bodies of water in UNRESTRICTED AREAS will result in exposures within (1) the Section II.A design objectives of Appendix I, 10 CFR 50, to a MEMBER OF 'ntI FUBLIC, and (2) restrictions authorised by 10 CFR 20.1301(a) . The i concentration limit for dissolved or entrained noble gases is based upon the assumption that Xe-135 is the controlling radionuclide and its effluent concentration in air (submersion) was converted to an equivalent concentration in water. This LCO does not affect the requirement to comply with the annual limitations of 10 CFR 20.1301(a).

The results of pre-release analyses and poet release analyses (of ccaposited samples) shall be used with the calculational methods and parameters in the CDCM to assure that the concentrations at the point of release are maintained within the limits.

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 LID, and other detection limits, can be found in:

(1) HASL Procedures Manual, HML:,192 (2) Currie, L. A., " Limits for Qualitative Detection and Quantitative 40, 586 98 Determination Application to Radiochemistry,' ma=1 r"ha= j (1968).

(3) Hartwell, J. K., " Detection Limits for Radioisotopic Counting Techniques,"

Atlantic Richfield Hanford Company Report AIM-2527 (June 22, 1972).

6_11.2 DOER This LCO is provided to implement the requirements of Sections II.A, III.A and IV.A of Appendix I, 10 CFR Part 50. Me AcrION statements provide the required operating flexibility and at the same time iglement the guides set forth in Section IV.A of W ad4= I which assure that the releases of radioactive material in liquid effluents to UNRESTRICTED AREAS will be kept 'as low as is reasonably achievable.' Also, for fresh water sites with drinking water supplies which can be potentially affected by plant operations, there is reasonable assurance that the operation of the facility will not result in radionuclide concentrations in the Se finished drinking water that are in excess of the requirements of 40 CFR 141.

dose calculations in the 0D08 implement the requirements in Section III.A of Appendix I that conformance with the guides of W ad4* I be shown by calculational procedures based on models and data, such that the actual exposure of a MEISER OF THE i PUBLIC through appropriate pathways is unlikely to be substantially underestimated.

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GRAND GULF, UNIT 1 A 63 ' Revision 17 03/95 4

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RADICACTIVE EFFLUINTS BASES l 6.11.2 DOSE (Continued) l The equations specified in the ODCM for calculating the doses due to the actual i release rates of radioactive materials in liquid effluents are consistent with the methodology provided in Regulatory Guide 1.109, " Calculation of Annual Doses to Man f rom Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance j

with 10 CFR Part 50, Appendix I,* Revision 1, October 1977 and Regulatory i Guide 1.113, 'Istimating Aquatic Dispersion of Effluent f rcus Accidental and Routine Reactor Releases for the Purpose of Implementing WaMx I,' April 1977.

This LCO, in conjunction with LCOs 6.11.5 and 6.11.6 is also provided to meet the dose limitation of 40 CFR 190 that nas been incorporated into 10 CFR 20.1301(d) .

j Even if a site contained up to four reactors, it is highly unlikely that the .

resultant dose to a MERSER OF THE PUBLIC will exceed the dose limits of 40 CFR 190 if j the individual reactors remain withis twice the dcse design objectives of 10 CFR 50 )

Appendix I, and the direct radiatiou doses f rom the units (including outside storage d tanks, etc.) are kept small.

i j Special Report:

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j LCO 6.11.2 requires preparation and submittal of a report in accordance with 10 CFR (

i 50.4 and as defined in 10 CFR 20.2203 (a) (4), if the dose design objectives of 10 CFR 1 50 Appendix I are exceeded.

I j If either the quarterly or the annual limit is exceeded, the report will:

(1) identify the cause (s) for exceeding the limit (s),

' (2) define the corrective actions that have been taken to reduce the releases, and j (3) define the corrective actions to be taken to ensure that future releases l j will be in coepliance with the limits.  !

j If a drinking water supply is taken from the receiving water body within three miles j

downstream of the plant discharge, the report shal.1 also include:

(1) results of radiological analyses of the drinking water source, and 4

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l (2) the radiological impact en finished drinking water supplies with regard to i the requirements of 40 CFR 141.

1 If the doses exceed the limits of 40 CFR 190, 25 arene to the whole body or any organ, except the thyroid, which is limited to 75 areas, the report shall:

(1) define the corrective action to be taken to reduce subsequent releases to prevent recurrence of exceeding the above limits, (2) include the schedule for achieving conformance with the above limits, (3) include an analysis that estimates the radistica exposure (dose) to a MEMBER OF THE PUBLIC freut uranium fuel cycle sources, including all effluent pathways and direct radiatica, for the calendar year that includes the

- release (s) covered by this report, (4) describe the levels of radiation and concentrations of radioactive material involved, (5) describe the cause of the exposure level or concentrations involved, GRAND GULF, UNIT 1 A.64 Revision 17 03/95

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s.11.2 Dost (Continued)

{ (6) describe a course of action that should result in the limitation of the

annual dose to a MunSER OF THE PUBLIC to within the 40 CFR 190 limits.

l For the purposes of the report it may be assumed that the dose comunitment to i the MIRSER OF THE PUBLIC from other uranium fuel cycle sources is 1 negligible, with the exception that the dose distribution frcum other nuclear i

fuel cycle facilities at the same site or within a radius of 8 kilcmeters must be considered.

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The Special Report with a request for a variance (provided the release conditions 1 1

resulting in a violation of 40 CFR 190 have not already been corrected), in l j

accordance with the provisions of 40 CFR 190.11 and 10 CFR 20.2203 (a) (4), is i

considered to be a timely request and fulfills the requirements of 40 CFR 190 until i NRC staff action is completed. The variance only relates to the limits of 40 CFR 1 190, and does not apply in any way to other requirements for does limitaticas of 10 j CfR 20, as addressed in 140s 6.11.1 and 6.11.4. An individual is not considered a MEMBER OF THE PUBLIC during any period in which he/she is engaged in carrying out any i operation that is part of the nuclear fuel cycle.

Demonstration of ccepliance with the limits of 40 CFR 190 or with the design 3

objectives of AppenM w I to 10 CFR 50 will be considered to demonstrate compliance l with the 0.1 rem limit of 10 CFR 20.1301.

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' GRAND GULF, UNIT 1 A 65 Revision 17 - 03/95

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4 6.11.3 LIOUID MasTE Teen'f*m!'

The LCO that the appropriate portions of this system be used when specified provides assurance that the releases of radioactive materials in liquid effluents will be kept "as low as is reasonably achievable." his 140 implements the requirements of 10 CFR 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 I to 10 CFR

} Part 50. The specified limit governing the use of appropriate portions of the liquid i i radwaste treatment system were specified as a suitable fraction of the dose design s- objectives set forth in Section II.A of W W I, 10 CFR Part 50, for liquid .

j effluents. f 1

I Special Report: l l

I LCO 6.11.3 requires preparation and submittal of a report in accordance with 10 CFR 50.4 if radioactive liquid waste is being discharged without treatment and in excess ,

i of the limits. The report shall include:

}

(1) an emplanation why liquid radwaste was being discharged without treatment, f, (2) identification of any inoperable equipment or subsystems which resulted in liquid radwaste being discharged without treatment, (3) the reason for the inoperability I (4) action (s) taken to restore the inoperable equipment to an OPERABLE status, j (5) summary descriptions of actions taken to prevent a recurrence.

}

anstoos IFFImmrrs 1 6.11.4 DOBE BA'f'E '

i This LCO provides reasonable assurance that radioactive material discharged in

{ gaseous effluents will not result in the exposure of a umMaww OF THE FORLIC in an i

l UNRESTRICTED AREA, either at or beyond the SITE BOOM 3 ART in ancess of the design

' objectives of Appendix I to 10 CFR Part 50. This specification is provided to ensure that gaseous effluents from all units on the site will be appropriately controlled.

(

It provides operational flexibility for releasing gaseous effluents to satisfy the

- Section II.A and II.C design objectives of Appendix I to 10 CFR Part 50. For MERSERS OF THE PUBLIC who may at times be within the SITE BOUNDARY, the occupancy of that MEMBER CF THE PUBLIC will usually be sufficiently low to compensate for the reduced atmosphere dispersion of gaseous offluents relative to that for the SITE M - 8Y.

The calculational methods and parameters in the ODCit are used to assure that the dose rates are maintained within the limits. Examples of calculations fos such MRISERS OF THE PUBLIC, with the appropriate occupancy factors, shall be given in the CDQE. The specified release rate limits restrict, at all times, the corresponding dose rates above background to a - OF THE PUBLIC at or beyond the SITE BOONDARY to less than or equal to 500 ares / year to the total body or to less than or equal to 3000 mres/ year to the skin. These releases rate limits also restrict, at all times, the corresponding thyroid dose rate above background to a child via the inhalation pathway to less than or equal to 1500 ares / year. This specification does not affec:t the requirement to comply with the annual limitations of 10 CFR 20.1301(a) .

Se dose rate due to radioactive gaseous offluents shall be determined in accordance with the methodology and parameters of the CDQt.

GRAND GULF, UNIT 1 A 66 Revision 17 - 03/95 4

RADIQAC"fIVE EFFLUENTS RASES _

s.11.4 Dosa Ehg3 (Continued)

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 ins (1) HASL Procedures Manual, MARL-300 (revised annually).

(2) Currie, L. A., ' Limits for Qualitative Detection and Quantitative Determination Application to Radiochemistry," n=1 h 40, 586 93 (1968).

(3) Hartwell, J. K., "Detectica Limits for Radioisotopic Counting Techniques,*

Atlantic Richfield Hanford Caspany Report ARH-2537 (June 22, 1972),

s.11.E DORE tamarm anese This LCO is provided to implement the requiremento of Sections II.3, III.A and l IV.A of Appendix I, 10 CFR Part 50. ne Limiting Cor.tition for Operation implements l the guides set forth in Section II.5 of _ W 4w 1. Se ACTION statements provide

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the required operating flexibility and at the same time implement the guides set forth in Section IV.A of Appendix I to assure that the releases of radioactive material in gaseous affluents to UNRESTRICTED AREAS will be kept as low as is reasonably achievable.*

The Surveillance Requirements implement the requirements in Section III.A of Appendix I that conformance with the guides of Appendix I be shown by calculational procedures based on models and data such that the actual esposure of a nanmen CF THE PUBLIC through appropriate pathways is unlikely to be substantially underestimated.

The dose calculations established in the CDCM 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 RoutineA' eleases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, (--d 4 - I,* Revision 1, October 1977 and Regulatory Guide 1.111, "Methode for Estimating arenapharic Transpart and Dispersion of Gaseous Effluents in Routine Seleases fram Light

• Water Cooled Reactors," Revision 1, July 1977 The ODCX equations provided for determining the air doses at and beyond the SITE BOUNDARY are based upon the historical average atmospheric conditions.

This LCO, in conjunction with LCOs 6.11.2 and 6.11.6 is also provided to meet the dose limitation of 40 CFR 190 that has been incorporated into 10 CFR 1301(d). Even if a site contained up to four reactors, it is highly unlikely that the resultant dose to a MEISER OF '!ME PUBLIC will exceed the dose limits of 40 CFR 190 if the individual reactors remain within twice the dose design objectives of 10 CFR 50 Appendix I, and if the direct radiation doses free the units (including outside storage tanks, etc.) are kept small.

GRAND GULF, UNIT 1 A-f7 Revision 17 - 03/95

RADICACTTVE EFFIDEarfS RAsts s.11.s cost - tenata m amm (Continued)

Special Report:

LCO 6.11.5 requires preparation and submitta: of a report in accordance with 10 CFR 50.4 and as defined in 10 CFR 20.2203 (a) (4), if the dose design objectives of 10 CFR 50 Appendix I are exceeded.

If either the quarterly or the annual limit is exceeded, the report will:

(1) identify the cause(s) for exceeding the limit (s),

(2) define the corrective actions that have been taken to reduce the releases, and (3) define the corrective actions to be taken to ensure that future releases ,

will be in compliance with the limits.

If the doses exceed the limits of 40 CFR 190, 25 areas to tie whole body or any l

organ, except the thyroid, which is limited to 75 areas, thr, report shall:

I ,

(1) define the corrective action to be taken to reduce subsequent releases to prevent recurrence of exceeding the above limits, (2) include the schedule for achieving conformance with the above limits, (3) include en analysis that estimates the radiation exposure (dose) to a ME355R OF M FUBLIC from uranium fuel cycle sources, including all effluent pathways and direct radiation, for the calendar year that includes the release (s) covered by this report, (4) describe the levels of radiation and concentrations of radioactive maderial involved, (5) describe the cause of the exposure level or concentrations involved, (6) describe a course of action that should result in the limitation of the annual dose to a MERSER OF M FUBLIC to within the 40 CFR 190 limits.

For the purposes of the report it may be assumed that the does commitment to the MERSER OF THE FUBLIC from other uranium fuel cycle sources is negligible, with the exception that the dose distribution from other nuclear fuel cycle faciiities at the same site or within a radius of 8 kilometers must be considerM.

The Special Report with a rdquesi. for a variance (provided the release conditions resulting in a violation of 40 CFR M rave not already been corrected), in accordance with the provisions of 40 CF A 190.11 and 10 CFR 20.2203 (a) (4) , is considered to be a timely request and itJ. fills the requirements of 40 CFR 190 until NRC staff action is cospleted.

j The variance only relates to the limits of 40 CFR 190, and does not apply in any way j to other requirements for dose limitations of 10 CFR 20, as addressed in LCOs 6.11.1

- and 6.11.4. An individual is not censidered a MEISER OF ' lite FUBLIC during any period l

j in which he/she is engaged in carrying out any operation that is part of the nuclear fuel cycle.

Demonstration of compliance with the limits of 40 CFR 190 or with the design objectives of Appendix I to 10 CFR 50 will be considered to demonstrate ccepliance with the 0.1 rem limit of 10 CFR 20.1301.

GRAND GULF, UNIT 1 A.63 Revision 17 03/95 r- - __ _ _.

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l 6.11.6 DOSE - IODINE 131. IODTMs-123. TRITItDt AND RADIONDcf TDES IN PARTICtHATE FORM This LCO is provided to implement the requirements of Sections II.C, III.A and j IV.A of Appendix I, 10 CFR Part 50. The Limiting Conditions for Operation are the l

< guides set forth in Section II.C of Appendix I. M e ACTIOR statements provide the

{ required operating flexibility and at the same time implement the guides set forth in i Section IV.A of Appendix I to assure that the releases of radioactive materials in

gaswous effluents to UNRESTRICTED AREAS will be kept "as low as is reasonably j achievable." The ODC38 calculational methods specified in the Surveillance

, Requirements implement the requirements in Section III.A. of W aM x I that 4 conformance with the guides of Appendix I be shown by calculational procedures based l

on models and data, such that the actual exposure of a MEISER OF THE PUBLIC through l appropriate pathways is unlikely to be substantially underestimated. The ODCM calculational methods for calculating the doses due to the actual release rates of I the subject materials 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 Ccagliance with 10 CFR Part 50, W a*

• I,"

Revision 1, October 1977 and Regulatory Guide 1.111, " Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light Water Cooled Reactors," Revision 1, July 1977. These equations also provide for determining the actual doses based upon the historical average atmospheric conditions, ne release race specifications for iodine 131, iodine 133, tritium and radionuclides in particulate form are dependent on the existing radionuclide pathway to man in the areas at and beyond the SITE 'avenusY. Se pathways which were examined in the development of these calculations were: (1) individual inhalation of airborne radionuclides, (2) deposition of radionuclides onto green leafy vegetation with subsequent consuspeian by men, (3) deposition onto grassy areas where milk animals and meat producing animals grase with consumption of the milk and meat by man, and (4) deposition on the ground with subsequent exposure of man.

This LCO, in conjunction with LCOs 6.11.2 and 6.11.5 is also provided to meet the dose limitation of 40 CFR 190 that has been incorporated into 10 CFR 1301(d) . Even if a site contained us, to four reactors, it is highly unlikely that the resultant dose to a MEMBER OF THE PUBLIC will exceed the dose limits of 40 CFR 190 if the individual reactors rossin within twice the dose design objectives of 10 CFR 50 Appendix I, and if the direct radiation doses from the units (including outside storage tanks, etc.) are kept small.

Special Report:

LCO 6.11.6 requires preparation and submittal of a report in accordance with 10 CFR 50.4 and as defined in 10 CFR 20.2203 (a) (4), if the dose design objectives of 10 CFR -

50 Appendix I are exceeded.

If either the quarterly or the annual limit is exceeded, the report will:

(1) identify the cause(s) for exceeding the limit (s),

(2) define the corrective actions that have been taken to reduce the releases, and (3) define the corrective actions to be taken to ensure that future relsalses will be in ecupliance with the limits.

GRAIED GULF, UNIT 1 A 69 ' Revision 17 - 03/95

f RADICJLCTIVE EFFTITD"f2

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f 6.11.6 DOSE IODINE 131. TODTWM-133. TRITItM AND RADIONDr*T>TDES IN PARTICULATE FORM (Continued)

If the d n;., exceed the limits of 40 CFR 190, 25 mress to the whole body or any organ, except the thyroid, which is limited to 75 areas, the report shall:

(1) define the corrective action to be taken to reduce subsequent releases to prevent recurrence of exceeding the above limits, (2) include the schedule for achieving conformance with the above limits, (3) include an analysis that estimates the radiation exposure (dose) to a MEMBER OF THE FUBLIC fr a uranium fuel cycle sources, including all effluent i pathways and direct radiation, for the calendar year that includes the release (s) covered by this report, (4) describe the levels of radiation and concentrations of radioactive material 4

involved, (5) describe the cause of the exposure level or concentrations involved, (6) describe a course of action that should result in the limitation of the annual dose to a MERSER OF THE FUBLIC to within the 40 CFR 190 limits.

For the purposes of the report it may be assused that the dose cessaitment to the MERBER OF THE FUBLIC frcss other uranium fuel cycle sources is negligible, with the exception that the dose distribution from other nuclear fuel cycle facilities at the same site or within a rulius of 8 kilometers must be considered.

The Special Report with a request for a variance (provided,ths u_ ease conditions resulting in a violation of 40 CFR 190 have not already been cor.scted), in accordance with the provisions of 40 CFR 190.11 and 10 CFR 20.2203 (a) (4) , is considered to be a timely request and fulfills the requirements of 40 CFR 190 until NRC staff action is cospleted.

The variance only. relates to the limits of 40 CFR 190, and does not apply in any way to other requirements for dose limitations of 10 CFR 20, as addressed in LCOs 6.11.1 and E.11.4. An individwal is not considered a RERSER OF THE FUBLIC during any period in which he/she is engaged in carrying out any operation that is part of the nuclear fuel cycle.

Demonstration of cospliance with the limits of 40 CFR 190 or with the design objectives of WM4x I to 10 CFR 50 will be considered to d==an=trate cospliance with the 0.1 rem limit of 10 CFR 20.1301.

GRAND QULF, UNIT 1 A-70 Revision 17 03/95 9

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f 6.11.7 and 6.11.9 GASEOUS RADWASTE T9ia'NINT AND VElfrILATION rrMADST TREATMElff The OPERABILITY of the GASEOUS RADWASTE TREATMElff (OFFGAS) SYSTEM and the VENTILATION EXHAUST TREATMENT SYSTEM ensures that the system will be available for use whenever gaseous effluents require treatment before 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 reasonably achievable.' This specification implements the requirements of 10 CFR Part 50.36a, General Design Criterion 60 of Appendix A to 10 CFR Part 50, and the design objectives given in Section II.D of Appendix I to 10 CFR Part 50. The specified limits governing the use of appropriate l portions of the system were specified as a suitable fraction of the dose design objectives set forth in Section II.B and II.C of Appendix I, 10 CFR 50, for gaseous effluents.

i Special Report:

LCOs 6.11.7 and 6.11.8 require preparation and submittal of a report in accordance l with 10 CFR 50.4 including:

(1) an explanation of why gaseous radwaste was being discharged without treatment, (2) identification of the inoperable equipment or subsystems which resulted in l

gaseous radwaste being discharged without treatment, (3) the reason for the inoperability, (4) action (s) taken to restore the inoperable equipment to an OPERABLE status, (5) summary descriptions of action (s) taken to prevent a recurrence. .,.

l LCO 6.11.8 is not applicable to the Turbine Building ventilation exhaust unless filtration media is installed.

Instruments checked to ensure the GASEOUS RADWASTE TREATMENT (OFFGAS) SYSTEM is functioning are:

(1) Adsorber Train Bypass Switch (1N64-HS M611) ,

(2) Bypass Valve Indication (IN64-F045).

When the Adsorber Train Bypass Switch is in the TREAT position and the bypass valve indicates CLOSED, the GASEOUS RADWASTE TREATMENT (OFFGAS) SYSTEM is functioning.

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GRAND GULF, UNIT 1 A 71 Revision 17 - 03/95

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RASES j 6.12.i mwrteninn pacanau l

The radiological monitoring program required by this LCO provides measurements of i

radiation and of radioactive materiale in those exposure pathways and for those radionuclides, which lead to the highest potential radiation exposures of ME3SERS OF j

'[HE PUBLIC resulting from the station operation. '!his monitoring program implements i Section IV.5.2 of W "4- I to 10 CFR Part 50 and thereby ogplements the radiological effluent um itoring program by verifying that the measurable

]

4 concentrations of radioactive materials and levels of radiation are not higher than l i' 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 ccamercial operation. Following this period, program changes may be initiated based on operational emperience.

' The detection capabilities required by Table 6.12.1-3 are state of the art for routine environmental measurements in industrial laboratories. It should be recognised that the LLD is defined as an "a priori * (before the fact) limit representing the capability of a particular measurement. Analyses shall be performed in such a manner that the stated Lime will be achieved under routine conditions.

a l Occasionally background fluctuations, unavoidably saml1 sample eises, the presence of j

interfering nuclides, or other uncontrollable circumstances may render these LIms

unachievable. In such cases, the contributing factors will be identified and a

described in the Annual Radiological Envircasental Operating Report.

J For a more ccuplete discussion of the LID, and other detection limits, see the following:

(1) HASL Procedure Manual, HAEL-300 trevised annually).

i (2) Currie, L. A., " Limits for Qualitative Detection and Quantitative i Determination Application to Radiochemistry," Anal. cham. 40, 586 93 5 (1968).

(3) Hartwell, J. K., " Detection Limits for Radioisotopic Counting Techniques,"

f Atlantic Richfield Hanford Ccapany Report A3E-2527 (June 22, 1972).

If milk or broadleaf vegetation sampling locations are relocated, the cause shall be reported in the next Annual Radioactive Effluent Release Report. Also, include in this report, revised ODCM figure (s) and table (s) reflecting the new locations. The 3 specific locations from which sagles were unavailable may then be deleted from the

! radiological enviremmental monitoring program and the table (s) in the 00Qt, provided j the locations from which the replacement samples were obtained are added to the

' table (s) as replacement locations.

f The requirement for participation in an approved Interlaboratory.comparisce i 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 anvironmental monitoring in ,

i order to demonstrate that the results are valid for the purposes of Section IV.E.2 of I Appendix I to 10 CFR Part 50.

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GRAND GULF, UNIT 1 A 72 g vision 17 03/95

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s.12.1 m wrrenI140 p* m * = (Continued)

Special Report:

LCO 6.12.1 requires preparation and sulmaittal of a report in accordance with 10 CFR j 50.4 when:

j (1) the level of radioactivity as a result of r.lant effluents in an environmental sampling mediusi at a specified location exceeds the reporting level (s) in ODOi Table 6.12.1 2 when averaged over a calendar quarter, or (2) more than one of the radio nuclides in ODCM Table 6.12.1-2 are detected in the sampling medium and s.

aaaaaaeemeten (2) + .. 21.0, or eaaeanermelan fil +

1 reporting level (1) reporting level (2)

I j (3) radio nuclides other than those in CDQt Table 6.12.1-2 ac detected, and the potential annual dose to a unuman OF TER FQBLIC is <rqual to or greater 8

than the calendar year limits of 140s 6.11.2, 6.11.5 and 6.11.6.

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! The rept:rt shall:

(1) identify the cause(s) for ==a=ading the limit (s) , and i

i (2) define the corrective actions to be taken to reduce radioactive effluents so 4

the potential annual does to a unem OF 't1EE PUBLIC is less than the i calandar year limits of LCOs 6.11.2, 6.11.5 and 6.11.6.

l The Special Report is not required if the measured level of radioactivity is not the 4

4 result of plant effluents however in such an event, the condition shall be reported 3 and identified in the Annual Radiological Environmental Operating Report.

g.12.2 f an tfBE N l

This LCO is provided to acaure that changes in the use of t.reas at and beyond the

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SITE BOUNDARY are identified and that modifications to the radiological 'the environmental best j monitoring program are wA m if required by the results of the census.

information from door to door survey, visual or serial susvey or frasthe consulting with local agricultural authorities shall be used. 'this census satisfies requirements of Section IV.5.3 of Appendix I to 10 CFR Part 50. Restricting the census to gardens of greater than 50 m2 provides assurance that significant exposure pathways via leafy

vegetables will be identified and monitored since a garden of this sise is the minimum required to produce the quantity (26 kg/ year) of leafy vegetables assumed in 1

Regulatory Guide 1.109 for consusption by a child. To determine this minimum used forgarden size, the following assumptions were made: (1) 20% of the garden was and (2) a growing broad leaf vegetat(on (i.e., similar to lettuce and cabbage),

vegetation yield of 2 kg/m*. Specifications for broad leaf vegetation segling in i

i the Table 6.12.1 1 shall be followed, including analysis of control semples.

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s.12.2 e wn esa emeses (Continued)

' The land use census should utilise information which provides the best results, such

! as a door to door survey, an 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 5.6.2.

4 When the Land Use census requires addition of sampling location (s) to the Environmental Mcnitoring Program, the sampling locations (s) having the lowest calculated dose or dose ccesutmente(s), via the same exposure pathway, may be deleted fremt the monitoring program. 'ntis deletica may take place after October 31 of the i year in which this land use census was conducted.

l The new sampling location (s) shall be identified in the next Annual Radioactive Effluent Release Report including a revised figure (s) and table (s) for the CDCK.  !

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i ATTACHMENT II l 1

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!, 1994 ARERR CORRECTED PAGES  :

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l ATACHMENT II-

! CORRECTED PAGE 1994 ARERR II. DETAILED INFORMATION (CONT'D) is' increased to satisfy the requirements of footnote "c" of Table 1D,

" Radioactive Gaseous Waste Sampling and Analysis,". (GGNS ODCM Appendix A, Table 4.11.2.1.2-1 [6.11.4-1]. Presently, strontium analysis is performed by a qualified contract laboratory. '

Appendix A of Regulatory Guide 1.21 states "In estimating releases for periods when analyses were not performed, the average of the two adjacent data points spanning this period should be used."

Releases from the Turbine Building, Fuel Handling Building and Containment Building exhausts were estimated using this guidance. These releases

occurred during April, August, October and December 1994. Each release l

l was evaluated and documented and found to have no significant effect on the total release from the site.

4. For Batch Releases: Gases 1

The processing of batch type releases (from Containment Purge) is analogous to that for continuous releases.

5. For Batch Releases: Liquid Effluents The radionuclides listed below are considered when evaluating liquid effluents:

H-3 Mo-99 l i Co-58 Tc-99m l Co-60 1-131 l Fe-55 I-132 Fe-59 I-133 l Zn-65 I-135 I

Mn-54 Cs-134 Cr-51 Cs-137 Sr-89 Ba-140 Sr-90 La-140 Nb-95 Ce-141 Zr-95 Ce-144 l

Representative pre-release grab samples are obtained and analyzed as  !

required by Table 2C. Isotopic analyses are performed using the  !

computerized pulse height analysis system previously described. Aliquots of each pre-released sample, proportional to the waste volume released, are composited in accordance with the requirements of Table 2C. Strontium-89, 90 and Iron-55 values are obtained by chemical separation and counting the separated strontium and iron using liquid scintillation techniques. Gross alpha determinations are made using 2-pi gas flow proportional counter.

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1994 ARERR l l

III. R ADIATION DOSE SUMM ARY (CONT'D)

Direct Radiation I i

Direct radiation dose is calculated by subtracting average doses measured by I thermoluminescent dosimeter (TLD) badges located at control locations from I average doses measured by TLD badges located near the site boundary, l

1994 Airborne Effluent Dose (mrem) _

1st Qtr 2nd Qtr 3rd Qtr 4th Qtr TOTAL Iodine, Tritium & Particulates 9.46E-3 1.30E-2 3.09E-2 1.7/E-2 7.11E-2 Fission and Activation (Skin dose, mrem /yr) 1.28E-2 6.68E-2 2.17E-2 2.77E-2 Gamma 1.43E-3 6.13E-3 1.71E-3 4.53E-3 1.38E-2 Air dose *

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• 1.54E-3 . 4.49E-3 1.86E-3 2.31E-3 1.02E-2 Direct Radiation 0 0 0.1 0 0.1

• Measurement units are mrad IV. OFFFSITE DOSE CALCULATION MANUAL /

R ADIOACTIVE WASTE TREATMENT SYSTEM CHANGES  ;

A. Offsite Dose Calculation Manual (ODCM) )

Revision 15 was issued in January 1994 implementing changes resulting from the revision of 10CFR Part 20. Revision 16 was issued in December 1994 to correct a

typographical error. Revisions 15 and 16 affected pages are included in Attachment I.

B. Radioactive Waste Treatment Systems No major changes were made during the report period.

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