ML20043A372
| ML20043A372 | |
| Person / Time | |
|---|---|
| Site: | San Onofre  |
| Issue date: | 04/30/1990 |
| From: | Siacor E SOUTHERN CALIFORNIA EDISON CO. |
| To: | |
| Shared Package | |
| ML13309A916 | List: |
| References | |
| NUDOCS 9005210267 | |
| Download: ML20043A372 (188) | |
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y NRC MONTHLY OPERATING REPORT DOCKET NO:- 50-361 ! UNIT NAME: SONGS - 2 i DATE: May 14 1990 COMPLETED BY: E. R. Siacor l TEl.EPHONE: (714) 368 6223 J l 0PERATING STATUS j
- 1. Un'it Name: San'Onofre Nuclear Generatina Station. Unit 2 l
- 2. Reporting Period: Acril 1990 j
- 3. Licensed Thermal Power (MWt): 3390 1
- 4. . Nameplate Rating (Gross MWe): 1127
- 5. Design Electrical Rating (Net MWe): 1070
- 6. Maximum Dependable Capacity-(Gross MWe): 1127 ;
- 7. - Maximum Dependable Capacity (Net ~ MWe):. 1070 , i
- 8. If Changes Occur In Capacity Ratings (Items Number 3 Through 7) '
Since Last Report, Give Reasons: NA ! I
- 9. Power Level To Which Restricted' If Any (Net MWe):
, NA
- 10. Reasons For Restrictions, If.Any: NA This Month Yr.-to-Date Cumul'ative :
i
- 11. Hours In Reporting Period 719.00 2.879.00 58.752.00 {
- 12. Number Of Hours Reactor Was Critical 719.00 2.844.17 41.911.01 6
- 13. Reactor Reserve Shutdown Hours 0.00 0.00- 0.00 ;
- 14. Hours Generator On-Line 719.00 2.837.90 40.980.93 .l
- 15. Unit Reserve Shutdown Hours 0.00 0.00 0.00 !
- 16. Gross Thermal Energy Generated (MWH) 2.410.063.88 9.535.293.26 133.470.322.57 i
- 17. Gross Electrical Energy Generated (MWH)827.107.50 3.290.932.00- 45.265.639.00 '
- 18. Net Electrical Energy Generated (MWH) 789.316.00 3.142.462.00- 42.885.306_,11 !
- 19. Unit Service Factor 100.00% 98.57% 69.75% '
- 20. Unit Availability Factor .
100.00% 98.57% 69.75% i
- 21. Unit Capacity Factor (Using MDC Net) 102.60%- 102.01%- 68.22% .
- 22. Unit Capacity. Factor.(Using DER Net) 102.60% 102.01% 68.22% ;
- 23. Unit Forced Outage Rate 0.00% 0.00% 6.26%-
24.. Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of Each): l NA !
- 25. If Shut Down At End Of Report Period, Estimated Date of Startup: NA !
- 26. Units In Test Status (Prior To Commercial Operation): Forecast Achieved ;
8 INITIAL CRITICALITY NA NA l INITIAL ELECTRICITY NA NA ! COMMERCIAL OPERATION NA NA j I mor.apr/2 i h520267900514 I R DOCK 050003$3 g PDC C l
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I IU AVERAGE DAILY UNIT PWER LEVEL
. DOCKET NO:' :50-361 UNIT NAME:. SONGS - 2 DATE: _ May 14, 3990 COMPLETED BY: E. R. Siacor .
. TELEPHONE: (7141 368-6223 MONTH: Anril 1990 DAY AVERASE DAILY PWER LEVEL DAY AVERAGt: DAILY POWER LEVEL
'(MWeNet) (MWe-Net) ,
1 1162.91 17 1094 ~. 88 2 1116.17 18 1097.08 3 1113.33 19 1106.79 ' 4- 1113.88 20 '1098.00 5 1111.88 21 1108.29' 6 1103.08 22' '1109.33 7 884.71 23 1107.17-8 1110.21 24 1106.92' ,, 9 , 1110.71 25 1106.79 10 , 1110.92 26 1106.29 11 1108.33 27 1106.71 12 1106.63 28 1096.08 13 1101.00 29' 1104.79 14 1094.38 30 '1058.79 15 1089.71 31 NA 16 1090.88 mor,apr/3
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UNIT SMTDt"Nt3 AM PONER REDUCTIONS DOCKET NO: '50-361 UNIT NAME: SONGS - 2 REPORT MONTH: APRIL 1990 DATE: May 14, 1990-COMPLETED BY: E. R. Siacer TELEPHONE:- f7141 368-E273 Method of Shutting Duration Systeiy Down LER Cg.5;.t Cause & Corrective No. Date Typel .(Hours) Reason 2 Reactor 3 No. Code' Code Action to
' Prevent Recurrence 54 900407 5 0.00 B 5 NA KE- COND Poier reduction of 20% or greater lto perform heat treating operations for the ~
circulating water tunnels.
'I -Forced F 2 Reason: -3 Method: 4IEEE Std 805-1984 S-Scheduled A-Equipment Failure'(Explain) 'l-Manual B-Maintenance or Test 2-Manual Scram.
C-Refueling .- . 3-Automatic Scram. D-Regulatory RestrictionL 4-Continuation-from E-Operator Training &' License Examination Previous Month H F-Administrative .
. 5-Reduction of 20% -SIEEE Std 803A-1983
.G-Operational Error (Explain).- or greater in the H-Other-(Explain) past 24. hours-6-Other'(Explain) -l
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SUMMARY
OF OPERATING EXPERIENCE FOR THE MONTH
-DOCKET NO: 50 361 ,
UNIT NAME: SONGS - 2 DATE: uv to. 1990 COMPLETED BY: E. R. Siacor TELEPHONE: (714) 368 6223
.7 D111 list 11 tat April 1 0001 Unit is in Mode 1 at 100% reactor power. Turbine' load at 1165 MWe-gross.
April 6 2228' Commenced > reactor power decrease from 100% to 80% power to perform heat-treating operations for the circulating water tunnels. April 7 0230 Reactor at 80% power. Preparations for heat treat: commenced. 1235 Commenced heat treating operations. 1700 Completed heat treating operations. 1740 Commenced reactor power increase to 100% power. 2225- Reactor at 100% power. April 30 2400. Unit is in Mode 1 at 100% reactor power. Turbine load at 1154 MWe gross. 4 t t mor.apr/5
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REFUELING INFORMATION DOCKET NO: !io-361 UNIT NAME: SONGS - 2 .) DATE: May 14 1990 [ COMPLETED BY: E. R. Siacor j t TELEPHONE: 014) 308-6223 MONTH: Acril 1990 ,
- 1. Scheduled date for next refueling shutdown. l Forecast for June 1991.. ]
- 2. Scheduled date for restart-following refueling. ~
Forecast for September 1991. l
- 3. Will refueling or resumption of operation thereafter require a Technical Specification change'or other license amendment? .
Nat yet specifically determined. Onder evaluation. What will these be? - Not yet determined. !
- 4. Scheduled date for submitting proposed licensing action and supporting ;
informaticn. , Not yet specifically determined. Under evaluation. I
- 5. Important Licensing considerations associated ytth refueling. e.g., new or [
different fuel design or supplier, unreviewed design or performance !' analysis methods, significant changes in fuel design,-new operating procedures.. . ; Not yet specifically determined. Under evaluation. [ t t ( l o mor.apr/6 l
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REFUELING INFORNATION DOCKET NO: _' 12:251 UNIT NAME: SONGS DATE:. May 14, 1990 COMPLETED BY: E. R Siacor TELEPHONE: -(714) 368 6223 4 MONTH: Anril'1990
- 6. The number of fuel assemblies, a) In the core. 217-b) In the spent fuel storage pool. 446 (376 Unit'2 Soent Fug]
Assemblies and 70 Unit 1 Soent-Fuel Assemblies)
- 7. Licensed ~ spent fuel storage capacity. 1542 *'
Intended change in spent fuel storage capacity.- None Expanded from 800 to 1542 by License Amendment No. 87 - Facility. modification is scheduled to complete.by December 1990.
- 8. Projected date of last refueling that can be discharged to spent fuel storage pool assuming present capacity.
Approximately 2001 (full off load capability)- t mor.apr/7
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NRC MONTHLY OPERATING REPORT DOCKET NO: 50-362 UNIT NAME: 10RG.S - 3 DATE:- Mov 14 1990 - - COMPLETED BY: E. R. Siacor ! TELEPHONE: I7141 368 6223 OPERATING STATU$
-l
- 1. Unit Name: - San Onofre Nuclear Generatina Station. Unit 3
- 2. Reporting Period: April 1990
- 3. Licensed Thermal Power (MWt): 3390
- 4. Nameplate. Rating (Gross MWe): 1127 :
- 5. Design Electrical Rating (Not NWe): 1080
- 6. Maximum Dependable capacity (Gross' MWe): 1127 !
- 7. Maximum Dependable Capacity (Net MWe): 1080 ;
- 8. If Changes Occur In Capacity Ratings (Items Number 3 Through 7) :
Since Last Report, Give Reasons: ; _ NA ,
?
- 9. Power Level To Which Restricted, If Any-(Net MWe): NA
- 10. Reasons for Restrictions, If Any: NA i i
This Month Yr.-to-Date Cumulative :
- 11. Hours In Reporting Period 719.00 _ 2.879.00 53.303.00
- 12. Number Of Hours Reactor Was Critical 315.33 2.294.21 40.224.39
- 13. Reactor Reserve Shutdown Hours 0.00 0.00 0.00 "
- 14. Hours Generator On Line 315.33 2.278.18 39.094.26 -
- 15. Unit Reserve Shutdown Hours 0.00 0.00 0.00
- 16. Gross Thermal Energy Generated (MWH) 1.037.723.96 7.496.618.89 123.364.375.44
- 17. Gross Electrical Energy Generated (MWH) 355.800.50 2.553.085.50 41.837.797.00
- 18. Net Electrical Energy Generated (MWH) 333.198.89 2.407.945.89 39.450.057.09 ,
- 19. Unit Service Factor 43.864 79.13% 73.34%,
- 20. Unit Availability Factor 43.86% 79.13% 73.34%
- 21. Unit Capacity Factor (Using MDC. Net) 42.91% 77.44% 68. 53%___ .
- 22. Unit Capacity Factor (Using DER Net) 42.91% 77.44% 68.53%
- 23. Unit forced Outage Rate 0.00% 7.96% 7.71%
- 24. Shutdowns Scheduled Over Next 6 Months (Type, Date and Duration of Each):
-Cycle 5 refuelina outaae commenced on April 14. 1990 is in oroaress. ^
Outaae duration scheduled for 78 days.
- 25. If Shut Down At End Of Report Period, Estimated Date of Startup: July 1 1990 l
- 26. Units In Test Status (Prior To Commercial Operation): Forecast Achieved ;
INITIAL CRITICALITY NA NA INITIAL ELECTRICITY. NA NA COMMERCIAL OPERATION NA NA mor.apr/8
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f I AVERAGE DAILY UNIT PWER LEVE i DOCKET NO: 50-362 ! UNIT NAME:- SONGS - 3 DATE May 14, 1999 i COMPLETED BY: E. R. Siator ' TELEPHONE: G14) 368 6223 l MONTH: Anril 1990 _ q DAY AVERAGE DAILY POWER LEVEL: DAY AVERAGE DA!LY PWER LEVEL ! (MWeNet) (MWeNet) ! i 1 , 1153.74- 17 0.00 ! i 2 1103.96' I8 0.00 t 2 1102.88' 19- 0.00 -
>I 4 .
1102.83- .20 0.00 j 5 1097.96 21 0.00 I 6 1096.42 22 0.00 + 7 1105.04 23 0:00 8 1108.29 24 0.00 : 9 1105.42 25~ 0.00 l t 10 1100.96 " 26 0.00 i 11 1097.21 27 0.00 .l t 12 1015.75 28 0.00 t 5 13 843.17 -29 0.00 14 35.97 30 0.00 15 0.00 31 NA 16 0.00 , i l.
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WIT SDENDOWS AM POWER REDUCTIONS DOCKET NO:: 50-362 UNIT NME: SONES - 3 _
- REPORT MONTH: APRIL 1990 DATE: May 14, 1990 COMPLETED BY: E. R. Stacor-TELEPHONE: (714) 368-6223 "Aethod of Shutting Duration Down LER Systeg C t- Cause & Corrective No. Da'te Type l (Hours) Reason 2 Reactor 3 No. Code Code Action to Prevent Recurrence 54 900414 'S 403.67 C 1 M M- M Cycle 5 refueling outage.
1F-Forced . 2Reason: 3 Method: 41EEE Std 805-1984
.. s S-Scheduled A-Equipment Failure-(Explain)- 1-Manual 2-Manual Scram.
B-Maintenance or Test-C-Refueling _ 3-Automatic Scram. D-Regulatory Restriction ~ 4-Continuation from E-Operator Training & License Examination Previous Month-F-Administrative 5-Reduction of 20% -SIEEE Std 803A-1983 G-Operational Error (Explain) or greater in the H-Other (Explain) past 24. hours.
'6-Other-(Explain) mor.apr/10 L
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$UMMARY OF OPERATING EXPERIENCE FOR THE MONTH DOCKET NO: 50-362 UNIT NAME: SONGS - 3 DATE: May 14 1990 COMPLETED BY: E. R. Siacor TELEM10NE: (714) 368-6223 QA1.t liat IXfl11 April 1 0001 Unit is in Mode'l at 100% reactor power. Turbine load at 1155 MWe gross.
April 12 0800 Commencet reactor power decrease to 80% to perform' heat treating operations for the circulating water tunnels.
-April 13 0215 Reactor at 80% power. . Preparations for heat treating operations in progress.. .
0841 Commenced heat treating operations. 1210 Completed heat treating operations. April 14 0100 Commenced reactor power decrease for'the Cycle 5' refueling outage. 0420 Manually tripped main turbine followed by manually
. tripping the reactor.
April 15 0525 Entered Mode 4. April 16 0204 Entered Mode 5. April 24 0100 Detensioned reactor head bolts. Entered Mode 6. l April 30 2400 Unit is Mode 6. Core alterations in progress. l l l-t mor.apr/ll L L. I
J REFUELING INFORMATION DOCKET NO: 50-362 l UNIT NAME: SONGS --3 1 DATE: 5/14/90 1 COMPLETED BY: E. R. Siacor- l TELEPHONE: (714) 368 6223 : i l MONTH: April 1990 i i
- 1. Scheduled date for next' refueling shutdown. I Forecast to start during the fourth quarter of 1991.
- 2. ' Scheduled date for restart following refueling, ii; Forecast -tb restart during the first quarter of 1992. !
Will refueling or resumption of operation.thereafter require a Technical 3. Specification change or other license amendment? Not yet specifically determined. Under evaluation. What will these be? ! Not yet specifically determined. Under evaluation.
- 4. Scheduled date for submitting proposed licensing action and supporting information.
Not yet specifically determined. Under evaluation, t
- 5. Important Licensing considerations associated with refueling, e.g., new or ,
different fuel design or supplier, unreviewed design or performance -l analysis methods, significant changes in fuel- designi new operating - . procedures. l Not yet specifically determined. Under evaluation. P [ l- mor.apr/12 i L ; l P l
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i i REFUELING INFORMATION i
-DOCKET NO: 50-362 1 UNIT NAME: SONGS - 3 )
DATE: May 14 1990 ' COMPLETED BY: .E. R. Siacor 1 TELEPHONE: (714) 368-6223 l i j 1 MONTH: Anril'1990 6.- The number of' fuel assemblies. .! a) In the core. '183 !
- i b) LIn the spent fuel. storage pool. 479 (302 Unit 3 Soent fuel' Assemblies. 69 Unit 1 Soent ,
, :uel Assemblies and 108 New ;
ruel Assemblies) !
- 7. Licensed spent fuel-storage capacity.- 1542 *
- Intended change-in spent. fuel storage capacity.- None l,
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Expanded from 800 to 1542 by License Amendment No. 77 - Facility. [ modification is scheduled to. complete by September 1991. ! . 8. Prbjected date-of last refueling that can be discharged to spent. fuel ; storage pool assuming present capacity. Approximately 2003 (full off load capability)
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1 j I February 21, 1990 i Mr. H. E. Morgan l
SUBJECT:
Revision 21 to the Units 2/3 offsite Dose Calculation , Manual (ODCM) l I In accorcance with Technical Specifications 6.5.2.9 and 6.14. 2, Revision il to the Units 2/3 ODCM has been prepared and reviewed ; for adopticn on February 15, 1990. This revision is occationed by ! Technical Specifications Amendments' Number 83 for Unit 2 and Number 73 for Unit 3. .These amendments are in response to NRC Generic ; Letter 89-01, which allowed the movement of the Radiological l' Effluent Technical Specifications from the Technical Specifications ' to the ODCM. Your approval-for this change is requested. Copies of this letter are being forwarded to the Site. Manager Vice : President, and the Nuclear Safety Group as required by Technical , Specification 6.5.2.10. ' If there are any questions, please don't hesit te a a.
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! , < / r Approvedbp: [A-H. f. MORGAN
[$ Station. Manager ! cc , R. H. Bridenbecker P. H. Penseyres W. W. Stro X. Helm # . R. Plappe t . E. S. Medling f Chem File ! CDM
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April 30, 1990
SUBJECT:
Revision 21 to Units 2/3 Offsite Dose Calculation Manual On February 15, 1990, Revision 21 to the Offsite Dose Calculation Manual (ODCM) was adopted and published. This revision moved the Radiological Effluent Technical Specifications (RETS) verbatim from the Technical Specifications to the ODCH per the NRC Generic Letter 89 01, Amendment 83 to~ the Unit 2 Technical Specifications, and Amendment 73 to the Unit 3 Technical Specifications. It has been determined that-these changes do not reduce the accuracy or reliability of the dose calculations and setpoint determinations. Documentation of the fact that this revision has been reviewed and found acceptable by the Station Manager is indicated by inclusion of a letter dated February 21, 1990 signed by the Station Manager. The RETS were incorporated as follows: Technical Soecification QDCM "Snecification 3.11.1.1 1.1.1 3.11.1.2 1.2.1 3.11.1.3 1.3.1 3.11.2.1 2.1.1 3.11.2.2 2.2.1 3.11.2.3 2.3.1-3.11.2.4 2.4.1 3.11.4 2.5.1 3.3.3.8 4.1.1 3.3.3.9 4.2.1 3.12.1 5.1 3.12.2 5.2 3.12.3 5.3 1.0 Definitions 6.) Table 1.1 (Operational Modes) Table 6-1 Table 1.2 (Frequency Notation) Table 6 2 6.9.1.8 6,2 6.15 6.3 1 i. l L-
o _ 1 Technical Specification ODCM "Soecification" Surveillance Surveillance 4.11.1.1.1 1,1,1.1 4.11.1.1.2 1.1.1.2 4.11.1.1.3 1.1.1.3 4.11.1.2 1.2.1.1 4.11.1.3.1 1.3.1.1 4.11.1.3.2 .l.3.1.2 4.11.2.1.1 2.1.1.1 14.11.2.1.2 2.1.1.2 4.11.2.2 2.2.1.1 4'.11.2.3 2.3.1.1 4.11.2.4.1 2.4.1.1 4.11.2.4.2 2.4.1.2 4.11.4 2.5.1.1 4.3.3.8.1 4.1.1.1 4.3.3.8.2 4.1.1.2' 4.3.3.9 4.2.1.1 4.12.2 5.2.4 i s
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1 I I l 9 0FF31TE DOSE CALCULATION MANUAL , i NUCLEAR GENERATION $1TE ! i UNITS 2 AND 3 !
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APPROVED FEB 211990' l 1 . tl REGElvt0GSM ! 00CM2 Revision 21 ;
- j. 3081c. man FEB 101990 02-15-90 t.
t- CIE FILE COPY , i I > I l .t
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I l 1 00CM . : 1 TABLE OF CONTENTS ! E121 ) LIST OF FIGURES ....................................................... iii L I ST O F TAB L E S . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . i v - v t INTRODUCTION .......................................................... vi , 1.0 LIQUID EFFLUENTS...................................;.............. 1-1 , t 1.1 1-1 i Concentration................................................ l.1.1 Spec i fi c a t i on . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1-1 1.1.1.1, 1.1.1.2, 1.1.1.3 Survei11 ances . . . . . . . . . . . . . . . . . . . . . . 1-1 1.2 Dose l 1.2.1 Specification....................................... 1-5 *
- 1. 2 .1.1 S u rve i 11 an c e . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1-5 1.3 Liquid Waste Treatment...................................... 1-6 _
1.3.1 Specification....................................... 1-6 1.3.1.1, 1.3.1.2 Survei11ances.............................. 11-6. , 1.4. Liquid Ef' fluent Moni tor Setpoi nts. . . . . . . . . . . . . . . . . . . . . . . . . . . 1-8 , 1.4.1 Batch Release Setpoint Determination.............<'.. 1-10 1.4.2 Continuous Release Setpoint Determination........... 1 16 l- 1.5 Dose Calcul ations for Liquid Effluents. . . . . . . . . . . . . . . . . . . . . . 1-26 1 s 1.6 Representative Sampling..................................... 1-29 L 1 2.0 GASE0US EFFLUENTS................................................. 2-1 2.1 DoseRate...................................................2-1 2 .1.1 S p ec i fi c a t i o n . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2-1 2.1.1.1, 2.1.1.2 Survei11ances........-...................... 2-1 2.2 Dose - Noble Gas............................................ 2-5 2.2.1 S pe c i fi c a t i on . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2-5 2.2.1.1 Surveillance........................................ 2-5 2.3 Dose - Radioiodines, Radioactive Materials in Particulate Form and Tritium............................................ 26 2.3.1 Specification........................................ 2 2 . 3 .1.1 S u rve i l l an c e . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 26 Revision 21 i 02-15-90 APPROVED FEB 211990 -
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ODCM TABLE OF CONTENTS (Continued) . P.lat . 2.4 Gaseous Radwaste Treatment.................................. 2-7 !
- 2. 4.1 S p e ci fi c a t i on . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2-7 !
2.4.1.1, 2.4.1.2 Su rve il 1 anc e s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 27 ' 2.5 TotalDose..................................................28 2.5.1 Specification......................................... 28 ; 1 2 . 5.1.1 S u rve i l l a nc e . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2-8. 2.6 Gaseous Effluent Monitor Setpoints . . . . . . . . . . . . . . . . . . . . . . . . . 2-10 2.6.1 Plant Stack ........................................ 2 10 . 2.6.2 Condenser Evacuation System......................... 2 14 Containment Purge ...................................~2-17 ; 2.6.3
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2.7 Gaseous Ef fl uent Dose Rate . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2-25 2.7.1 No bl e G a s e s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2-26 2.7.2 Radioiodines and Particulates ...........'........... 2-26 2.8 Gaseous Ef fluent Dose . Calcul ation . . . . . . . . . . . . . . . . . . . . . . . . . . 2-28 2.8.1 N o bl e G a s e s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2 - 2 8 2.8.1.1 Hi storical Meteorology !. . . . . . . . . . . . . . . . . . 2-28 2.8.1.2 Concurrent Meteorol ogy . . . . . . . . . . . . . . . . . . . 2-29 < 2.8.2 Radioiodines and Particul ates . . . . . . . . . . . . . . . . . . . . . . . 2-30 2.8.2.1 Hi storical Meteorology . . . . . . . . . . . . . . . . . . . 2 ' - 2.8.2.2 Concurrent Meteorology . . . . . . . . . . . . . . . . . . . 2 32 2.9 Tot al Do s e C al cul ati ons . . . . . . . . . . . . . . . . . . . . . . . . . . . .~. . . . . . . . 277 2.9.1 Total Dose to Most Likely Member of the Public ..... 2-77 2.9.2. Thyroid Dose ........................................ 2 79 3.0 PROJECTED DOSES 3.1 Liquid Dose Projection ..................................... 3-1 . 3.2 Gaseous Dose Projection .................................... 3 , 4.0 EQUIPMENT........................................................ 4-1 1 4.1 Radioactive Liquid Effluent Monitoring Instrumentation...... 4-1 4 .1.1 S p e c i f i c a t i on . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 4-1 4.1.1.1, 4.1.1.2 Surveillances.............................. 4'1
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l Revision 21 ii 02-15 90 t
. APPROVED FEB 211990 i
00CM 1 TABLE OF CONTENTS (Continued) : Elat ; 1 4.2 Radioactive Gaseous Effluent Monitoring Instrumentation..... 46 .
. 4. 2.1 Spe ci fi c ati on . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 4- 6 j 4 . 2.1.1 S u rv e i l l a n c e . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6 4.3 Operability of Radioactive Waste Equipment.................. 4-12 i i
I 5.0 Radiol ogical Envi ronment al Mon'i toring . . . . . . . . . . . . . . . . . . . . . . . . . . . . 5-1 ! 5.1 Radiological Envi ronmental Monitoring Program. . . . . . . . . . . . . . . 51
- 5.2 Land Use Census............................................. 5-10 j 5.3 Interl aboratory Compari son Program. . . . . . . . . . . . . . . . . . . . . . . . . . 5-10 i
5.4 Annual Radiological Environmental Operating Report.......... 5-11 . 5.5 S ampl e Lo c a t i o n s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 5 - 12 3 5.6 Bases....................................................... 5-12 c 6.0 Administrative................................................... . 6-1 .;
. 6.1 De f i n i t i o n s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6-1 1
6.2 Administrative Controls..................................... 6-6 6.3 Mejor Changes to Radioactive Waste Treatment Systems (Liquid and Gaseous)......................................... 6-8 ; 6.4 Bates....................................................... 6-9 V 1 y Rev. 21 e t iii 02 15-90 o . APPROVED FEB 211990 . i
r ODCM LIST 0F FIGURES Fiaure Title Paae 12 Site Boundary for Liquid Effluents............................... . 1-7 2-2 Site Boundary for. Gaseous Effluents. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2-9 4-5 SONGS 2 and 3 Radioactive Liquid Waste Treatment Systems......... 4 13 4-6 SONGS 2.and 3 Radioactive Gaseous Waste Treatment Systems........- 4-14
' **10 4-7 So11d Maste Handi1ng........................ ... - <<
=!
-I l
Rev. 21 iv 02-15-90 APPROVED FEB 2.11990
. 'I 00CM l
LIST OF TABLES j Table Title Pace i 1-1 Radioactive Liquid Waste Sampling and Analysis Program..... 1-2 Liquid Effluent Radiation Monitors 13 Calibration Constants ..................................... 1 25 14 1 27 Dose Commitment Factors Ah ............................... 2 Radioactive Gaseous Waste Sampling and Analysis Program.... 22 23 Gaseous Effluent Radiation Monitors Calibration ~ Constants ..................................... 2 24 24 Dose Factors for Noble Gas and Daughters . . . . . . . . . . . . . . . . . . 2 34 2-5 Dose Parameters Pik"******'*"*"'****"****".2-35 2-6 Controlling Location Factors' . . . . . . . . . ; . . . . . . . . . . . . . . . . . . . . 2-36 27 Dose Parameters $R for Sector P............................ 2-37 thru 2-38 28 Dose Parameters Rgfor Se ctor Q. . . . . . . . . . . . . . . . . . . . . . . . . . . . 2-39 thru 2-46 2-9 Dose Parameters gR for Sector R............................ 2 47 thru 2-51 2 10 Dose Parameters gR for Sector A............................ 2-52 thru 2-54 2 11 Dose Parameters gR for Sector B............................ 2-55 thre 2-57 2-12 Dose Parameters gR for Sector C............................ 2-58 thru 2-62 2-13 Dose Parameters $R for Sector D............................ 2 63 thru. 2-65 2 14 Dose Parameters iR for Sector E............................ 2-66 thru 2 68 2 15 Dose Parameters gR for Sector F............................ 2 69 thru 2-73 L 2 16- Dose Parameters gR for Sector G............................ 2-73 thru 2 77 v Rev. 21 02-15 90 APPROVED FEB 211990
1 00CM. LIST OF TABLES--(Continued))- Table Title- Pace 41 Radioactive Liquid Effluent Monitoring Instrument; tion ..... 4-2 42: 1 Radioactive Liquid Effluent Monitoring Instrumentation
. Surveillance Requirements..........,...................... ~. 4-4 4-3 Radioactive Gaseous Effluent Monitoring Instrumentation.... 4 4-4 Radioactive Gaseous. Effluent Monitoring. Instrumentation-Surveillance Requirements............-...................... 4-9:
5 - 1.- Radiological. Environmental Monitoring Program .-........... 5.-2 :l 5-2 Reporting Levels for Radioactivity. Concentrations;in: Envi ronment al S ampl e s . . . . . . . . . . -. . . . . . . . . . . . . . . . . . . . . . . . . . . . . ; 5 -6 5-3 Maximum Valuesxfor the Lower Limits of Detection tLLD)...... 5-7 5-4 Radiological Environmental ~ Monitoring . Sample Locations. . . . . . 5-14 5-5 PIC Radiological Environmental Monitoring locations......... S-20 5-6 Sector'and Direction Designation for' Radiological; ) Environmental . Monitoring : Sample Location Map . . . . . . . . . . . . . . . 5 j 6-1 Operational Modes..........................................,...-6-4 , 6-2 Frequency Notation......................................... . 6-5 1
.i
'a i !
APPROVED FEB 211990-vi Rev. 21 02-15-90 l
.i 1
p , l i INTRODUCTION J The OFFSITE DOSE CALCULATION MANUAL (ODCM) is a supporting document of the. L RADIOLOGICAL EFFLUENT TECHNICAL SPECIFICATIONS _(NUREG 0472). The ODCM enumerates dose and concentration specifications,. instrument requirements, as - well; as. describes the methodology and parameters to be_'used in-the calculation of offsite doses due _ to radioactive liquid .and gaseous effluents. In order to meet release limitations .it additionally calculates ,the liquid and gaseous effluent monitoring instrumentation alarm / trip setpoints. The environmental section
~
contains a. list of-the sample locations for the radiological environmental monitoring program. The ODCM will be maintained at 'the Site for use as a document _of Specifications and acceptable methodologies and calculati-ons to be used in _. implementing the Specifications. Changes in the calculational methods or parameters will be1 , 1 incorporated into the ODCM in order to assure that'the ODCM represents the 1 present methodology. . i l 1 i , 3 q i 1 i-1 APPROVED FEB 211990 . i
+ -w-, w ,,
4
- 1.0' !.! QUID EFFLUENTS i
1.1 CONCENTRATION-SPECIFICATION'
- l.1.1 The concentration of radioactive material released from the site-(see Figure 1-2) shall be limited to the concentrationsi specified in 10 CFR Part 20,. Appendix B, Table II. column 2-'
for radionuclides other than dissolved or entrained noble . microcuries/ml. shall- gases. -For dissolved or entrained nobleconcentration total: activity.- APPLICABILITY:- At all times ACTION: 7 With the concentration of radioactive material released fromithe site ' exceeding the above limits,.immediately restore the concentration to; '
'within.the above limits.. 1 SURVEILLANCE RE0VIREMENTS [.
.The radioactivity content of.each batch of radioactive liquid waste a
~
.1 shall be-determined prior to release by sampling and analysis in J accordance with Table 1 l' ' The results of. pre-release analyses . '
shall be used with the calculational' methods in Section'l.4 to
-assure that the concentration at the point of release L is maintained within the' limits;of Specification-1.1.1.
.2 Post release analyses of. samples composited from' batch releases
~
shall be performed in accordance 'with Table- 1-1. ~ The results of the previous post-releasa! analyses shall' be:used with the calculational' -' methods 4in Section 1.4 to assure that the concentrations at the'
-point'of release.were maintained within the limits of Specification 1.1.1. a
.3 The radioactivity concentration of liquids discharged from-continuous release points:shall .be determined by~ collection and analysis. of samples in accordance with Table 1-1. The results of. ..
the analyses shall be.used:with the calculational methods in Section-1.4 to assure that'the concentrations'at the' point of release are d maintained within the l_imits of Specification 1.1'.l.- ..! s e i APPROVED FEB 211990 l-1 Rev. 21 . ( 02-15-90 , i
.[
q TABLE l-1 H
~
RADI0 ACTIVE'LIOUID WASTE SAMPLING AND ANALYSIS PROG 888 q
. Lower Limit I Minimum of Detection Liquid Release Sampling Analysis Type of Activity -(LLD) l Tvoe Freauency Freauency Analysis fuci/ml)A- '
A. Batch Waste P P Relea 'Each Batch Each Batch Principal Gamma 5x10 ': i Tanksge Emitters" ,
. i
- 1. Primary Plant Make-I-131 _1x10 '
-up Storage Tanks P M -Dissolved and _1x10 '
- 2. Radwaste Primary One; Batch /M Entrained Gases Tanks (Gamma emitters)-
P M Compositeb ' lx10 8 3_. Radwaste Primary .Each Batch H-3 Secondary Tanks .
- 4. Miscellaneous Gross Alpha lx10
Waste Condensate Monitor Tanks >
- 5. Neutralization P Q Sr-89,.Sr-90 5x10
- Sump Each Batch- Composite b ,
Fe-55 ,- 1x10-' 0 W Principal Gamma-B. Continuous 5*10-7 Releasese> # Grab Sample Composite c Emitters 1 .
- 1. Steam Generator I-131' 1x10
- f Blowdown M M -Dissolved.and
- 2. Turbine Building Grab Sample Entrained Gases . lx10 ' 1 Sump (Gamma. emitters)
- 3. Miscellaneous Waste Evaporator D M- -
Condensate
- Grab Sample Compositec H-3 1x10 ' !
- 4. Salt Water Gross Alpha 1x10 ' :
Discharge From Component Cooling Heat D Q i Exchanger Grab Sample Composite c Sr-89, Sr-90 5x10 '
- 5. Steam Cenerator .
Blowdown Bypass ** Fe-55 1x10
- I l-2 Rev. 21 t 02-15-90 APPROVED FEB 211990 j
TABLE T-1. (Continued) TABLE NOTATION a.. The LLD is the smallest concentration of radioactive material in' a sample that will be detected with 95% probability with 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 s LLD = b' E . V e 2.22 x 10" . Y e-exp: (-Aat) Where: LLD;is the "a' priori" lower limit of detection- as defined above (as microcurie per unit mass or volume), sb is the standard deviation:of the background counting rate or.of the.
~
counting rate of a blank sample. as appropriate (as counts per minute),
-E'is the counting efficiency (as. counts per transformation),
V is.the sample size (in units of mass or volume), 2.22 x 106 is the number of transformations per minute per microcurie, l Y is the fractional radiochemical yield (when applicable), a A is the radioactive. decay constant 1for the particular radionuclide, and j at is the elapsed time between -midpoint of sample collection' and -time of-counting (for plant effluents, not environmental 1 samples); The value of sb used in the calculation.of _ the LLD for a particular . measurement system shall ba 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 predicted variance;- In calculating the LLD. for a.radionuclide determined by gamma ray? spectrometry, the background should-include the. typical contributions of other radionuclides normally present in'the samples. Typical values of. E, Y Y and at should be used in the calculation. ; 1 It should be recognized that the LLD-is defined as.an a oriori (before the , fact) limit' representing the capability of the measurement system and notLai a costeriori (after the fact) limit for.a particular measurement.*
*For a more complete discussion of the LLD, and other detection limits, see the following: i (1) HASL Procedures Manual, HASL-300 (revised annually). .
(2) Currie, L. A., " Limits for Qualitative Detection and Quantitative Determination - ' Application to Radiochemistry" Anal . Chem. 40, 586-93 (1968). (3) Hartwell, J. K., "Datection Limits for Radioisotopic Counting Techniques," Atlanti Richfield Hanford Company Report ARH-2537 (June 22, 1972). 1-3 Rev. 21 02 15-90 ! R APPROVED FEB 211990
j TABLE 1 '(Continuedt i TABLE NOTATION b.- ' A composite sample;is one 'in which the ' quantity of-liquid sampled'is' { proportional to the' quantity of liquid waste discharged and in which the l method of sampling employed results_ in; a : specimen which is' repres6..tative 'of 1 the liquids released. {
- c. To be representative.of t'he quantities'and concentrations of radioactive
. materials in liquid effluents, samples shall be collected continuously in-proportion to' the rate of: flow of the effluent stream.1 Prior to: analysis,
- all samples taken for thel composite shall be thoroughly mixed in order for.
the composite. sample.to be representative of-the effluent release.- l- . d.- . A batch release is the discharge of liquid wastes of a discrete volume. Prior to sampling for-analyses, each batch shall be isolated, and'then ' thoroughly mixed, by'a method described in.the 00CM, to assure ' representative sampling. ,
- e. 'A continuous release is the discharge.of: liquid wastes of a nondiscrete ,
volume; e.g.,E from alvolume of; system that has an input' flow during. the-continuous. release. .
- f. The principal gamma emitters for which the LLD specification applies: [
exclusively are the=following radionuclides: Mn-54', Fe-59, Co-58, Co-60,. . Zn-65, Mo 99, Cs-134, Cs-137, Ce-141, and'Ce-144.- This list does not mean that bnly these nuclides are to be detected;and reported. Other peaks'which are measureable and' identifiable,' together with the above nuclides. sha11 also be identified and reported.-
- Sampling of this flow is not required if, at least once per 31 days,-
condensate monitor tank bypass. valve, SA 1415-2\"-200,'is verified locked shut.
# : Administrative controls shall provideLfor composite sampling of the continuous- releases per note b v. ice note ~ c until' January _1,1983.. .;
Continuous proportional sampling shall be in accordance with note'c:from' January 1, 1983;and all times subsequent as required by Table 1 1.
** Sampling of this flow is not required if at least once per 31 days blowdown bypass isolation valve (S21301MU618 for. Steam Generator 2E088, S21301MU619 for Steam Generator 2E089,-S31301MU618 for Steam' Generator:3E088 and S31301MU619 for Steam Generator 3E089). is , verified locked shut.
d 1-4 Rev. 21 02-15-90 , APPROVEg 759gy;g90
-1.0 LIQUID EFFLUENT 5'_(Continued)L ,
1.2 QQ11 SPECIFICATION j 1.2.1- The dase or dose commitment to an individual from radioactive 3 materials in' liquid effluents released,; from each reactor $ unit, from- the site .(see Figure 1-2) shall. be limited:- a.- During' any calendar quarter .to less than or equal to 1.5 mrem' to the total body and-to .less than or equal- to 5'r. rem to any- ! organ, and l b.- During anyLcalendar year to'less than or equal' to 3 mrem to the total body and to less than or equal:toJ10 mrem to'any - organ. r
's APPLICABILITY: At'all times. 3 ACTION: ,
a '
- a. With calculated dose from the. release.of radioactive
~
materials in' liquid ' effluents exceeding'any- of the above. , limits,;in~ lieu of:any other report required by Technical 1 Specification 6.9.1, prepare and submit ~to the Commission within 30 days, pursuant to Technical Specification:6.9.2;-a Special-Report _which identifiesLthe cause(s)-'for exceeding:- " , the limit (s) and defines the corrective actions takenuto reduce the releases:and the proposed actions-to be taken to assure that subsequent' releases will be'in compliance with Specification 1.2.1. SURVEILLANCE REOUIREMENTS.
.1 Dose Calculation. Cumulative dose contributions from liquid effluents shall be determined in accordance with. Section 1.5 at t least once per 31 days.
3
.{-
APPROVED FEB 211990
- 1-5 Rev. 21 l
02-15-90 .l I
'(
5 l 1.0- LIQUID EFFLUENTS- (Continued) 1.3- LIOUID WASTE TREATMENT SPECIFICATION 1.3.1 The liquid radwaste treatment system shall be OPERABLE.- The appropriate portions of the system shall be used to reduce the radioactive materials in liquid wastes prior to their
~
discharge'when the projected doses due to.the liquid effluent
'from the site (see Figure 1-2) when averaged over 31 days, would exceed 0.06 mrem to the total body or 0.2 mrem to.any
' organ;*
' APPLICABILITY: At all Ltimes-ACTION:-
a .- .With the liquid radwaste treatment system inoperable for more than 31 days or with radioactive liquid waste being,- discharged without-treatment and in excess of the above limits, in lieu.of any other repcrt required by Technical Specification >6.9.1, prepare and submit to the Commission-within 30 days pursuant:to Technical' Specification 6.9.2 a' Special Report which includes the-following information:;
- 1. Identification of the inoperable' equipment or subsystems--
and the reason for-inoperability,
- 2. Action (s) taken to-restore the inoperable: equipment to
-OPERABLE status, and
'3. Summary description of-action (s) taken'to prevent a recurrence.
SURVEILLANCE REOUIREMENTS l
.1 Doses due to. liquid releases 'shall be projected at least once per 31.
days, in accordance with Section 3.1.' J q
.2 The liquid radwaste treatmentisystem shall be' demonstrated OPERABLE. ;
by operating the liquid radwaste treatment; system' equipment for at i least 15-minutes at least once per 92; days;unless the liquid- ' radwaste system has been: utilized-to process radioactive liquid : effluents during the previous 92 days, j i
*Per reactor unit 1
,i
.i l
4 APPROVED FEB 211990 . 1-6 Rev. 21 02-15-90
?
'saa amorst muci.taa GRIRa&ful8 STATulu t UEITS I,2 83 x 0 oo -
A C's 4 m:.:
*\ -
rdna
+ (si .
s [,, /s e
!. aan eso.rse :
g4 I
~i
- r. ' r
' \;/ ~. ;
l
\ s'
,/
SITE B0UNDARY FOR LIOUID~ EFFLUENTS l FIGURE 1-2
REFERENCE:
TECHNICAL SPECIFICATIONS, FIGURE 5.1-4 l '- 7 Rev. 21 02-15-90 ; APPROVED FEB 211990
s
-1.0 LIQUID EFFLUENTS._.(Continu;d)' 7 1.4 Liquid Effluent Monitor Methods of Setpoint calculation,- ,
Liquid Radwaste' Effluent Line Monitors provide alarm and automatic -- termination of release' prior to exceeding the concentration limits-specified in 10CFR20, Appendix B Table.II, Column.2:at the' release point to the unrestricted area. 'To meet this. specification-and for the purpose-of implementation of specification 1.1.1_. l
-the alarm / trip ~setpoints for liquia effluent monitors and flow' :
measurement devices-are set to assure that the following equation ;
?
is satisfied:-
~
s-t
- i C*R 5 MPC,ff; F+R :(1-1}l Where:
MPC,ff = the effective effluent maximum concentration permissible limit-(pCi/ml) at the release point. Ii to the unrestricted area for:the radionuclide mixture being released, , i-1 ! F N i (1-2)_ . { ) i=1 MPC 4 i 1-8 Rev. 21 02-15-90 I APPROVED FEB 211990
+,- .
il.4L Liquid Effluent i9onitor Methods of;Setpoint Calculation ~ (Continued) , N -Where: Fj - fractional concentration of- the Lith'radionuclide as obtained by -sample analysis. - l N. - Number 'of radionuclides; identified in- sample analysis. th radionuclide-(10CFR20, App B, MPC = MPC of- the i 4 Table,11, Column 2).; C, - the setpointi-in.gCi/ml, representative ofe a radionuclide concentration for the radiation monitor w measuring the radioactivitynin the waste effluent-line-prior to dilution and subsequent release, i
-R = the permissible waste-effluent- flow: rate-at the.
radiationmonitorlocation,involume(perunittime. q in:the same units as for F. , F
= the dilution water- flow in volume per unit 1 time. The ,!
2 dilutionwater-flow (F)lis 185',000 gpm per: circ = pump j (4 total) and 17,000 gpm per saltwater pump (2 total). - , The design flowrate of. each circulating water pump. is. 205,000 gpm. The value used in the determination of F, takes into account factors such as frictional. losses, pump inefficiency, and-tlidal flow, and - 1 provides reasonable assurance,that the radioactive release k concentration is not underestimated. . i l l-9 Rev. 21 02 15-90 APPROVED FEB 21- 1990-u
4
-1.4' Liquid Effluent Monit:r Methodszof Setpoint Calculation (Continued)' l Administrative values are'used to reduce each setpoint to account for
~
n j ise potential activity in other releases. These administrative values. Jshall be periodically' reviewed based on actual' release data-(including, a for, example, any saltwater discharge of the component cooling water heat; exchanger) and revised in accordance with Unit: 2/3 Technical Specifications.- . 1.4.1 Batch ReleaseLSetpoint Determination. ,
- r i
The waste . flow 1(R)- and monitor: setpoint (c) are set _ to meet the' condition _of equation (lil) for the offective , MPC (MPC,ff) limit. .The method by which this is accomplished.is as-foilows: [,
~
STEP 1: The isotopic concent' ration for each batch tank (or, sump) to be released is obtained from:-
-the sum of the measured concentrations 11n.the tank ~(or sump)-as determi_ned by: analysis.
L . C - I C,$ + C, + C s+C+C, t p J1-3)- i '- Where: C - The total concentrationfin each batch tank. (pci/ml) 4 ICi - The sum of the measured concentrations for each - i 7 radionuclide, i, in the. gamma spectrum. (pCi/ml) 1 C = 'he Fe 55 concentration as determined in the previous q Fe quarterly composite sample. (pCi/ml) APPROVED FEB 211990 - 1-10 Rev. 21 02-15-90 .
- q x
. 'l.4.1 Batch Release Setpoint Determination (Continued) '
C,. - The: gross ~ alpha concentration' determinedLin.the . i previously. monthly compos,ite sample;- (pC1/ml). 1 1 C s
- The Sr-89 and1 Sr 90 concentrations as. determined in the ;
previous quarterly composite sample. (pCi/ml)~ ; Cg =lThe H-3'concentr tion as determined;in'the previous
- monthly composite' sample. (uCi/ml). i
\
' STEP 2: -The: effective:MPC.(MPC,ff) for each;-batch tank;(or. sump) {
'is' determined using: . ;
-l' -(1-4)
'II I '(C23jg) --(C_3fg) (C_gfq) _
g) (CFe/C)? I i)(MPC,4) .(MPC3 ) ;(MPC t
).(j (MPC,) 7.(MPC p ,)-
MPC,j, MPC 3 , MPC t , - the limiting concentrations of the: MPC p ,, MPC; appropriate radionuclide from 10CFR20,; 1 Appehdix B, Table II, Column 2.; q NOTE: For dissolved or entrained noble ' gases, th~e concentration . . shall be limited to 2.0E-4 ~pCi/ml total . activity. .l f j1 r j-1 APPROVED FEB 211990
. 1-11 Rev. 21 .i 02-15-90' y
\
-. i ,
s 1.4.1- . Batch Release'Setpoint Determination (Contirced). 1 STEP 3:: iThe radioactivity monitor'setpoint C,(pCi/ml), j may now be specified' based on the values of - - . C, I j,:F, MPC,7f and R to provide compliance
'with the limits ofL10CFR20,-Appendix B, Table II, .
. Column 2. The monitor-setpoint (cpm) is tAken
~
from the^ applicable calibration constants given , in Table 1-3 to correspond to the calculated
'l monitorconcentrationL1imit:C,-(pCi/ml).- \;
, 1. 4 .1.- 1 . RADWASTE DISCHARGE LINE MONITOR (2/3-7813)
- The value for C,, the; concentration limit at the detector,
- is' determined'by using:-
y (Rm (FL-(C,ff') (1-5) - C4RC m j 3q
;RppC RC nn <
MPC,9})+' MPCeff2 ++ MPC,ffq.
; i Where: ,
l
- n. = Number of tanks to be released, C,ff = Effective gamma isotopic, concentration at the monitor
! for the tank ' combination to be released (equal to - I .C, j for single' tank-releases). l R3 (ICg)3 + R2 (IC,j)2 + ... +Rn(fyi)n (1-6): ] R-+R2 3 + ... + R n i APPROVED FEB.211990 .;
- l-12 Rev. 21' !'
02-15 90 i e. # , - , . , _ + , . ---. -
,r-,-
n L3 .4.1.1: : RADWASTE OfSCHARGE LINE MONITOR (2/$l'%1).1 _(Continued)
- (I Cg);,;(IC g)2, etc. = Thel total gamma isotopic cencentratio' n
of first-tank, second tank, etc. (pCi/ml).
'Rg ,_ R , etc. ~=_ The effluent ficw rate from first tank,z 2
second tank, etc. ' Values of R for each ' tank are as-follows:-
- Radwaste Primary' Tanks R = 140 gpm/ pump l(x no. of pumps to be run)c Radwaste. Secondary Tanks R:=140gpm/ pump'(xno.of.pumpstobe:run)
Primary Plant Makeup' Tank R =.-160'gpm/ pump-(x no. of pumps to be'run) Condensate Monitor Tanks' R = 100.gpm/ pump'(x~no. of pumps.to'_be run)- j NOTE: Since the values of R are much smaller than. F,1the: term l (F + R); in equation (1-1). may be replaced by F. l 1 i MPC,ff3, MPCeff2, etc.. - Values of: MPC,77 from equation (1.4) for-first tank, second tank, etc. C , C , etc. - Values of C, the total concentration, from 3 2 j equation,(1-3) for the first tank, second : tank, etc. in pci/ml. ! l 1 i 1 i APPROVED FEB 211990 - ' 1-13 Rev. 21 0 02-15 90
i 1.4.l~.1- RADWASTE DISCHARGE LINE MONITOR (2/3-7811, .(Continued):...
;i are:
RW and SGM 2' 3089-2' 3088 80 89 3, 82 , 83, T 2, T3 > administrative values' used for simultaneous- releases from the Radwaste' Effluent discharge and any or all of the four Steam Generators as .well as continuous! discharges from the two. Blowdown
~
Processing Systems and the two Turbine Plant Sumps. The 7 fractions RW and SG88 2' 3089 2' 3088 3' 3089-3, B 2 ' 0 ,T' 3_2 3 '. will be assigned such that RW + SG88 2 + S089'-2 + S088-3
' + 3089-3'0 2
- 03+I2+T3 s 1.0.
l-l The 1.0 is an administrative--value used to account'for the-potential . activity released simultaneously from other release-points. This ' assures that .the total concentration. from all release. points'to the plant' discharge 1will not result ~in'a- 3
}
release'of concentrations exceeding the limits,of'10 CFR 20,. -)
- Appendix B, Table II,' Column 2 from the site.-
l l To-NOTE:- If C,1 C,ff, then no. releaseiis possible.
~
}t increase C ,, increase dilution. flow F'(by. running l more circulating water pumps.in the applicable dis- i charge structure), and/or decrease the effluent-flow rates R3 , R2 , etc. (byl throttling the combined flow as measured on 2/3FI-7643, 2FICi4055, 2FIC-4056, ;
.i 3FIC-4055 or 3FIC-4056' as appropriate) and recalculate C,using the new-F, R and equation (1-5).
If there is-no release associated with this monitor, the j 4 E monitor setpoint shouldEbe established as close to background- - as practical to prevent spurious alarms and yet assure an alarm should an inadvertent release occur, y 1-14 ev. 21 ; i 02-15-90 e t 4
~ . , w u- w 1
1.4.1.21 - NETRALIZATION SUMP DISCHARGE LINE MONITOR (batch) (2 F-7817. 3RT-7817)- The value- for' C2 or3 C ,2 the. concentration limit.at the-Unit'2 or Unit'3 detector, is determined by using: .. (B2 )(F)IC y C2 5 i (I'7)> 1
,R)(C/MPCfff)
( (8)#)EC 3 1 7g C3 -g -
. _ _ -(1-8). "
(R)(C/MPC,ff) Where: ., C, IC,g, MPC,ff
=
The' values of C ICg and.MPC,ff
!as defined in STEPS-1)~and 2) for the Neutralization Sump.
R = ~ 400;gpm/ pump x'(n' umber of sump pumps to'be run)' j l C 2
'= the instantaneous concentration at the- l
-detector.(2RT-7817) in pCi/cc- -l C
3
= the instantaneous concentration-~at the-detector l(3RT-7817) in uCi/cc
-a
~
l B2 and'B3are administrative values used to account for simultaneous releases from both SONGS 2 and SONGS 13 l neutralization sumps. The fractions =B 2 and=B3 (each. normally set to 0.05) will be assigned such that RW +1SG88 ;
+ SG89-2 + 3088-3 + SGgg,3 +- B2+B3+T2+T3 1 1.0.
APPROVED FEB 211990 1 1-15 Rev.-21 02-15 -{ a
. i
- 1.4.1.2' NEU"RALIZATION SUMP DISCHARGE LINE' MONITOR (batch)
-" (2R"-7817. 3RT-7817) (Continued) i NOTE: If C2or C 3 C43, then no release:is possible, i
~To increase C or C , increase dilution flow F (by 3
2 running more pumps), and/or decrease the effluent' flow rate R (by. throttling ~:the flow as measured on 2FI-3722. m and 3FI-3772),:and recalculate C2 r C3;using the new l
.p F,.R and equation (1-7)lor (1-8).- !
If. there is' no release' associated with this monitor,~ the monitor setpoint -should- be; established as close to background : 1 as practical to prevent spurious alarms and;yet assure an _ alarm should:.an inadvertent relesse occur. . 1.4.2 continuous- Release Setpoint Determination - I The waste flow (R) 'and ' monitor setpoint1(C,) 'are-set tb meet
~
the condition of equation:(1-1) for_ the effective MPC-;(MPC,ff) limit. The method by.which this'is accomplished:is as follows: i o STEP 1: The isotopic concentration for the continuous releases are - -,T obtained for each release. stream _(steam generator blowdown,- 3 steam generator blowdown' bypass and turbine building; sump)- ;, i from the sum-of the respective measured' concentrations as'4 ! determined by analysis: C = IC,4 + C, + Ct+Cs+C, p @ 9) t , t APPROVED FEB Z 11990 Rev. 21 i l-16 02-15-90
, ,. ,w - , , . . - , ,, ,
.~.
t 1.4.2 ContinuousRelease'Setpdintl Determination'(Continued): Where: C~ = ?Totalconeentration'(pCi/ml);
.m
~
IC g; - ' The total gamma activity (uci/ml)' associated with each radionuclide, i, in the weekly composite
= analysis'for'the release! stream.
C,-
=~ 'The _ total measured gross alpha concentration (uCi/ml)-
- determined from the previous monthlyicomposite analysis; for: the release ' stream. -
il . 1 C,p
= The- total Fe-55 concentration!(gCi/ml) as determined - ]
in the previous quarterly composite sample;for the release-stream.. C =- The total' measured:H-3 concentration :(gCi/m1 determined t from the previously monthly" composite analysis for the d l release stream. ! J C - . The total measured concentration'(pCi/ml)Lof Sr_-89 j s q and Sr-90 as determined from the previous quarterly J composite analysis for_the release stream.- - j
-1 i
STEP 2: The effective MPC (MPC,ff) for' each: release stream ~-(steam generator blowdown,-or turbine building? sump) is determi_ned-using: N 1 3 (1.- 10) ]
'If I
i ([,i/C),(C s/C) (MPC [gL() C Fe/C)
) , ((MPC,)_p , ((MPCt ,) ,-((MPC )
h) (MPC4 ) s !
'I l-17 Rev. 21 !
15-90 j APPROVED FEB 211990-j . j
'n i
- 1. 4. 2 - Continu:us Reidase Setpoint;Dettraination (Continued) .!
STEP 3: TheLsetpoiht, C,l(uC1/ml), for each continuous release l radioactivity monitor may now be specified based on the e respective values of C, g,:F, MPC,ff, and R to provide compliance.'with the limits of'10CFR20,
, . . g Appendix ~B,. Table II, Column 2. -The monitor setpoint-(cpm)
.is taken.from the applicable calibration constants given in'. Table 1-3 to correspond to the calculated. monitor limit-C,,(yC1/m1). .
e o i a J i 1 i 4 1 i l o APPROVED FEB 211990-
- 1-18 Rev. 21. l' 02-15-90 l
. -~ - -
4 1.4,2,1~ _-NEU"RALIZATION SUMP DISCHARGE LINE~ MONITORS' 'l (2R"-7817. 3 tT-7817) i The value.for C 2 r C3 ,:th'econcentration limit at the Unit 2 or Unit 3-detectorJis determined by using: I I: ~' (B2 )(F)tc (1-11). C2 5 i 4 I
.(R)(C/MPC,ff)
(1-12) (B3 )(F)tC7$i g' C3s >
-(R)(C/MPC,ff),
^' fWhere: .>
-=
C, ICg,MPCfff The; values of.C, I C,4;and MPC,7f a's'definedinSTEPS1)'and2)fforthei y
. Steam Generatur: blowdo'wn. ,
-t R' = blowdowniflow rate '(maximum.of[500 gpm)'-
Where R.is' the effluent flow rate;at the i radiation monitor as: defined in_ STEP 2.. C 2= the_ instantaneous concentration at-.the L Unit 2 detector l:(2RT-7817)Lin:pci/cc J l^ r . C the instantaneousiconcentration;at.the 3= l Unit 3' detector (3RT-7817)'in pCi/cc 4 B2 and 8 3are administrative values used to-l account for simultaneous releases from both SONGS 2 and SONGS 3 neutralization sumps. 'The fractions B2 and B3 "III , be assigned such that RW + SG88-2 + 3089-2.+ SG88-3 + S089-3
+B'+03+T2+T3 2
1 1.0 APPROVED FEB 211990 i .. 1-19 Rev. 21 < 02-15-90 l $ h.
k I
=1.4.2.1: NEU"RALIZAT10N' SUMP DISCHARGE LINE' MONITOR-(2R"-7817. 31T-7817)
(Continued)=
. r-NOTE: - If- C2 or C 3
$ I C,3; then no release is possible.
, To increase C{ or C 3 , increase dilution flow F (by-runningmore/ circulating.waterpumps),and/ordecrease-1 the effluent flow rate' R,'(by tnrottling the_ flow as measured on 2FI-3722 Land 3F1-3772), and recalculate:
C or C 3usingLtheLnew F, R and equation (1-11) or 2 (1-12). If there 'is no release; associated' with'this monitor', Lthe monitor setpoint-should be established as close to' background
- as practical; to prevent . spurious alarms 'and yet assure an alarmi should an-inadvertent release occur.
- l d
1 a: s l 2 i
!i 4
i i APPROVED FEB 211990 1 1-20 'Rev. 21 !
.v 02 15-90 {
t 5 s -
1.4.2.2: STEAM GENERATOR BLOWDOW BYPASS D SCHARGE TINE MONITORS ( (2RT-6753. 2RT-6759. 3 RT-6753. 3R"-6759) '
'The .value for C59-2, C53-2,:C59-3 or C 53-3' the concentration' limit at the Unit 2 or Unit.3 detectors', is; determined by using: i (SG88 2)(F)r C g C
59-2 5 I II'I3 (R)(C/MPC,ff)- , C53-2 < (SG8b 2)(F)E C4 vf . (3,34) (R)(C/MPC,7f). (5088~3)(F)Ei C74-
'(1-15)
C59-3 < (R)(c/MPC,ff)[* 3 J
~(SG89e3)(F)r C7y i -(1-16)_
C53-3 e - (R)(C/MPC,7f): , Where: ., C, I C,g,- MPCgff = values- of C,gt C 4 andMPC,7fT
.(as defined:in STEPS.lfand 2:above); 4 for the steam' generator; blowdown bypass. . .]
R = 200.gpm-
- Where R-is the maximum blowdown bypass; eff.lUentiflowrate j per steam generator, a
C59-2 = the instantaneou's concentration at the Unit 2 detector-(2RT-6759) in pCi/ml 1 - .1 C53-2. = the instantaneous'concentrationDat the Unit 2 detector ci (2RT-6753) intpCi/mi :!
.t the instantaneous concentration at the Unit 3 detector'
~
C = :J 59-3 (3RT-6759) in pCi/ml ~ C 53-3
- the instantaneous concentration at the Unit 3 detector
- (3RT-6753) in gCi/ml.
! APPROVED FEB 111990 1-21 Rev. 21 .c
. 02-15-90
. j
?
t q'
- l' 4. 2. 2 -' STEAM.' GENERATOR B _0WDOWN BYPASS T SCHARGE LINE! MONIIQM '
(2RT-6753; 2RT-6739. 3RT-6753. 31"-6759) _(Centinued)- RW and SG88 2' bO89-2' 3088 3' S089 3, B2 ' 03 '? 2' T3'are. , e h administrative values used for sihultaneous' releases from'the: 1 c 1
~
Radwaste Effluent discharge and any or all of.' the four Steam? l
. Generators as well as continuous-discharges from the two Blowdown I 1
- Processing Systems and thettwo Turbine Plant Sumpsa : The.
L o . [ fractions RW and.SG.88-2'. 8089-2' 3088-3' 30 89-3, B2 , B3 ,7 2,fT3 will be assigned such that~ RW- +'SG'88-2 + 3089-2 + S088-3 f
- + SG 89-3 B2+B3+T2 :+ 3 s 1.0, ;
The10isan/administrativevalueusEdtoaccount-forthe-
- potential ~ activity _ released simultaneously :from other release points. This assures that the -total' concentration, fEom all. l a
release points to the plant discharge willLnot(result in'a' ; i release of concentrations exceeding the l'imits'of 10 CFRL20,. I Appendix'B, Table II, Column 12'from the site. . y l NOTE: If C59-2, C53-2,.C59-3, _ r C53-3 i f i (for'the respective steam generator)', then.no release is possible. To increase-C59-2, C53 2, C59-3 or C53-3, increase q i dilution flow F .(by' running- more circulating, water > i' . pumps), and/or decrease .the ~' effluent! flow- rate. R (by . throttling the flow as measured on 2FIC-4055, 2FIC.4056, i - . 3FIC-4055, 3FIC-4056 or 2/3FI-7643' as-appropriate) and-recalculate C59-2, C53-2, C59-3' or C 53-3 sing lthe new" : values of:F, R and equation (1-13), (1-14)' (1-15) or , (1-16). O q i-APPROVED FEB 211990~ L l-22 Rev.-21 j I 02-15-90 F f - , . _ . _ , , _ , - t y y
f i).,,
- 1.4.2;2 STIAM GENERATOR' BLOWDOWN BYPASS D SCHARGE LINE MONITORSL ,
f 211T-6753. 2RT-6759. 3RT-6753. 3R"-6759)- (Continued); If there is noirelease. associated with this monitor,-the
~
monitor setpoint should be established as close to backgroundLas: , _ practical to prevent- spurious alarms and-yet ' assure and
~
alarm should an inadvertent release occur.
' l.4.2.3 TURBINE PLANT SUMP MONITORS'(2RT-7821. 3RT-7821i The value- for C 2 or.C3 (the concentration limit'at the=
Unit 2 or Unit 3 detector)'is determined-by-using:- 1
-(T2 )(F)tc g (1-17 ) :-
1 C25 (R)(C/MPC,ff) i(T)N)rc 3 Mg
-(1-18)1 C3~1
~i (R)(C/MPC,ff) ]
Where: .! C, IC,g , MPCfff_ = . values' of C, EC $.and MPC,ff (as defined:in_ STEPS 1 and<2/above) for.the turbine building sump; R = 50 gpm/ pump (x no.= sump pumps'to-be-run) i L 1 C 2= the instantaneous concentration at th'e Unit 2' detector (2RT-7821) in gCi/ml. l C 3= the instantaneous concentration at the. Unit 3 detector- j (3RT-7821) in~gCi/m1'. ;
- I a
i APPROVED FEB 21.1990 1-23 Rev. 21 - 02-15-90 i p
'h:
aig .
. 1.4.2.3' TURBINEPLANT_SUMPMONITORS~(2RT-7821.3RT-7821)-(Continued)
T2 and T 3are administrative values' used to account for simultaneous releases from 'othiSONGS b 2 and SONGS 3 turbine 1 pl ant - sumps'. The fractions-T 2 and T3 will be' assigned such that RW +;SG88-2 + 3089-2;+ 3088-3 + 3089-3 B 2 + B3_+ T2!
^
+T3 s 1.0. .
R NOTE: If C 2or C 1ECg (for.the< respective sump),-then 3
.no release is possible. To increase C 2or C ,-' 3 --
increase the dilution flow F '(by running more circulating. water q.
-pumps) and;recalcuiate C2or C ' 3using- the- new value -
l of 'i and equation' (1-17) or (1-18)'. -
.j If there1 1s no release associated with t'his-monitor, the 1
- j monitor-setpoint should be. established as close to background.- ]
as practical-to prevent spurious alarms.and_yet assure an: 1
'* i alarm should an inadvertent release occur.
]
l x! y 1 t AFPkOVED FEB 211990 !
-1 1-24 Rev. 21 02'15-90 5,
v-- 3-g .
-; -Table 1-3 1.iquid Effluent Radiation Monitor Calibration Constants-(pCi/cc/ cpm).
' MONITOR' Co-60 Ba-133': Cs-137-
-2RT-6753 '2.04E-8 1.95E-8' ;l 2RT-6759- 1.11E-8 1.92E-8 ,
3RT-6753 1.71E-8 1.92E-8 ,
.)
-i 2/ T 3 2.1'E-9 0 . 4E . E- -
2RT-7817 2.14E-9 -2.76E -4.74E-9 2RT-7821 '2.10E-9: -3.58E-9 :5.21E -
'3RT-7817 2.13E 9 '3.63E-9= 5;26E-9 {
3RT-7821 2.14E-9 x 3.'26E-9' 4.75E-9
.j
-1
.: j j
i i 1 i a ; (*) This table provides typical ( 20%) calibration constants for _the liquid effluent radiation monitors.
^
d 1 s APPROVED FEB '211990 1-25 Rev. 21-02-15-90 1
- 1.Si Dose Calculation fer Liquid Effluents .
The dose comitment' to an-individual from radioactive materials
]
in liquid effluents released to unrestricted areas are calculated for the purpose ~ of implementing Specification 1.1.2 -) using[the following expression.- D,
=
r[Aj, (ot) C 93f j)) (1-19)- ! Where: Ag ,. .the site related adult ingestion: dose comitment factor to the total body or an, organ, r, for each :
. identified principal gama' and: beta. emitter,.1, from Table 1-4 fin mrem /hr per Ci/ml'..
~C - the' average concentration-of!radionuclide, 1, in'the 4 .
43
. undiluted liquid effluent during time period, at).in (pCi/ml). ,
D, = the dose comitment .to thel tota'l . body or. an organ, r, from the liquid effluent for the-time . period, [j i
'at j, in mrem;
~
7j F = the near-field averageTdilutionifactbr. for C jj "during 3 the time period, at). This factor is the ratio of. L the maximum undiluted liquid waste flow during time , ti period, 6tj, to the average flow from the site j a dischar'ge structure to unrestricted receiving waters, j
- a j or 1
maximum liavid radioactive waste flow-
'l
" discharge structure exit flow- ]
at j = the length of the jth' time period over which ! are averaged for all liquid releases, C ) and.F3 4 { in hours. -t ! APPROVED FEB 211990 1-26 Rev. 21 i
~02-15-90 I Lj 1
,,~
TABLE 1-4 D0SE COMITNENT FACTOR 5*, A g' (mrem /hr per pCi/ml) Radio- Total Nuclide Body Bone Liver Thyroid Kidney Lung GI LLI H3 2.80E 1 2.80E-1 2.80E-1 2.80E-1 2.80E 1 2.80E-1 Na 24 4.57E 1 4.57E 1 4.57E-1 4.57E-1 4.57E0 4.57E 1 4.57E 1 Cr 51 5.60E0 3.30E0 1,20E0 7.04E0, 1.40E3 Mn-54 1.35E3 7.08E3 2.* 11 E3 2.17E4 Mn 56 3.15El 1.78E2 2.26E2 5.67E3 Fe-55 8.24E3 5.12E4 3.53E4 1.97E4 2.03E4 Fe 59 7.27E4 8.07E4 1.90E5 5.30E4 6.23E5 Co-57 2.36E2 1.42E2 3.60E3 Co 1.35E3 6.04E2 1.22E4 Co 60 3.83E3 1.74E3 3.26E4 Cu-64 1.01E2 2.14E2 5.40E2- 1.83E4 2n 65 2.32E5 1.61E5' 5.13E5 3.43E5 3.23E5 Br 84 9.39E-2 2.14E2 7.37E-7 Rb 88 9.49E-1 1.79E0 0.00E0 Sr-89 1.43E2 4.99E3 R.00E2 Sr-90 3.01E4 1.23E5 3.55E3 Sr 91 3.70E1 4.37E2 Sr-92 1.50E0 3.48E1 6.90E2* Y 1.62E-1 6.06E0 '
, 6.42E4 Y-91m 2.22E-3 5.72E-2 l.68E-1 Y-92 1.55E 2 5.32E 1 9.32E3 Zr 95 3.47E0 1.60El 5.12E0 8.03E0 1.62E4 Zr-97 8.14E 2 8.80E-1 1.80El 2.70E-1 5.51E4 Nb-95 5.51E-1 1.84E0 1.02E0 1.01E0 6.22E3 '
Nb 95m 5.51E-1 1.84E0 1.02E0 1.01E0 6.22E3 Nb-97 1.43E-3 1.55E 2 3.91E-3 4.56E-3 1.44El Mo-99 2.44El 1.28E2 2.90E2 2.97E2 Tc-99m 4.66E 1 1.30E 2 3.66E 2 5.56E-1 1.79E 2 2.17El ' Ru-103 4.61El 1.07E2 4.08E2 2.25E4 Ru-106 2.01E2 1.59E3 3.07E3 1.03E5 Ag-110m 8.61E2 1.57E3 1.45E3 2.85E3 5.91E5 Sn-ll3 2.20E5 Sb-124 1.10E2 2.77E2 5.23E0 6.70E 1 7.85E3 Sb-125 4.42E1 2.20E2 2.37E0 2.00E-1 2.30E4 1.94E3 Te-129m 1.48E2 9.33E2 3.48E2 3.20E2 3.89E3 4.67E3 3 Te-132 1.24E2 2.40E2 1.32E2 1.46E2 1.27E3 6.25E3 1 -131 1.79E2 2.18E2 3.12E2 1.02E5 5.36E2 8.24El I- 132 9.96E0 1.06El 2.84El 9.96E2 '4.54E1 5.35E0 1 -133 3.95El 7.46El 1.30E2 1.91E4 2.26E2 1.17E2 l 1 -134 5.40E0 5.56E0 1.51El 2.52E2 2.40El 1.32E-2 1 -135 2.24El 2.32El 6.08E1 4.01E3 9.75El 6.87El
- Source: USNRC NUREG-0133, Section 4.3.1 APPROVED FEB 211990 1-27 Rev. 21 02 15-90
TABLE 1-4 ] 00$E COMMITMENT FACTOR $*. j A' (mrem /hr per pCi/ml) l Radio- Total . Nuclide Body Bone Liver Thyroid Kidney Lung GI LLI-Cs-134 1.33E4 6.84E3' l.63E4 5.27E3 1.75E3 2.85E2 l' Cs-136 2.04E3 7.16E2 2.83E3 1.57E3 2.16E2 3.21E2 Cs 137 7.85E3 8.77E3 1.20E4 4.07E3 1.35E3 2.32E2 , Cs-138 5.94E0 6.07E0 .1.20E1 8.81E0 8.70E 1 5.11E-5 . Ba 139 2.30E 1 7.85E0 5.59E 3 5.23E 3 3.17E-3 1.39El Ba-140 1.08E2 1.65E3 2.07E0 7.00E 1 1.18E0 3.39E3 La 140 2.10E 1 1.58E0 8.00E-1 5.84E4 , Ce 141 2.60E 1 3.43E0 2.32E0 1.08E0 8.86E3 : 1 Ce-143 4.94E 2 6.00E 1 4.47E-2 2.00E 1 1.67E4 Ce 144 9.59E0 1.99E2 7.47El 4.43El 6.04E4 ; Nd 147 2.74E 1 3.96E0 4.58E0 2.68E0 2.20E4 - W -187 2.68E0 9.16E0 7.66E0 2.51E3 Np 239 1.92E-3 3.53E 2 3.47E-3 1.08E-2 7.13E2 , i f . .. .
- Source: USNRC NVREG 0133, Section 4.3.1 APPROVED FE8 211999 1-28 Rev. 21 02-15-90 m.. .. ._ _ -_ __ _
i .
- 1.6 Representative Sampling ;
Prior to sampling of a batch release, each batch shall be thoroughly mixed to assure representative sampling. The methodology for mixing and sampling is described in l S0123-I!!. 5.11.23, ' Units 2/3 Liouid Effluent Release Permit" and S0123 l!! 5.2.23 " Units 2/3 Liquid Effluent Sample Collection". i j kt l-f5
- -3081c. man APPROVED FEB 2.1 1990 ;
l 29 Rev. 21 . 02-15-90
2.0 SASE005 (FFLUENTS 2.1 DOSE RATE SPECIFICATION 2.1.1 The dose rate in unrestricted areas due to radioactive materials released in gaseous effluents from the site (see Figure 2-2) shall be limited to the following:
- a. For noble gases: Less than.or equal to 500 mrem /yr to the total body and less.than or equal to 3000-mrem /yr to the skin, and-
- b. For all radioiodines, tritium and for all radioactive materials in particulate form with half lives greater than 8 days: Less than or equalito 1500 mrem /yr to any organ.
APPLICABILITY: At all times ACTION: With dose rate (s) exceeding the above limits, immediately decrease the release rate to within the above' limit (s). SURVEILLANCE REOUIREMENTS
.1 The dose rate due to noble gases in gaseous effluents shall b.e determined to be within the above limits in accordance with Section 2.7.'
.2 The dose rate due to radiciodines, tritium and radioactive materials in particulate from with half ilves greater than.
8 days in gaseous effluents shall be determined to be within the above limits in accordance with Section.2.7 by obtaining representative samples and performing analyses in accordance with the sampling and analysis' program specified in Table 2-1. 1 s
' APPROVED FEB 211990 2-1 Rev. 21 02-15-90
]
TABLE 2-1 RADI0 ACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS PROGRAM , Lower Limit Minimum of Detection Gaseous Release Sampling Analysis Type (LLD) Type Frequency Frequency Activity Analysis (uCi/ml)a A. Waste Gas P P Storage Tank Each Tank Each Tank Principal Gamma Emitters 9 1x10 ' Grab Samole P P Principal Gamma Emitters 9 1x10 B. Containment Purge Each Pargeb ,c Each Purge b 42 inch H3 1x10-' 8 inch Mb gb Principal Gamma Emitters 9 1x10** Grab Sample H3 1x10 ' Mb Mb Principal Gamma Emitters 9 1x10
- C. 1. Condenser Grab Evacuation Samole System H3 1x10**
- 2. Plant Vent Stack Wb ,e wb D. All Release Types Continuousf Wd 1 131 1x10 22 as listed in B Sampler Charcoal ano C above. Sample 1-133 1x10***
Continuousf Wd Principal Gamma Emitters 9 1x10***' Sampler Particulate (1 131, Others) Samole Continuousf M Gross Alpha lx10'** Sampler Composite Particulate Samole Continuousf Q Sr 89, Sr 90 lx10 ** Sampler Composite Particulate Samole E Continuousf Noble Gas Noble Gases 1x10 Monitor Monitor Gross Beta or Gamma E. Incinerated Oilh Each batchi Each Batchi Principal Gamma Emitters 9 5x10 7 Grab Samole
. 2-2 Rev. 21 APPROVED FEB 211940 02-15 90 J
t IABLE 2-1 (Continuedi .l TABLE NOTATION ,
- a. The LLD is the smallest concentration of radioactive material in a sample that will be detected with 95% probability with 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 s LLD - b Ee V e 2.22 x 10"
- Y e exp (-Aat) {
'r Where:
LLOisthe"apriori'lowerlimitofdetectionasdefinedabove(as ! microcurie per unit mass or volume), [ I sb is the standard deviation of the background counting rate or of the counting rate of a blank sample as appropriate (as counts per minute), y F L E is the counting efficiency (as counts per transformation), , p V is the sample size (in units of mass or volume), :i [ < 2.22 x 106 is the number of transformations per minute per microcurie, , I Y is the fractional radiochemical yield (when applicable), [ l A is the radioactive decay constant for the particular radionuclide, and at is the elapsed time between midpoint of sample collection and time of ; counting (for plant effluents, not environmental samples). ; The value of sb used in the calculation of the LLD for a particular . measurement system shall 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.. predicted variance, in calculating the LLO for a radionuclide determined by gamma ray _ spectrometry, the background should include the typical contributions of-other radionuclides normally present in the samples. Typical values of E, V Y and at should be used in the calculation, it should be recognized that the LLD is defined as an A oriori (before the fact) limit representing the capability of the measurement system and not as; A costeriori (after the fact) limit for a particular measurement.*
*For a more complete discussion of the LLD, and other detection limits, see the -)
following: , (1) HASL Procedures Manual, HASL-300 (revised annually). . (2) Currie, L. A., " Limits for Qualitative Detection and Quantitative Determination - ! 1 Application to Radiochemistry" Anal . Chem. 40,58693(1968). (3)Hartwell,J.K.,"DetectionLimitsforRadioisotopicCountingTechniques,"Atlanticj ' Richfield Hanford Company Report ARH-2537 (June 22, 1972).' 2-3 Rev. 21 l 02-15 90 j APPROVED FEB 211990 .
1 TABLE 2 1 (Continued) ; 1 I TABLE NOTATION , l
- b. Analyses shall also be perforned following shutdown, startup, or a THERMAL i POWER change exceeding 15 percent of the RATED THERMAL POWER within a 1-hour period.
- c. Tritium grab samples shall be taken at least once per 24 hours when the i
refueling canal is flooded. !
- d. Samples shall be changed at least once per 7 days and analy'ses shall be completed within 48 hours after changing (or after removal from sampler).
Sampling shall also be performed at least once per 24 hours for. at least 7 ! days following each shutdown, startup, or a' THERMAL POWER change exceeding 15-percent of RATED THERMAL POWER in I hour and analyses.shall be completed
- within 48 hours of. changing. When samples collected for 24 hours are !
analyzed, the corresponding LLDs may be increased by a factor of -10.. j
- e. Tritium grab samples shall be taken at least one per 7 days from the '
ventilation exhaust from the spent fuel- pool area, whenever spent fuel is in r the spent fuel pool.
- f. The ratio of the sample flow rate to the sampled' stream flow rate shall be known for the time period covered by each dos'e'or dose rate calculation made in accordance with Specifications 2.1, 2.2, 2.3. .
- g. The principal gamma emitters for which the LLO specification applies exclusively are the following radionuclides: Kr-87, Kr-88, Xe 133, Xe-133m, Xe 135, and Xe-138 for gaseous emissions and Mn 54, Fe 59,-Co 58, 00 60, Zn- '
65, Mo-99, Cs-134, Ce 141 and Ce 144 for particulate emissions. This list does not mean that only these nuclides are to be detected and reported. Other : peaks which are measurable and identifiable,* together with_the above nuclides, < shall also be identified and reported.
- h. Incinerated oil may be discharged at points other than the plant vent stack.
Release shall te accounted for based on pre-release grab sample data,
- i. Samples for incinerated oil releases shall be collected from representative samples of filtered oil in liquid form. '
t V 2-4 Rev. 21 .i 02 15 90
- APPROVED FEB 211990
I 2.2 DOSE - NOBLE GASES i SPECIFICATION i 2.2.1 The air dose due to noble gases released in gaseous ; effluents, from each reactor unit, from the site (see Figure 2 2) shall be limited to the following: _
- a. During any calendar quarter: Less than'or equal to 5 mrad for gamma radiation and less than or equal'to 10 mrad for beta radiation and, 1
- b. During any calendar year: Less than or equal to 10 mrad for i j
gamma radiation and less than or equal to 20 mrad for beta radiation. l APPLICABILITY: At all times , ACTION:
- a. With calculated air dose from radioactive noble gases in gaseous effluents exceeding any of the above limits, in lieu ;
of any other report required by Technical Specification 6.9.1, prepare and submit to the Commission within 30 days, : pursuant to Technical Specification 6,9.2, a Special Report , which. identifies the cause(s) for exceeding the limit (s) and : defines the corrective actions taken to reduce releases and- 'l ' the proposed corrective actions-to be taken to assure that subsequent releases will be in compliance with Specifica-tion 2.2.1. s SURVEILLANCE RE0VIREMENTS ,
.1 Dose Calculations Cumulative dose contributions.for the current-calendar quarter and current calendar year shall be determined in accordance with Section 2.8 at least once per 31 days.-
l ' l e I F l i i 25 Rev. 21= 02-15-90 ,- APPROVED FEB 211990 ;
- 1 2.3 DOSE - RADIOI0 DINES. RADIOACTIVE MATERIALS'IN PARTICULATE FORM AND TRITIUM SPECIFICATION -
2.3.1 The dose to an individual _from tritium, radioiodines and radioactive materials in particulate form with half-lives ; greater than 8 days in gaseous effluents released from each I reactor unit, from the site:(see Figure 2 2) shall be limited i to the following:-
~
- a. During any calendar. quarter: Less than or equal to 7.5 mrem-to_any organ and,
- b. During any calendar year: jLessthanorequalto15mremto any organ. .
3
- c. Less than 0.1% of the limits of 2.3.1 (a) and (b) as a result' )
of burning contaminated oil. APPLICABILITY: At all times ACTION: ) i
- a. With the calculated dose'from the release of tritium, i radiciodines, and radioactive materials in particulate form, !
with half lives greater than 8 days, in gaseous effluents-
, exceeding any of the above_ limits, in'11eu of any other-
- report required by Technical Specification 6.9.1, prepare and submit to the Commission within.30 days pursuant to Technical ,
Specification 6.9.2 a Special Report which identifies the ; cause(s).for exceeding the limit and. defines the corrective actions taken to reduce; releases and the proposed actions to i be ta~ ken to assure that sucsequent releases will be in compliance with Specif; cation 2.3.1. > 1 SURVEILLANCE REOUIREMENTS
.1 Dose Calculations Cumulative ccso contributions for the current '
calendar quarter and current calendar year shall be determined in accordance with Section 2.S rd least. once per 31 days, i l t i i I. l l 2 f< Rev. 21 02 15 90 l ME%MED FEB 211990 i 6 ,, ,
2.4 GASEOUS RADWASTE TREATMENT f SPECIFICATION' l 1 2.4.1 The GASEOUS RADWASTE TREATMENT SYSTEM and the I VENTILATION EXHAU!T TREATMENT SYSTEM shall be OPERABLE. I The appropriate portions of the GASEOUS RADWASTE TREATMENT SYSTEM shall be used to reduce radioactive i materials in gaseous-waste prior to.their discharge ; when the projected gaseous effluent air doses due to gaseous effluent releases from the site (see Figure 2- l 2), when averaged over 31 days, would exceed 0.2 mrad l for gamma radiation and 0.4 mrad for beta radiation. l The appropriate portions of the VENTILATION EXHAUST : TREATMENT SYSTEM shall be used to reduce. radioactive ? materials in gaseous waste prior to their discharge when the projected doses due to gaseous effluent ' releases from the site (see Figure 2 2) when averaged i over 31 days would e ceed 0.3 mrem to any organ.* ; APPLICABILITY: At all times ' ACTION:
- a. With the GASEOUS RADWASTE TREATMENT SYSTEM and/or the VENTILATION EXHAUST TREATMENT SYSTEM inoperable for ,
more than 31 days or.with gastous waste being , discharged without treatment and in excess of the above limits, in lieu of any other report required by ' Technical Specification 6.9.1, prepare and submit to. i the Commission within 30 days,. pursuant to Technical ; Specification 6.9.2, a Special. Report which includes i the following information: ; Identification of the inoperable ~ equipment or 1. subsystems and the reason for inoperability, . 4
- 2. Action (s) taken to restore'the inoperable f equipment to OPERABLE status, and ;
- 3. Summary description of action (s) taken to prevent I a recurrence. ,
SURVEILLANCE REOUIREMENTS
.1 Doses due to gaseous releases from the site shall be projected at least once per 31 days, in accordance with Section 3.2.
.2 The GASEOUS RADWASTE TREATMENT. SYSTEM and VENTILATION EXHAUST l TREATMENT SYSTEM shall be demonstrated OPERABLE by operating :
the GASEOUS RADWASTE TREATMENT SYSTEM equipment and VENTILATION EXHAUST TREATMENT SYSTEM equipment for at.least-15 : minutes, at least once per 92 days unless the appropriate r system has been utilized to. process radioactive gaseous ' effluents during the previous 92 days. i
*These doses are per reactor unit.
2-7 Rev. 21 : 02 15-90 APPROVED FEB 211990 ;
r 2.5 TOTAL DOSE : SPECIFICATION . I 2.5.1 The dose or dose commitment to any member of the l public, due to releases of radioactivity and radiation, i from uranium fuel cycle sources shall be limited to ! less than or equal to 25 mrem to the total body or any i organ (except the thyroid, which shall be limited to l 1ess than or equal to 75 mrem) over 12 consecutive : months. j APPLICABILITY: At all times /
. ACTION: ;
- a. With the calculated dosec from the release of radioactive materials in liquid or gaseous effluents , i exceeding twice the limits of Specifications 1.2.1.a. !
1.2.1.b. 2.2.1.a.'2,2.1.b, 2.3.1.a or 2.3.1.b in lieu .i of any other report required by Specification 6.9.1, j i prepare and submit a Special Report to.the Director, Nuclear Reactor Regulation, U.S. Nuclear Regulatory l Commission, Washington, D.C. 20555, within 30 days, which defines the corrective action to.be taken to , i reduce subsequent releases to prevent recurrence of exceeding.the limits of Specification 2.5.1. This ! Special Report shall include an analysis which j estimates the radiation exposure (dose) to a member of 1 the public from uranium fuel cycle sources-(including ,' all effluent pathways and direct radiation) for a 12-consecutive. month period that includes the release (s) { covered by this report. If the estimated dose (s) . exceeds the limits of Specification 2.5.1', and if the i release condition resulting in violation of 40 CFR 190 ' has not already been corrected, the Special Report ' shall include a request for a variance in accordance with the provisions of 40 CFR 190 and including the [ specified information of paragraph 190.11(b). Submittal of the report is considered a timely request, i and a variance is granted until' staff action on the. i request is complete. The variance only relates to the ; limits of 40 CFR 190, and does not apply in any way to the requirements for dose limitation of 10 CFR Part 20, ! as addressed elsewhere in this 00CM. > L I SURVEILLANCE RE0VIREMENTS : i
.1 Dose Calculations Cumulative dose contributions from liquid- -
' and gaseous effluents shall be determined in accordance with ! surveillance 1.2.1.1, 2.2.1.1, and 2.3.1.1.. U .i e a 2-8 Rev. 21 02 15-90 APPROVED FEf3 211990 i
-~ - - -- -- -
X* .
...iF "-'"~ ~
~~ . ,% ,, . = .7 --
- , * ':J:: *..*".::::::::-
* ::"*:7."~;".':7.:7***
f~g . . . . - f,,,,
- t. .
y .....- - l{
; , . . . . N., , , . . . .,
/
4 l4
/
5 N ~
- .5.EP I
K 1 _.. - - _. 8.g
,_ 2_ .
.f i.
2 7 _ _..
.x..,_ _
. . . . .- cc -- -- ;
/ ___
- W.f-y g,- . ;he ,/ -- - -
y.-----
. . .]// ;t 7,
~W o,
3"~~
~.
~
.- o i c
_f.%pr --lb.~,-- t
~'.
p .
}I My 7,: }ym, ;p.>
.. 1 g __ =: ~. . _. ._=r:. --}
x
-Q D~ .v,
;i , t , . . . - -
l ({,'- _ (h. gW _ 7 _N;9..', j g b ~#L. l . j s . 4
\ t
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7 x / . N / N- t__._. / .. FIGURE 2-2 APPROYED FFB 211990
REFERENCE:
- TECliNICAL SPECIFICATIONS, . FIGURE 5.1-3 Rev. 21 2-9 02-15-90' e
.w
._...u.-
~~
i i 2.0 GASE0US EFFLUENTS ; 1 2.6 Methods of Calculation for amanous Effluent Monitor Setnoints ! Administrative values are used to reduce each setpoint to account for the potential activity inLother releases. .These administrative t values shall' be periodically reviewed based ,on actual release data , and revised a's required.
~
\
.2.6.1 ' PLANT VENT STACK - 2/3RT 7808, 2RT 7865-1, 3RT 7865-1 ]
2/3RT 7808 - plant Vent Stack Monitor 2.6.1.1 e For the purpose of implementation of Specification 2.1.1, s t'he alarm setpoint level for noble gas monitors is based , 3 on the. gaseous effluent flow rate and the meteorological dispersion factor. Total Body . The concentration at the detector corresponding to a 500 mrem /yr total body dose rate at the exclus' ion area boundary is determined by:. C (0.45)(2120 m)sec)(500 mrem /yr)(10m*/cc) (2-1) det = (Flow rate, cfm) (X/Q, sec/m*)[I (K'g, mrem /vr) ( _1g_ )) s 1 pC1/m .C tot ; Where: C = the instantaneous concentration at the detector, det t uti/cc ; D 0.45 = an administrative value used to account for potential activith from.other haseous release. pathways l 2 10 Rev. 21 ' 02-15-90 l l: ; AIrPROVED FEB 211990- , j
- . , = h .h o,
2.6.1 PLANT VENT STACK . 2 3RT.7808, 2RT.7865 1, 3RT 7865 1 (Continued) j th j K,
-- the total body dose conversion factor for the i gemma emitting noble gas, mrem /yr per uCi/ms, !
from Table 2 4 .) th noble gas, as determined C 4
= _ Concentration of the i by sample analysis, uti/cc l l
-C . Total concentration of noble gases, as determined tot
- by sample analysis,-( Ci/cc) = ICg :
i t ( Flow Rate = the plant vent flow rate, cfm '
= 83,000 cfm/ fan (x no. of fans to be:run) _.<
+ 17,500 cfm (laundry facility) f 2120 = conversion constant, cfm per m*/sec total body dose rate-limit,.as specified by 500 mrem /yr =
Specification 2.1.1.a X/Q = historical annual average dispersion factor, sec/m*
- 4.8E-6 secfms
- na The concentration at the detector corresponding to a
- . 3000 mrem /yr skin dose rate at ths exclusion area boundary a L
L is determined by: (0".45)(2120 m'/ c C
) (3000 mrem /yr) (10" m*/cc)
C (2-2)- det = (Flow rate, cfm) (X/Q, sec/m')[I(L g + 1.1Mg , mrem /vr)( _qt_.)] I i pC1/m* C to't 2-11 Rev.- 21 02-15 90 APPROVED FEB 211990 l \' ,
i 7 2.6.1 PLANT VENT SiACK'- 2/3RT.7808, 2RT 7865-1. 3RT-7865 1- (Continued)' 4 I where:- Lj = Skin' Dose Conversion Factor for the i th noble gas, mrem /yr per pC1/mb from Table 2 4' f M 4
=
- Air Dose Conversion Factor for the i th noble i
gas, mrem /yr per pCi/ms, from Table 2 4 - , ! 1.1 = ' Conversion factor to convert gamrna air dose to skin dose 3000 mrem /yr - skin dose rate limit, as specified by ! Specification 2.1.1.a Other values in equation (2 2) are defined in equation (2-1). - l The smaller of the values.of C det from equations-(2-1) or f (2-2) is to be used in the determination of the maximum .
- permissible monitor alar'm setpoint (cpm), as follows
- l 1
The maximum permissible alarm setpoint (cpm)_is determined l using the calibration constant for 2/3RT-7808 given in Table 2-3. The maximum permissibis alarm setpoint is the value !
" cpm" corresponding to the concentration, Cdet (the smaller value from equation (2-1) or (2-2)). The calibration constant i used is based on Kr-85 or on' Xe-133, whichever yields a lower ;
detection efficiency (the largest value in terms of pCi/cc/ cpm). The alarm setpoint will be maintained at a value not greater ; than the maximum permissible alarm setpoint. 2-12 Rev.'21 -[ 02-15-90 { APPROVED FEB 211990 r. l
2.6.1 PLANT VENT STACK 2/3RT 7808, 2RT-78651, 3RT 78651 (Continued). If there is no release associated with this monitor, the monitor setpoint should be established as close as practical to background to prevent spurious alarms and yet assure an alarm should inadvertent release occur. 2.6.1.2 2RT-7865-1 and 3RT-7865-1 Wide Ranoe Gas Monitors The maximum release rate (gCi/sec) for Wide Range Gas Monitors _Isdeterminedbyconvertingtheconcentrationat the detector, Cdet (uC1/cc) to an equivalent release rate in uti/sec, as follows: A max . 1Cdet, uti/ccif flowrate. cc/sec) (2 3) 2 Where: A = _the maximum permissible release rate, Ci/sec , max C det
- the smaller of the values.of Cdet obtained from equations (2 1) or (2 2)?.
Flow Rate - flowrate,pc/sec
= (3.917 x 10 cc/sec per fan) (number of fans to be run) + 8.259 x 10' cc/sec (laundry facility) 2- a factor.to compensate for the split flow between Unit 2 and Unit _3 plant vent stackt f
.The release rate setpoint will not be set greater than the maximum release rate determined above,'when this monitor is being used to meet the requirements of Specification 2.1.1.1.
t 2 13 Rev. 21 02-15 90 ; APPROVED FEB 211990 , s
. I
2.6.1 PLANT VENT STACK'. 2/3RT-7808 2RT.7665-1, 3RT-7865 1 (Continued). If there is no release associated with this monitor, the j monitor setpoint should be established as close as practical to - background to prevent spurious alarms and yet assure an alarm .l t should an inadvertent release occur. ; 1 2.6.2 CONDENSER EVACUATION SYSTEM 2RT 7818, 2RT-7870-1, 3RT-7818 or .: 3RT-7870 1 i i 2.6.2.1 2RT-7818 and 3RT 7818 Condenser Air Eiector Monitors l For the purpose of implementation of Specification 2.1.1, the. j alarm setpoint level for noble gas monitors is based on the gas-eous effluent flow rate and the meteorological dispersion factor, j The concentration at the detect'or corresponding to a total body dose rate of 500 mrem /yr at the exclusion area boundary is determined by using: Total Body C (0,1)(0,5)(2120 mhsec)(500 mrem /yr)(10m*/cc) (2 4)~ det = (Flow rate, cfm) (X/Q, sec/ms)[E (K 4
, mrem /vr) ( lj.,))
i uCi/m* C tot 4 The concentration at the detectsr corresponding to a 3000 mrem /yr skin dose. rate at the exclusion area boundary is determined by using: Skin (0.1)(0,5)(2120 m hsec) (3000 mrem /yr) (10 m*/cc) C (2-4a) det = (Flow rate, cfm) (X/Q, sec/ms)(z(L; + 1.lM g , mrem /vr)( li )] j i uti/m' C tot i 1 2-14 Rev. 21 02-15 90 . APPR01!ED FEB 21 loon
2,6.2. CONDENSER EVACUATION SYSTEM 2RT 7818, 2RT 7870-1, 3RT-7818' or 3RT 7870 1- (Continued) Where: 0.1 is an administrative value uted to account for potential activity from other gaseous release pathways. 0.5 is an administrative value used to account for releases from both SONGS 2 and SONGS'3 condenser air ejectors simultaneously. Other parameters are.specified in 2.6.1.1, above. from equations (2 4) or The smaller of the values Cdet (2 4a) is to be used in determining the maximam permissible monitor alarm setpoint-(cpm), as follows:. The maximum permissible alarm setting (cpm) is-determined by'using the calibration. constant for ~ the corresponding Condenser Evacuation System Monitor' given. in Table 2 3. The maximum permissible: alarm setpoint is the cpm value corresponding to the-concentration. Cdet, (smaller _ value from equation (2-4) or (2 4a)). The calibration constant used is based on Kr-85 or on Xe-133, whichever yields a lower detection efficiency (higher value in terms of uti/cc/ cpm). The alarm setpoint will not be set greater than .the maximum permissible alarm setting determined above. 2 15 Rev. 21' 02 15 90
, APPROVED FEB 211990 ,
f'
- 2. 6. 2 . CONDENSER EVACUATION SYSTEM . 2RT-7818, 2RT-7870 1, 3RT-7818 or 1 3RT-7870 1 (Continued) j If there is no release associated with this monitor, !
I the monitor'setpoint should be established as close as l practical to background to prevent spurious alarms yet assure an alarm should an inadvertent release. occur. o 2.6.2.2 2RT-7870-1 and 3RT-7870-1 Wide Ranae Gas Monitors i The maximum release-rate.(uC1/sec) for Wide Range Gas Monitor is determined by converting the concentration at the detector, C det (uti/cc), to an equivalent release rate in pCi/sec. A,f,, x = (Cdet, uti/cc) (flow rate, cc/sec) , Where: A,,x = the maximum permissible release rate, pCi/sec
. Cdet = the smaller value of Cdet, as obtained-from equations (2-4) and (2-4a) flow rate of the condenser air ejector, cc/sec flow rate
= 4.719ES cc/sec-(conservatively assumed.as design ;
flowrate) If there is no release associated with this monitor, the I monitor setpoint should be established as close as practical to background to prevent spurious alarms yet assure an alarm ,
~
should an inadvertent release occur. L i 2-16 Rev. 21 02-15-90 , APPROVED FEB 2119o0
2.6.3 CONTAINMENT PURGE - 2RT-7828, 3RT-7828, 2RT 7865, 3RT 7865 : For the purpose of implementation of Specification 2.1.1, the alarm setpoint level for noble gas monitors is based on l the gaseous effluent flow rate and the meteorological dispersion factor. 3 l The concentration at the detector corresponding to a total body dose rate of 500 mrem /yr at the exclusion boundary is determined by using: $ Total Body f C (0.45)(P2)(2120 ,9[,c)(500 f mrem /yr)(10"m'/cc) (2 6). det2 =(Flow rate, cfm) (X/Q, sec/m*)[I (K g , mrem /vr) ( lj_ ))- i uti/m* C tot C (0.45)(Ps)(2120 mhec)(500 mrem /yr)(10m*/cc) (2-7)- ' det3 =(Flow rate, cfm) (X/Q, sec/m')[r (K 9
, mrem /vr) ( lj_-)) .
i pCi/m' C tot The concentration at the detector corresponding to a 3000 mrem /yr skin dose rate at the exclusion area boundary is determined by using:
!!.k_i.D f
, C (0.45)(P2)(2120 ,$ / ec ) (3000 mrem /yr) (10" m*/cc) (2 6a det2 =(Flow rate, cfm) (X/Q,. sec/ms)[I(L 3 + 1.lM3 , mrem /vr)( lj_ )) o i sci/m" C tot C (0.45)(P3)(2120 mhec)-(3000 mrem /yr)(10Im*/cc)' (2-7a ' det3 =(Flow rate, cfm) (X/Q, sec/m*)[E(L g + 1 lMg , mrem /vr)(-lj_ )) i pCi/m' C tot j l 2-17 Rev. 21 02-15-90 APPROVED FEB 21 1000. U. .
2.6.3 CONTAINMENT PURGE 2RT-782E, 3RT.7828, 2RT 7865, 3RT-7865 i (Continued) where: . C det2 The instantaneous concentration of the Unit 2 detector in uCi/cc. r Cdet3 - The instantaneous concentration of the Unit 3 detector in pCi/cc. 0.45 is an administrative values used to account for potential activity from-other gaseous release pathways. t P, and Pa are administrative values used to account for simultaneous purges of both SONGS 2 and SONGS 3. The fractions P 'and P will be assigned such that P: + P s 1.0. j i Flow rate - the observed maximum flowrate in> cfm from 'the [ unit spei monitor 7828.. Default values will ; be the fol w a conservative measured flows-
- 50,000 cfm full purge
= 3,000 cfm mini purge- i the above values replace the smaller design'
- flowrates. ;
Other parameters are as specified in 2.6.1.1 above. The smaller of the values of maximum permissible Cdet2 from j equation (2-6) or (2-6a) and Cdet3 from equations (2 7). or (2-7a) is to be used in determining the maximum permissible' monitor alarm setpoints, i 2-18 Rev. 21 i 02 15 90 . ; APPROVED FEB 2 1 1990-
2.6.3 CONTAINMENT PURGE-o 2RT-7828, 3RT-7828.-2RT 7865, 3RT 7865 (Continued) 2.6.3.1 Maximum, permissible Alarm Settina (RT-78651 The maximum permissible alarm setting for the Wide Range Gas. Monitor expressed as a maximum release rate-(uC1/sec) is-determined by converting the concentration at.the detector,' det ( Ci/cc),to an equivalent release rate;in uti/sec. C A,,x = (Cdet, pCi/cc) (flow rate, cc/sec)- Where: A,,x = the' maximum permissible release rate Cdet the smaller value of Cdet, as btained from , l equation (2 6, 2 6a) for. Unit 2 or'.(2-7, 2 7a). , f for Unit'3.. . flow rate = flow rate,- cc/sec j
= either.l.416E6 cc/sec for mini purge o'r !
2.360E7 cc/sec for main purge, y
.2 Maximum permissible Alarm Settina (2RT 7828)
The maximum permissible alarm setting for:2RT-7828 is in l uCi/cc and is the smaller of the values of Cdet2 (uCi/ce) from equations-(2-6) and (2-6a). If there is no release associated with this monitor, the monitor setpoint should be established as-close as practical to background to prevent spurious alarms yet assure an alarm should an inadvertent release occur. 2-19 Rev. 21 02 15-90 t APPROVED FEB 211990
2.6.4 . WASTE GAS HEADER - 3 7865, 2/3RT-7808 for the purpose of Specification 2.1.1, the alarm setpoint-level for noble gas monitors is_ based on-the gaseous effluent flow rate and the meteorological dispersion factor. SInce.the waste gas header discharges to the plant, vent stack, either 'I 3RT-7865 or 2/3RT-7808 may be used to monitor waste gas header , releases'. L The concentration at the detector corresponding to a total body , dose rate of 500 mrem /yr or a skin dose rate of 3000 mrem /yr.at t the exclusion area boundary is' determined by using equations (2 1) j or (2-2) with sample ~ concentration (C4
) and (Ctot) being obtained. i from the waste gas decay tank to be released. :
v The smaller of the values of maximum permissible concentration (Cdet) from equation (2-1) or (2-2) is to be used'in determining the maximum permissible monitor alarm setpoint. , 2/1RT-7808 The maximum permissible alarm setting.-(cpm) is determined by using the calibration constant for plant vent stack i I monitor 7808 given in Table 2 3. The maximum permissible setpoint is the cpm value corresponding Ji.the concentra-tion C det, (smaller value from equation (2-1) or-(2-2)). 1 i 2-20 Rev. 21' 02-15-90 APPROVED FEB.211990-
, .,. , w
2.6.4 WASTE GAS HEADER - 307865, 2/3RT 7808 (Continued) l 3RT-7865 . The maximum permissible alarm setting is expressed as a j maximum release rate. ( Ci/sec) and is determined by
~
converting the concentration at.the detector, Cdet' to an equivalent release rate in pCi/see by , equation (2 8). . A gx '(2 8)- __Ltdet. uti/cc) (flowrate. 2- cc/sec) s Where: ,. A the maximum permissible release rate, gCi/sec det Cdet = the smaller value of Cdet, as obtained from j
- equation (2 1) or (2-2).- l flowrate = flowrate, cc/sec
= 7'83E7 cc/sec for 2 fan operation or 3.92E7 cc/sec for 1 fan operation ,
2 = corrects for 3-7865 viewing only 1/2'the i total Plant Vent Stack Flow.
.1 A release from the waste gas header is not possible if:
f
),Cdet (2-9)'
(I Cj ) ( r f 2-21 Rev. 21 - 02 15 90 , APPROVED FE8 811990 o 9
l 2.6.4 WASTE GAS HEADER 7865,.2/3RT-7808 (Continued) j 2.6.4.1 (Continued) 1 Where: ICj total concentration in waste. i i ' gas holdup tank to be released i f= waste gas header effluent flow rate - cfm h F= plant vent stack flowrate:in efm (166,000 cfm 1 for 2 fan operation; 83,000 for-1 fan operation) + 17,500 cfm-(laundry facility)1 Cdet = smaller of the values of Cdet from ; equation (2-1) or (2-2) with Cg being 4-obtained from the waste gas holdup tank to be released If a release is not possible, adjust the waste gas header flow by determining.the maximum permissible waste gas header effluent flow rate corresponding to the Vent Stack Monitor setpoint in accordance with the following: f 4 (0.9)(Cdet)(F) (2-10) . EC 3 i Where: f= waste gas header effluent flow rate (cfm) F= plant vent stack. flow rate (cfm) used in equation (2-1)~or (2-2) : 2-22 Rev. 21 02-15 , APPROVED FEB 211990 ! i
2.6.4 WASTE GAS HEADER - 3 7865, 2/3RT-7808 (Continued) 2.'6.4.1 (Continued) C from det = the smaller of the value of Cdet equation (2-1) or (2-2) EC4= total gamma activity -(pCi/cc)'of the i j waste gas holdup tank to be released, ; as determined from the pre-release sample analysis. j The 0.9 is an administrative' value to account for the pctential-activity from other releases in the same release' pathway.
-i t
1
?
k t k [
?
2-23 Rev. 21 02-15 '
, APPROVED FEB 211990-
. .~ .
Table 2 3(*) f Saseous Effluent Radiation Monitor Calibration Constants : (pCi/cc/ cpm) i MONITOR Kr-85 Xe-133 I 2/3RT-7808C 3.90E-8 4.62E-8 2RT 7818A- 4.27E-8 6.63E 8 2RT-78188 7.31E-5 2.07E 5 3RT-7818A 3.73E 8 5.09E ' 3RT 7818B 9.31E 5 2.21E-5 i i i (a)This table provides typical (120%) calibration-constants for the gaseous effluent radiation monitors.
- L 2-24 Rev. 21 02-15-90 ,
t
~
i APPROVED' FEB 211990
.- q 2.7 aassous Effluent Dona Rate ,
The methodology used for the purpose of implementation 'of { Specification 2.1.1 for the dose rate above background to an individual in an unrestricted area is calculated' l by using the following expressions' ' .2,7.1 fpR NOBLE GASES:' { E i (X/Q) O g (2-11) DjB " *i - ] i b s
"* Ili + I'IH i) 70 i (2-12)-
i i Where: ; i j D TB
= ' total body dose rate,in. unrestricted areas'due I
to ra,dioactive materials released in gaseous effluents, in. mrem /yr ,. b s
= skin dose rate in unrestricted areas due to radioactive materials ~ released in gaseous effluents, in mrem /yr l.
- t Kj = the total body dose factor due to gamma j emissions for each identified noble' gas !
radionuelide,.i, in mrem /yr per Ci/m'- 1 from. Table 2-4. . r 2-25 'Rev. 21 02-15-90 APPROVED. FEB P,11990 -
1 1 2.7.1- FOR NOBLE GASES: (Continued) Lj = skin' dose factor'due to the beta emissions for each identified noble gas radionuclide,.1, in- -!
. mrem /yr per pCi/m' from' Table 2-4 Mg :
theEair dose--factor due to' gamma emisdf 1s for; each' identified noble gas radionuclide,,i,:i s 1 mrad /yr per pCi/m' from Table 2-4. f i
~(conversion constant of 1'.1 mrem / mrad convertsL t air dose to. skin dose.)
h4. = the release rate of radionuclide', i, in gaseous effluents-in'pci/sec
~
TX7QT - 4'.8E sec/m*. The maximum annual-I averageJatmospheric dispersion factor for= j
~any. sector or distance at or:-beyond1the.-
q
. unrestricted area b'oundary.
j 2.7.2 FOR ALL'RADIOI0 DINES. TRITIUM AND FOR ALL-RADI0 ACTIVE l MATERIALS IN PARTICULATE FORM WITH HALF LIVES GREATER' I THAN-EIGHT DAYJ:. ! D o I [I (P ik=N k )l i ) (2-13) i k l Where: b n
= organ dose rate-in unrestricted areas due to- ;
radioactive materials released-in gaseous j effluents, in mrem /yr , 2-26 Rev. 21 02-15-90 ! J APPROVED .FFR 9 31000;
i . Y
~
2.7.2 FOR Alf RAD 1010DLNES. "RITiljM'AND FOR ALL RADIOACTIVE ! MATERLALS IN PAR"lCULA"E F0 lM WITH HALF tlVES GREATER: THAN EIGHT DAYS: (Continued) 4 hj _ = the release rate'of.radionuclide, i, in-- gaseous- effluents in pti/sec lPik = the dose parameter for.radionuclide, i, for pathway, k, from Table _2-3 for the inhalation pathway in mrem /yr per pCi/mt : The dose. factors.'are based on the critical individual organLand the. child age group. W k
= the highest calculated annual average dispersion parameter for> estimating the' dose to_an individual lat or beyond the
' unrestricted area boundary for pathway k.~
= 4.8E-6_ sec/mCfor theLinhalation pathway.
- i The location' is' the unrestricted area .in the j
!LW, sector.
= .4.3E-8 m'* for the food and ground plane pathways. The location-is the unrestricted area'in the E sector.
i
- j i
i 2-27 Rev. 21 j 15-90 APPR0"ED. FEB 21 1990
2.8 Gaseous Effluent' Dose Calculation-2.8.1 DOSE FROM NOBLE GASES IN GASEOUS EFFLUENTS-The air dose,in unrestricted areas due to noble gases released in gaseous effluents is calculated using thei ! following expressions:
.c 2.8.1.I' For historical meteoroloav:
D'. -- 3.17x10 E Mg [ (X/Q)-Q4 ) (2-14). 7 j l D-g 3.17x10 I N 4[ (X/Q)-Q4) (2-15)- Where: J D -- the- total projected gamat air dose from gaseous-' 7 i. effluents,. in mrad
~
D
- the total projected beta air dose from gaseous; effluents, in mrad ,
1 3.17x10 = (inverse seconds per year) Mj = the air dose factor due'toLgamma emissions ~for-each identified' noble gas radionuclide, i, in mrad /yr per uti/m* from TableL2-4 ! Ng = the air dose due t'o beta emissions for each identified noble-gas radionuclide, i, in mrad /yr per pCi/m' from Table 2-4 l i 2-28 Rev. 21 ! 02-15-90 -j PPROVED FEB 211990 ; u
- 2. 8. 2 .1 ' For h'istorical meteroloov:1 (Contihued) l
=;
TT/QT = 4.8E-6. sec/m*. . The maximum annual average d a atmospheric dispersion factor for anyl sector or= distance at or beyond the unrestricted area bound ary. -- - Q- = the amount of: noble' gas' radionuclide, :1[ j , released in . gaseous'. effluents in gCi . l . u
. 2 . 8 '.1. 2 For meteoroloav concurrent with'releasa: }
c ; o
=.1.14x10r M j (I (at) (X/Q)), Q43')]! (2-16);
0,, q . Dj ,- = 1.14x10~'I Nj [I (at j;(X/Q)3, Q43)] (2kl7) t . - -Where: L D - the-total gammaiair' dose from1 gaseous-g effluents'in sectort e, ~in mrad-o 0,, =Lthe total beta air. dose from gaseous , effluents in sector e, in mrad
~
j f'
= the air-dose factor due to gamma emissions-M
- for each identified noble lgast radionuclide,.
~
i, in' mrad /h per pCi/m' from Table 2-4 p N
= the: air dose factor.due to beta emissions. ;
for each identified nobi'e' gas. radio'nuclide, i,- in mrad /yr; per pCi/m* from' Tabi'e 2-4. L 2-29 Rev.'21' ' 02-15-90 ; v Ik { cy VED FEBL219990- d
, 4 4 , -
o
n .
, q ;,y 4 4 L
u 2.8.1.2- For meteoroloav~ concurrent with release? f(Continued)? at j = the_. length of the-jth time period over which,(X/Q)3, and h33 are averaged.for-gaseous releases in hours * (X/Q)3, = the' atmospheric-dispersion factor _for q-1 time period'atj at exclusion _ boundary location; in sector a determined-by concurrent 1 4
, -meteorology,_in sec/m* ]' i h-43
' -the average release-rate of radionuclide,-
-i, in gaseous effluents 'during time period, at , in pCi/sec 3
j 2.8.2 D251 FROM TRITIUM!-RADI0 IODINES AND-RADI0 ACTIVE MATERIALS IN PARTICULATE FORM WITH HALF LIVES. GREATER THAN 8 DAYS IN GASEOUS EFFLUENTS
~
The dose to an- individual from ' tritium, .radioiodines i and. radioactive-materials sin_p' articulate' form with ,i half lives greater:than eight. days _in gaseous effluents released to unrestricted areas -is~ calculated using the : following expressions: 2.8.2.1 For historical meteoroloav: ; j D o - 3.17x10" I [(IR ikNk) Oi ] (2-18) l i k , 1 i l. 2-30 Rev. 21 02-15-90 APPROVED FEB 211990 l 4 i # . - ;
2.8.2.1 For historical meteoroloov: .(Continued) Where:- D o
-:the totaliprojected dose from gaseous effluents to an individual, in mrem Og .= . the amount of each:radionuclide,'i, '
o , , (tritium,radioiodine,-radioactive : material in particulate form with half -
.j
-lives greater than eight days), rel. eased' in gaseous effluents in'uci-
= the' sum of allipathways k'for radionuclide, IR(W:
k g k j i,- of the:R ,g W product in mrem /yrlper gCi/sec. The I R kWk..value for each? -; k e radionuclide, i, is-given-in Table 2-6;
. The given is the maximum I R ikkI0I"II W
k- { locations-andiis based'on the most-3 restrictive age groups ~. j I
- R ik = the dose factor for each identified' radionuclide, i, for. pathway k1(for the.
inhalation pathway,in mrem /yr.per gCi/m*~ l li' and for the food and ground plane pathways in m' - mrem /yr per pCi/sec) at the . i- controlling location. The Rik s for-each: controlling location for,each age group:are. : given in Tables.2-7.thru 2-16. 1 t i I 2-31 Rev. 21 02-15 -i
"'**VED FEB 2 9999 ,
2.8.2.1 For historical meteoroloav:_ '(Continued)' W - the annual- average dispersion parameter forf k estimating the dose to an individualLatlthe. ; controlling location'for pathway _k.
- (X/Q) for the inhalation pathwayf ni sec/ms. ,;
E -The TX7QT for each controlling' location is , a
'given in Tables 2-7 thru 2-16.- J i
?
- III/TJforthefoodandground'planepathways q
l in m. The TD7QT for each controlling q location are' given .in iables 2-7 thru.2-.16. 2.8.2.2 For meteoroloov ' concurrent with releases:
'f
. 1- m n . D, - 1.14'x 10 ".E 2 j [(at){(Rike)Mjkh[(Oi j )] .- (2- 19) - [ , l Where: D, = the total ' annual dose' from gaseous: effluents to an r individual in sector e in mrem. i l-L l- -: at j - the length'of the j th . period over which Wjke and-
.Qjj are averaged for gaseous released in hours Q - the average release. rate of radionuclide, i,'in- ,
43 gaseous ~ effluents during time period at3 'n"gCi/sec- i , 2-32 Rev. 21 02-15-90 [ APPROVED FEB $ 11990: ,
.f
_.L ?
~
2.8.2.2 For meteoroloav concurrent with releases:1 (Continued) 1,-
.Rike = the" dose factor for each identified radionuclide for pathway k for. sector # (for the inhalation- i pathway in mrem /yr per gCi/m' and for the- ,
l
- ~ food and ground plane" pathways in m'. mrem /yr per t
Ci/sec) at'the controlling location. .,A listingloff
~Rik:f rLthe controlling locations'in.each landward:
j sector, for.each group is'givenjin Tables 2-7 thru l 6 . . . .
- t 2 - 16 ~. The eLis determined by the concurrent. j t
meteorology. < W jke = ,the dispersion paramiter for the time period aty t for each pathway k for calculating the dose to an.
-individual at.the controlling locationiin-sectorLe; using concurrent = meteorological conditionc.. i
- (X/Q) for the inhalation pathway in sec/m'~
i
= (0/Q)'for?the food and ground plane pathways lin m-*
. L k j [ t n 2-33 Rev. 21 : 02-15-90 APPROVED FEB 211990
t
' ~
*EABiE2-4 D05E FACTORS.FOR' NOBLE GASES AND DAUGHTERS **
Total- Body Dose _ Sk'i n 'Do s e - 4 Gamma Air Dose. Beta Air Dose . Factor K j Factor L,. 4 Factor M Factor N j 9 Radio- (mrem /yr- (mrem /yr! l .(mrad /yr :(mrad /yt Nuclide per pCi/m*) .per-uCi/m*). f - per pCi/m*).; per pCi/m*) d Kr-85m-; 1.17E3* 1.46E3-f 'l'.23E3: -l.97E3 l Kr-85 -1.61E1L 1.34E3 1.72E1- 1.95E3' ! t Kr-87 5'.92E3 9.73E3 , 6.17E3 1.03E4-
. Kr 88 1.47E4 2.37E3 .l.52E4 '2.93E3 Xe-131m 9.15El 4.76E2 1.56E2- '1.11E3 :
Xe-133m 2.51E2 9.94E2' 3.27E2 1.48E3' Xe-133 2.94E2 .3.06E2 3~.53E2 1.05E3 Xe-135m 3.12E3 7.11E2 3.36E3 -7.39E2 . Xe-135 1.81E3 1.86E3 1.92E3 2.46E3 Xe 138- 8.'83E3 4.13E3 '9.21E3 4'. 7 5 E3 - L Ar-41 8.84E3 2.69E3 9.30E3 '3.28E3 i , 4 f
*1.17E3-= 1.17 x 10*
** source: USNRC Reg. Guide 1.109, Table B-1 2-34 Rev. 21 ,
02-15-90 L APPROVED FEB 211990 ,
-k TABLE 2-5 ,
DOSE PARAMETER g P* CHILD AGE GROUP CRITICAL ORGAN Inhalation Pathway' InhalationPathway l(mrem /yr per pCi/m ) Radionuclide- (mrem /yr-per Ci/m ). Radionuclide H-3 1 lE3 I -131 1.6E7 . Cr-51 1.7E4 I -132 1.9E5 j il.6E6 1 -133' 3.8E6
. Mn-54 00-57 5~.1E5 I:-134 - 5 lE4 Co-58 1.lE6 I -135 7.9E5 }
Co-60 7.lE6- Cs-~134 1.0E6 Sr-89 2.2E6 Cs-136 1.7E5 ; Sr-90 1.0E8 Cs :7 9. lES-Zr-95 2.2E6 'Ba-240 - 1.7E6 Nb,95 , 6.lE5 Ce-l'41 5.4E5 '
~
Te-129m 1.8E6 Ce-144 1.2E7' e l l .r 3 t s
- Source: USNRC NUREG-0133, Section 5.2.1.1 2-35 Rev. 21 02-15-90 o
APPROVED FEB 211990 t i
.- ~
, , .- n, .
TABLE 2-6 i 4 CONTROLLING LOCATION FACTORS [.RjkNk-' Radionuclide mrem /yr per pCi/sec.- 1 H -3 9.62E 4 t Cr 1.58E-2' o Mn-54 4.02E0 Co-57. 9.95E-1 Co 58 -l'16E0 '- Co-60L 6.14E1 Sr-89 4.34El- - Sr-90 '1. 82 E3 -. .~ e Zr-95 l'.66E0 , 6.81E0 4 Nb-95 Te-129m 4.90E0 t Cs-134 3.36El i Cs-136 ~5.73E-1 1
-Cs-137 3.08E1 - fi Ba 140- 2.28E-l' -
Ce-141 5.74E : Ce-144- '1.68El-1 131 11~97El I -133 - 2.82E0- '
.I -135 5.92E
- UN ID ' 3. 50E0 '-
i
% i e
e d
- i.
. . i. Footnote: These values to be used in manual calculations:are the maximum j rR N for all locations based on the most restrictive age l group. k ik k 'l 2-36 Rev. 21 02-15-90 , ! '\ APPROVED FEB 21:1990 l i
.t- - -_ . . . - . _ _
y ; 1 TABLE 2 4 DOSE PARAMETER Rj FOR SECTOR P S' e Page 1 of 2 Pathway'= Surf Beach . Distance- = 0.4 miles - - X/Q = 1.8E-6 sec/m* D/Q = 8.2E-9_m 1 Infant Child Teen: Adult Inhala. Food & Inhal a- Food &~ Inhala- Food & Inhala- Food & = Radio- tion Ground tion Ground tion: Ground- tion Ground Nuclide Pathway Pathway Pathway Pathway Pathway Pathway Pathway Pcthway \q H -3 1.2El 5.1El -0 8.7E1; -! Cr-'51 1.lEl 2.2E4 1.2E2 1.lE5 2.3E2 3.2E5-Mn-54 4.5E2 . 6_. 6 E6 2.7E3 -3.2E7- 5.3E3 9.5E7 Co-57: l1.4E2' l.6E6- 1.3E3 7.9E6 2.2E3 2.3E7 Co 58' 3.6E2 1.8E6 3.8E3- -8.7E6- 7.3E3- 2.6E7 , Co-60' . 1.0E3- 1.0E8 ' l.0E4- 4.9E8. 2.0E4 1.5E9 Sr-89 6.2E3 1.0E2 ^1'.8E4 4.9E2 2.1E4 1.5E3 ' . Sr-90 - 1.lE6- 4.4E6f :6.8E6 ' Zr-95 -0 : 6.3E2- 'l.2E6 6.0E3 5.8E6 1.0E4 1.7E7 . Nb-95 Te-129m-3.8E2 5.2E2 6.6E5 9.4E4 3.9E3 2.1E3
.3.1E6 4.5E5 7.lE3 2.5E3:
9.4ES! 1;.3E6 l ' Cs-134 1.lE4 3.3E7- 4.5E4 1.6E8 5.8E4- '4.7E8 < Cs-136 1.8E3 7.2E5- 7.8E3 3.4E6 1.0E4 1.0E7 7 Cs 137 -0 : 8.6E3 4.9E7 3.4E4, 2.4E8 4.3E4- 7;1E8 s Ba-140 - 7.7E2- 9.9E4~ 9.2E3 4.7E5 1.5E4 1.4E6 Ce-141 5 .9E2, .6.6E4 5.1E3 3.lE5 -8.2E3- 9.4E5' ,_ Ce-144 :4.0E3 3.3E5 3.5E4 1.6E6- 5.6E4_ 4 ~. 8E6 I -131 -02 1.7E5- 8.3E4 5.9E5- 3.9E5' 8.2ES- 1.2E6 I .133 , 4.0E4: 1.2E4 1.2E5- 5.6E4 1.5E5 1.7E5
.I '135 i 8.2E3 1.2E4 2.5E4' 5.8E4 3.1E4 1.7E5 UN-ID ! 1.2E3 3.6E6 5.4E3 1.7E7 7.1E3' 5.lE7 '
; .t d
l \ i s. L Inhalation Pathway, units = Food & Ground Pathway, units = (a, r vr) 2-37 Rev. 21 ' . 02-15-90 l APPROVED FEB 211990 ' l.
E TABLE 2-7 DOSE PARAMETER Rj'FOR SECTOR P 4 Page 2 of 2 Pathway,= Former Nixon Estate.(no. garden). Distance = 2.8 miles ' !. %X/Q = l~.2E-7 sec/m' .0/Q = 3.4E-10 m-Infant Child,.. Teen . Adult Inhala-- Food.& Inhala- Food &- Inhal a- Food & Inhal a- Food'& Radio- tion Ground- tion Ground tion . Ground tion- ' Ground-Pathway ' Pathway Pathway Pathway Pathway: Pathway Pathway' Pathway Nuclide 1
\. g '.
H -3 6.5E2L -0=. 1.lE3- - l'.3E31 - 1.3E3 =\ 0-- 3.6E2 t3.7E6. 1.lE3 3.7E6 3.0E3 ' '3.7E6 3.3E3" 3.7E6 Cr-51 ' Mn-54 L2.5E4 1.lE9 4.3E4 -1;1E9- -6.7E4 1.IE9 7.7E4 1.1E9-i
.C0-57 4.9E3 :2.7E8- :1.3E4 2.7E8 3.1E4 i 2.7E8' 3.1E4 2.7E8.
3.4E4
~
3.0E8 9.5E4 - 3.0E8 1.lES: 3.0E8 j Co 1.1E4 3.0E8 Co 3.2E4 1.7E10 '9.6E4. L1.7E10. 2.6E5 ,1.7E10-. '2.8E5 1.7E10' Sr-89 4.0E5 1.7E4 6.0ES. 1.7E4 4.3E5 1.' 7 E4 ! 3.0E5. 1 : 7E4. I
.Sr-90 4.lE7 1.0E8 1.lE8 - .9.9E7 ;
Zr 95- - 2.2E4 2.0E8 6.lE4 2.0E8 1.5E5 2.0E8 1.5E5 2.0E8 Nb-95 1.3E4 1.lE8 3.7E4 1.1E8 9.7E4 1.1E8~ .1.0E5 1.1E8 1.6E7 5.2E4. 1.6El 3.7E4 1.6E7- J Te-129m 3.2E4 1.6E7 5.0E4 Cs-134 7.0E5 5.5E9- 1.0E6 5.5E9 - 'l .1E6 ' 5.5E9 '8.5ES 5.5E9 Cs-136 1.3E5 1.2E8 1.7E5 1.2E8 1.9E5' l.2E8- L1.5E5 '1.2E8L Cs-137- 6.lES 8.2E9 8.3E5 8. 2 E9. .8.5E5- :8.2E9 6.2E5 8.2E9' Ba-140 5.6E4 'l .6E7 ' 7.4E4 -1.6E7 2.3E5' l.6E7 2.2E51 1.6E7-Ce-141 2.2E4 1.1E7 5.7E4- 1.lE7 1.3E5 .1.1E7 - ~ 1'.2E51 1.1E7 " 1.5E5 5.6E7 3.9E5 .5.6E7 8.6E5 5.6E7? 8.2E5; 5.6E7-Ce-144 I -131 1.5E7 1.4E7 1.6E7' l.4E7 1.5E7. :1.4E7 1 2E7 1.4E7 : I -133 3.6E6 2.0E6 3.8E6 2.0E6 12.9E6- 2.0E6 >212E67 2.0E6 ' I -135 7.0E5 2.0E6 7.9E5 2.0E6 6.2E5 2.0E6 4.5ES 2.056 UN-ID 6.3E4 6.0E8 1.lE5 6.0E8 1.3E5' 6.0E8 ' l '. 0E 5 . 6.0E8-V . L . W Inhalation Pathway, units = "C /
~
I* # "} Food & Ground Pathway, units
/ c 2-38 Rev. 21 02-15-90 APPROVED FEB 211990,
- g, --
,- - -, ,- . - . , . . - .ma
, i TABLE 2-8 D0SE PARAMETER Ri FOR SECTOR Q Page 1 of 8
=
Pathway . San Onofre Mgbil Homes Distance = l'.3 miles X/Q = 7.4E-7 sec/m 0/0 3.6E-9 m** Infant Child Teen- Adult'- i - Inhala-- Food & Inhala- Food & Inhala- Food &'- Inhal a- - Food & Radi o'- tion Ground tion Ground tion? Ground ~ tion ~Groand. l . Nuclide. Pathway Pathway Pathway Pathway Pathway = Pathway Pathway: ' Pathway i H'-3 6.5E2 1.lE3. - 0- 1. 3 E3 - '0-1.3E3 ' Cr 3;6E2 3.7E6 1.1E3 3.7E6 3.0E3 3.7E6 3.3E3 3.7E6 Mn-54 2.5E4 1.lE9 4.3E4- 1.1E9 6.7E4 1.1E9 7.7E4 1.lE9- -.'L i Co-57' 4.9E3~ 2 718 1.3E4 .2.7E8~ 3.1E4 ' 2.7E8 3.1E4 2.7E8 Y i Co-58 -1.lE4 3.0E8 3.4E4 3.0E8 9.5E4 3.0E8 l' lE5 -3.0E8 Co-60 3.2E4 1.7E10 9.6E4 1.7E10. 2.6E5' 'l.7E10 .2 8E5 . 1.7E10. ; Sr-89 J4.0E5 'I.7E4 6.0E5 - 1.' 7 E4 4;3E5- 1.7E4 3.0E5 - 1.7E4 ! Sr-90 4 lE7 1.0E8 1.1E8 ~ - 9.9E7- . -0 . Zr-95 2.2E4 2.0E8 6.lE4 2.0E8 1.5E5 2.0E8 1.5E5 2.0E8- . Nb 95 1 1.3E4 1.1E8 3.7E4 1.lE8 9.7E4- 1.1E8. 1.0E5 1.~ 1 E8 - o Te-129m 3.2E4 1.6E7- 5.0E4 -1,6E7 5.2E4 1.6E7 3.7E4' 1. 6 E7 -
'Cs-134- -7.0E5- 5.5E9 '1.0E6 5.5E9 1.1E6 5.5E9~ 8.5E5 5.5E9i Cs-136 1.3E5 1.2E8 1.7E5 1.2E8 'l.9ES 1.2E8- 1.5E5 1.2E8 Cs-137 6.lE5 8.2E9 8.3E5 8.2E9 .8.5E5 8.2E9 6.2E5 1 8.2E9~
Ea-140 5.6E4 1.6E7 7.4E4- .1 ~. 6 E7 2.3E5- 1.6E7 2.2E5 :1.6E7 . , Ce-141 2.2E4 1.lE7 :5.7E4 1.1E7 1;3E5- 1.1E7 1.2E5 . l'.1 E7 I Ce-144 1.5E5 5'6E7
. 3.9E5 5.6E7 '8.6E5i 5.6E7. 8.2E5 ' -
5.6E7 . l I -131 1.5E7 1.4E7 :1.6E7 1.4E7- l'.5E7
-1.4E7- 1.2E7 1.4E7 I -133 3.6E6- 2.0E6 3.8E6 2.0E6 2.9E6 2.0E6- 2.2E6 2.0E6 1 -135 ~7.0E5 2.0E6 7.915 2.0E6 6.2E5 2.0E6 -- 4. 5E5 2.0E6 UN-ID 6.3E4 6.0E8 1.1E5 6.0E8 1.3E5 6.0E8 . l .~ 0 E 5 - 6.0E8
- i i
j. i Inhalation Pathway, units 5" p Food & Ground Pathway, units = (m rem /vr) 2-39 Rev. 21 02-15-90 APPROVED FEB 21 1990 . - v .
4 _
; i ; \
TABLE 2-8 D05E: PARAMETER-Rj FOR SECTOR Q Page 2 of 8 i
. Pathway.=StatePark0{ficeTrailer Distance = 0.'6 miles _
L X/Q. 2.2E-6 sec/m D/Q = 1.2E-8 m-' Infant Child Teen Adult
'I nh al a- - Food'& Inhala-.- Food & Inhala-. Food &- Inhala- Food & !
Radio- tion Ground tion Ground tioni Ground tion' Ground. 1 '
- Nuclide- Pathway Pathway Pathway Pathway Pathway. Pathway Pathway l- Pathway
~ y i H"-3-' 10 - . 5.8E1 . Cr-51 - '
- 11.5E2 2.1 E5 ' i Mn - ,-0 ;
- 3.5E3 L6.3E7: ;
Co-57 - - 1.4E3 l'. 6 E7" Co -0 ' - - . -- 4. 9 E3 1.7E7 4
.Co-60 _1.3E4 9.8E8
-Sr-89 0-- -1.4E4 9.9E2
- Sr ~ 4'.5E6 . -0 p Zr-95 - :6.9E3- - 1.1E7: 4 Nb-95. - ' 4 8E3. ^6.2E6m
.Te-129m - : 1.7E3- 9,0E51 2 Cs-134 , - : -
3.9E4 3.1E8- 1 Cs-136 - 6.7E3 6.9E6-Cs-137 2.8E4 -4.7E8 Ba-140 - .-0; : 1.0E4: 9.4ES- 1 Ce-141 - .5.5E3- 6.2E5 Ce-144 . - 3.7E4' !3.2E6 I -131 - : 5.4E5 7.9ES I -133 0- 9.8E4 1.1 ES - I.-135~ '2.0E4 - 1.2E5
- . UN-ID- ' 4.7E3 3.4E7 I
s 7
~
1: b Inhalation Pathway, units =
- y
!" i Food & Ground Pathway, units I* " V"I
, 2-40 Rev. 21 . 02-15-90 APPROVED FEB 211990 n - e ,
TABLE 2-8 DOSE PARAMETER ~Rj FOR SECTOR Q Pathwav = Surf.' Beach Guard Shack Distance = 0.7 miles X/h=1.8E-06sec/m* D/Q --9.9E-09 m * -i Infant Child ~ Teen Adult Food & Inhala- -Food &: Inhala- Food & Inhal a--- Food.& Inhsl a-Radio- tion -Ground tion -Ground tion ~ Ground- tion Ground-Pathway Pathway Pathway Pathway Pathway Pathway Pathway. Pathway t Nuclide. l
~
H -3 ' c '7.2E1 . Cr-51 -0 . ' 1.9E2. 2.7E5- : i Mn-54 -0 . . 4.4E3 7.9E7L Co-57 -0 . < - -0 + 1.8E3 2.0E7 Co 0- 6.1E3- 2.2E7 - Co-60 ~ 10 -- 1.6E4 11.2E9' t Sr-89 -0 . 1.7E4- -1.2E3 .
-Sr-90 ' -5.7E6 -
- Zr-95 0- '0- - .8.6E3: 1.4E7' Nb 95 e0- 5.9E3' 7.8E6' Te-129m 1 . .?. 1E3: 1.1E6 Cs-134 4.8E4 3.9E8 Cs-136 : 8.4E3- 8.6E6 il Cs-137 - '0-
- ' 0-
- : 13.5E4 5'. 9E8 -
.-0--
Ba-140 - -0 1.2E4 '1.2E6-Ce-141 . 6.9E3 L7.8E5 Ce-144 . - 4.7E4- 4.0E6 I -131 . 6.8ES- 9.8E5; I'-133- 1.2E5 -1.4E5-I -135 - 2.6E4 1.4E5 UN-ID 0- 5.9E3- 4.3E7: i l Inhalation Pathway, units - yr I* "I Food & Ground Pathway, units l 2-41 Rev.~ 21 02-15-90 . l l APPROVED FEB 211990 4
a TABLE 2-8 D0SE PARARETER Rj FOR SECTOR Q g Page 4 of 8 l
. Pathway' Enlisted Beach. Check-In Dis 15ance - l.4 miles X/Q - 6.8E-7 sec/m* -l D/Q j 3.2E-9 m 4 L - Infant Child- Teen . Adult Inhala- -Food & Inhala- -Food &- InhalaI Food:&i- Inhala- l Food &
Radio ' t1on Ground- tion: ' Ground tion Ground- tion- . Ground' l , Nuclide Pathway Pathway Pathway Pathway Pathway Pathway Pathway Pathway i H -3 - -01 "2.9E2 j Cr-51 - - 7.6E2 ; 1.lE6 ! LMn-54 - . - 1.8E4 ! 3.2E8~ Co-57 : - - ; -- 7.2E3 7.8E7 Co-58 ' 2.4E4- 8.7E7 L Co-60 0- - 6.5E4' 4.9E9. Sr-89 '0-
. ~0' 0- 6.9E4 - 4 '. 9 E3 -
Sr-90 : 2.3E7 - JZr-95 -0 . -3.4E4- 5.7E7 Nb-95 - 2.4E4 3.lE7 . , Te-129m 8.3E3 4.5E6 ;
'Cs-134 - ~ 1.9E5 .l.6E9 Cs'-136 3. 3 E4,- 3.4E7 Cs-137' 1.4E5 2.3E9 1 Ba-140 1 : 5.0E4 .4.7E6 Ce- 141-. : 2.7E4' 3.lE6-Ce-144 1.9E5 1.6E7 -i I -131- - 2.7E6- 3.9E6 I -133 - 4.9ES. 5.6E5
, I -135 1.0E5 5.8E5 UN-ID 2.4E4 1.7E8 ; i f' 1 i i-e Inhalation Pathway,. units ,5# Food & Ground Pathway, units I*2 II*"'*#V"I . pC1/sec l 2-42 Rev. 21 02-15L90 APPROVED FEB 211990 l 1 g, 9 ,, -- ,
.i--
s 4 g -; TABLE 2-8 ~ L D0SE PARAMETER Rj FOR. SECTOR Q Page 5 of 8. j; [ l 0 Pathway =~ Sheep (Meat)*' Distance = 1.6 miles-X/Q -.5.6E-7 sec/m D/Q = 2.6E-9 m i
' Infant- Child Teen Adult
. Inhala- - Food & Inhala- Food & Inhala- Food & Inhala- Food:&
' Ground: tion Radio- tion: Ground tion Ground tion Ground .
Nuclide Pathway: Pathway Pathway Pathway Pathway Pathway Pathway- Pathway
, l
- -. l l - H. -0 .- 1.5E0 - 1.2E0 7.0E0 . 2.1 E0 . !
Cr-51 1 5.1El 1.0E2 1.8E1 2.6E4' l L - 4.3E2 7.6E6 l Mn-54 7.8E2 l'. 4 E3 : L Co - ' 0-
- 4.7E3 8.1E3 '1.7E2=
1.9E6-00 -0 ' 9.7E3- .2.0E4 5.9E2- 2.1E6 Co-60 - 3.7E4 ' 0-7.3E4 1.6E3 1.2E8 ; L Sr-89 5.0E4 2.6E4= 1.7E3 3.1E4 j i Sr . 1.0E6 8.1E5 : 5.5E5 - 1.3E6 Zr-95 ~ 0- 6.3E4 11.1E5 8.3E2 1.6E6: i
. Nb-95 2.4E5 -4'. 5ES : 5;7E2i 1.6E6 -j Te-129m - 6.0E5- 4.5E5' 2.0E2 ~6.5E5 1
-0 .
Cs-134 1.4E5 1.2E5 ^4.7E3 3.8E7 l Cs-136 - 5.1E3 4.3E3 8.1E2: 8.3E5 ; L l Cs-137 - 1.3E5 19.5E4 3.4E3- 5.7E7 i Ba-140 5.1E3 4.3E3. 1.2E3 1.2E5 -: l Ce-141 1.5E3 '2.4E3 L6.6E2 7.9E4- ,l Ce-144 1.8E4 : 3.0E4- 4.5E3 4.3E5 7.0E5
],
- l. I 131 6.6E5 4.4E5- 6.6E4 I 4133 1.6E-2 8.7E 1.2E4 1.3E4 I -135 1.1E-18 -6.4E-19 2.5E3 1.4E4 j
l. j s VN-ID 1.1E5 9.5E4 5.7E2 4.2E6 l 1 l a f l InhalationPathway, units =*C$/
\
I* " "I Food & Ground Pathway, units $ I i 2-43 Rev. 21 02-15-90 APPROVED FEB 211990 , L
TABLE 2-8' DOSE PARAMETER.R[ FOR SECTOR Q-Page 6 of 8 1 Pathway = S. C. Res-W Garden Distance'= 4.1 miles D/Q --4.1E-10 m-* i
- X/Q = 1.2E-07 sec/m' Infant , Child 1 Teen- Adult !
Inhala-1 Food & Inhala- . Food &- Inhal a-1 Food'& Inhala- . Food &- l Radio- tion Ground tion- ~ Ground tion- Ground- tion Ground Pathway Pathway- ; Pathway Pathway Pathway Pathway . Pathway Nuclide Pathway H -3 . .-0-- '0.
- 4.0E3 - :2.6E3. 1.3E3 2.3E3- !
' 0- 6.1E6- - '1; 0E7 - 3.3E3 1.5E7. '!
1 'Cr-511 -
<Mn-54 ' 0-
- 6.5E8 9.2E8 7.7E4' 2.0E9 -
Co 2.4E8 - 3.2E8- 3.1 E4 . 5.6E8 Co-58 .3.7E8 : 5.9E8 1.1E5 9.1E8~ v 2.1E9- 3.2E9 ~2;8E5 '2.0E10-Co .3.5E10. 1.5E10 3.0E5 :9,8E9:
'Sr-89' i Sr-90' - '1.4E12 8.3E11 '9.9E7 ~ 6.7E11 ,
Zr ' =8.8E8 1.2E9 l'5E5
. 1.4E9 4 Nb-95 ~ 2.9E8 4.5E8 l'.0E5 5.8E8- '
.1.2E9 i Te-129m 2.9E9 - 1.8E9 3.7E4 Cs-134 2.6E10 1.6E10- 8.5E5- 1.6E10 Cs-136 2.2E8 1.7E8 11.5E5 '2.9E8 <
Cs-137 - 2.4E10: .-0-- 1L4E10 6.2ES~ 1.7E10 'i 0- 2.8E8 2.'1E8 12.2E5; 2.8E8 r Ba-140 ' 4.0E8 5.3E8' 1~.2ES , 5.1E8-4 Ce-141 , Ce'144- 1.0E10 1.3E10' 8.2E5~ :1.1E10 1 -131 4.8E10 3.1E10 1.2E7~ 3.8E10 ( I -133 -0 . 8.1E8 4.6E8 2.2E6 5.3E8 t i I -135 9.8E6 .5.7E6 4.5ES 8.6E6 UN-ID- 2.7E9 1.9E9 1.0E5 1.9E9 i f Inhalation Pathway, units ;
*C /
y I* , Food & Ground Pathway, units f*j"j'#" c 2-44 Rev. 21 02-15-90 i APPRoyEn 759g y ;ggq i i
f TABLE 2-81 DOSE PARAMETER Rj FOR SECTOR Q Page 7'of 8 Pathway - San Clemente Ranch (No Residents) Distance = 2.2 miles
- X/Q = 3.3E-7 sec/m*- D/Q - 1.4E-9 m-*
-Infant Child- -Teen , Adult i
Inhala- Food & Inhala- Food & Inhala-- Food & Inhala- -Food &' 3 Radio- tion -Ground tion' Ground tion . Ground tion Ground ! Nuclidef Pathway Pathway Pathway Pathway Pathway _ Pathway Pathway. Pathway
- l H 3.8E3 -2.4E3 .-0 -
. I '. 9 E 3 Cr-51 4.8E6 ~7.4E6. . 6.7E6: ,
Mn-54 6.1E8 .8.3E8, 28.0E8 C0 - 2.2E8 2.9E8 2.4E8:
-Co-58 3.3E8 5.1E8 ' 0-
- 4.7E8 -
Co-60 2.0E9 - 3.0E9 '2.7E9 l' Sr-89 3.lE10 1.2E10 - 7.2E9-Sr-90 - 1.3E12 - 7.7E11 5.8E11 Zr-95 -7.8E8 1.lE9 0- 9.1E8 Nb 2.4E8 -3.5E8 3.1E8: Te-129m 2.3E9 - 1.4E9 ' -0 : 7;9E8 :
'Cs-134 - '0-2.4E10' -1.5E10 -9.2E9 1 Cs-136 9.0E7- 5.7E7- '3 ~
. 6E7:
Cs-137 2.2E10 -0; 1.3E10 7.8E9 Ba-140 = 1.lE8 6.8E7: 5.3E7 . Ce-141- '0-
' 0-3.3E8 - 4.1E8' . 3.2E8 Ce-144. 9.2E9 . 1.2E10 - 9.0E9 I -131 4.1E9 2. lE9 : J 1.4E9 I -133 4.0E-11 1.7E-11 1.1E-11
, I -135 0- 6.9E-35 ,3.0E-35 -0 . 1.9E-35 l
- UN-ID 2.5E9 1. 7 E9 -- 'l.1E9 l r
l l l-l L i Inhalation Pathway, units = *]j"(5#
" Y"I Focd & Ground Pathway, units I*2hf 2-45 Rev. 21 .
l (. 02-15-90 l o a APPROVED FFB 211990 i
i TABLE 2-3 DOSE PARAMETER Rj FOR SECTOR Q. Page 8 of 8- f Pathway =; San Clemente Ranch'Adm. Offices Distance = 2.5 milest X/Q = 2.7E-7 sec/(m*)-- -D/Q = 1.lE-9.m-' . Infant Child . Teen Adult. , Inhala- . Food.& Inhala ' Food-& Inhala-- Food &' Inhala- Food & Radio- tion ' Ground' tion Ground- tion- Ground- tion Ground. Nuclide Pathway Pathway Pathway Pathway Pathway ( Pathway Pathway- Pathway r i H - -0L- .-0-- 2.9E2 1.9E3 Cr-51 - - 7.6E2 7.8E6 Mn -0 .1.8E4-- 1.'l E9 ' Co' 7.2E3 3.2E8 -
.Coa 58' - : 2.4E4' 5.6E8 .Co 60 - ;0-. -0 6.5E4- 7.6E9. .
L Sr-89 6.9E4 7.2E9 " Sr-90 - ' .-0-- 2.3E7- 5.8E11 Zr-95 3.4E4: 9.7E8- ?!
- Nb 95 . -0 2.4E4 3'4E8 Te-129m - 8 3E3-
. :7.9E8 Cs-134. - - -0 : 1.9E5 1.1E10- .
Cs-136 ' 0-3.3E4- 7.0E7- lt' , Cs-137 -0 . .l.4E5 '1.0E10-Ba-140 0- 5.0E4 ~ 5.8E72 Ce-141 :2.7E4 3.2E8 Ce-144 ~ .l 9E5 9.0E9 I -131 - - 2.7E6 1.4E9 I -133' - 4.9E5- 5.6E5 i I -135 1.0E5 5.8E5 UN-ID 2.4E4 1.2E9 i t j l Inhalation- Pathway, units = 5" 4 2 Food & Ground Pathway, units - (m H mrem /vr) pCi/sec 2-46 Rev. 21 1 02.-15-90 i APPROVED FrR R ,1999
- _ _. _ _. u_.
._. ._ _ __ _ _ _ _ _ -~ .
i TABLE 2 1 J DOSE PARAMETER R[ FOR SECTOR R Page 1 of'5 1
~
Pathway = San Onofre Mobile Homes- Distance.- 1.2 miles . l 3.2E-9 m-' X/Q = 5.3E-7 sec/m* D/Q l Infant Child -Teen Adult Inhala- Food & Inhala- Food & Inhala- Food &' Inhala- ' Food & Radio- tion Ground- tion- l Ground; tion ~ Ground. tion Ground. Nuclide Pathway Pathway Pathway Pathway Pathway : Pathway Pathway Pathway ,
~
H -3 '6.5E2- 1.1E3 -0 , 1.3E3- . - O '- ~ ~1.3E3 - . ' 0-1 :
-3.7E6; Cr-51 '3.6E2 3.7E6 :1.1E3 3.7E6 3.0E3. 3.3E3 3.7E6 Mn-54 2.5E4 .1 ~.1 E9. :4.3E4 1.1E9 6.7E4: 1.1E9 7.7E4 1.1E9 i Co-57~ 4.9E3- 2.7E0: 1.3E4- -2.7F8J 3.1E4- 2.7E8 3.1E4 2.7E8; <
Co-58 -1.1E4 3.0E8~ 3.4E4 3.0E8 -9.5E4 3.0E8 l'1E5 3.0E8( . 2.8E5 1.7E10-Co-60 3.2E4 .1.7E10 9.6E4 -1.7E10 2.6E5 1.7E10 D Sr-89 4.0E5 1.7E4 6.0E5 1.7E4J 4.3E5' 1.7E4 3.0E5 l'. 7 E4 : Sr-90 '4.1E7 1.0E8 - 1.1E8; . > 9 '. 9 E7 ' Zr-95 2.2E4 .2.0E0 6.1E4 2.0E8 . 1.5E5 2.0E8 1.5E5- ~2.0E8 Nb-95 1.3E4 -1.1E8 3.7E4 *1.1E8 9.7E4? ,1.1E8 1.0E5 1.1E84 Te-129m 3.2E4 1.6E7 5.0E4 1.6E7 5.2E4- 1.6E7 3.7E4 l'. 6 E7 L 'i Cs-134 7.0E5 5.5E9 1.0E6. 5.5E9 1~.1E6 5.5E9 '8.5E5 5.5E9 -I Cs-136 1.3E5 1.2E8 .1.7E5 1.2E8' 1.9E5 1.2E8 .1.5ES 1.2E8 ; Cs-137 6.1E5 8.2E9 8.3E5 '8.2E9 8.5ES- 8.2E9 '6.2E5 8.2E9' 1 o Ba-140 5.6E4 1.6E7 7.4E4? 1.6E7 2.3E5 l'6E7' 2.2E5- ' 1.6E7 Ce-141. 2.2E4 1.1E7 5.7E4 - 1.1E7 1.3E5- 1.1E7 1.2E5- -1.1E7 Ce-144 1.5E5 5.6E7 3.~9ES 5.6E7- :8.6E5 5.6E7: 8.2E5 5.6E7 I -131 1.5E7 1.4E7 1.6E7 1.4E7' 1.5E7 1.4E7 1.2E7 1.4E7 ; I -133 3.6E6 -2.0E6 3.8E6- 2.0E6 2.9E6 2.0E6 2.2E6- '2.0E6 ' I -135 7.0E5 2.0E6 7.9E5 2.0E6 6.2E5- 2.0E6 4.5ES- 2.0E6 L UN-ID 6.3E4 6.0E8 1.1E5- 6.0E8 1.3E5 6.0E8 > 1 '. 0 E 5 6.0E8 s r l l: l' l 3 i Inhalation Pathway, units * !" y Food & Ground. Pathway, units I*2 # "I j 2-47 Rev. 21 1 02-15-90 A P P R O V E n Er a 9 y 1999 . l;
TABLE 2-9
.D0SE PARAMETER Rj-FOR SECTOR R Page'2 of 5
- o. Pathway - San Clemente Ranch (No Residents) Distance.='2.3 mile's D/Q.= 1.0E-9 m-
8
,X/Q. 2.0E-7 sec/m Infant Child Teen Adult
, Inhala . Food-& Inhala- . Food & Inhal a- - Food & Inhala- Food & : Radio- - tion Ground tion Ground tion Ground tion- Ground-Nuclide Pathway' = Pathway Pathwayz Pathway PathwayL Pathway Pathway- Pathway , , t H'-3 :3.8E3 2.4E3 11.9E3' Cr-51 : 4.8E6' -0 : '7.4E6 6.7E6-
- - Mn-54 ' 6.1E8- -0, - 8.3E8 . 8,0E8
- Co-57 - -0 ' 2.2E8
- - 2.9E8 : -2.4E8 Co-58' 3.3E8 5.1 E8 ' 4.7E8 Co-60 . 2.0E9. 3.0E9 2.7E9 Sr-89 . 3.1E10- .1.2E10 7.2E9-Sr-90 . 1.3E12 7.7E11 15.8E11 Zr-95 7.8E8- < 1.1E9 9.1E8 *
.Nb-95 2.4E8 3.5E8 3.1E8 Te-129m '2.3E9 .-0-- -1.4E9 7.9E8
'Cs-134 2,4E10 1.5E10 9.2E9 Cs-136 - 9.0E7- 5.7E7- - 3.6E7' ,
Cs-137 -0 ' - 2.2E10 1.3E10 7'8E9 Ba-140 1.1E8 . -6.8E7 - 5.3E7
.Ce-141 - 3.3E8- '4.1E8- 3.2E8-Ce-144- - 9.2E9- -0; 11.- 2 E10 - 9.0E9 L I -131 4.1E9 2.1E9 . -04 1.4E9- i I -133- 4.0E-11 - 1.7E-11 -0 : 1.1E-11 I -135 6.9E-35 3.0E-35 1.9E-35 -
UN-ID 2.5E9L 1.7E9. 1.1E9 j h i I L t. Inhalation Pathway, units = "I'"(?" j "C Food & Ground Pathway, units = I* f*ff*/V"I 2-48 Rev. 21 02-15-90 APPROVED ECR21 1R90 . q
= TABLE 2-9' DOSE PARAMETER Rj.FOR SECTOR R--
Page 3 of 5 i Pathway - SC Ranch Packing Distance - 2.6 miles X/Q - 1.7E-07 sec/m' .0/Q =: 8.2E-10 m l i Infant Child Teen Adult Inhala- Food & Inhala- Food & Inhala-- Food-&> Inhala- Food'&> Radio- tion Ground. tion Ground tion Ground tion Ground Pathway Pathway- Pathway 1 Nuclide- Pathway Pathway Pathway Pathway Pathway H -3 - O'- '3.8E3 2.4E3 1.2E3- 1.9E3 Cr-51 4.8E6 '- 7.4E6- 3.0E3 1.0E7-- 6.1E8 '8.3E8 7.1E4 ,1.9E9 Mn-54 . Co-57 2.2E8 - f2.9E8 2.9E4 :5.2E8 L Co-58 3.3E8- 5.1E8L 9.8E4: .7.8E8 Co-60 -2.0E9- 3.0E9 2.6E5L 2.0E10 4 Sr 3.1E10 . '1.2E10 2.8E5- '7.2E9 Sr-90 1.3E12< 7.7E11; 9.1E7 ~5.8E11L 7.8E8 1.4E5; -1.1E9 Zr-95 1.~ 1 E9 Nb-95 2.4E8 3.5E8: 9.5E4 4.2E8: 4 Te-129m ~ 2.3E9 - 1.4E9- 3.4E4' 8.0E8 Cs-134 2.4E10 : -l.5E10 7.8E5 1.5E10 Cs-136 9.0E7 -0 ~ 5.7E7- li3E5 1.6E8 ' Cs-137 2.2E10 1.3E10- .5.7E5 l'.6E10 Ba-140 1.1E8 = . 6. 8E7- 2.0E5 17.0E7 ' Ce-141 3.3E8 -4 1E8' 1.1E5 3.3E8-Ce-144 9.2E9 '1.2E10- 7.5E5- 9.0E9 , I -131 - 4.1E9 2.1E9 1.1E7: 1.4E9-I -133 4.0E-11 1.7E-11 2.0E6 -' 2.0E6 ! I -135 ~ 6.9E-35 3.0E-35 - 4.1 E5 - 2.0E6 i UN-ID 2.5E9 1.7E9 9.5E4 1 7E9 :
?
l .' Inhalation Pathway, units =
- y I* V"I Food & Ground Pathway, units l
- 2-49 Rev. 21 02-15-90 APPROVED FEB 211990
_. . ~ _ TABLE 2-9' DOSE PARAMETER Rj FOR-SECTOR'R Page 4=of 5 , Pathway - Sheep Meat Distance'= 0.9 miles D/Q = 5.2E-9 m-*~ t X/Q = 8.3E-7 sec/m*. Infant Child Teen Adult c Inhala-- Food & Inhala-- Food 1 &: Inhala- LFood &- Inhala- Food &- Radio - tion- Ground tion; Ground tion: Ground tion- Ground ; Nuclide Pathway- Pathway Pathway Pathway Pathway Pathway Pathway _ . Pathway [ t H -3 : 1. 5EO ,- - 1:.2E0 '7.0E0 2.1E0 C r- 51 -- 5.1El . '1.0E2 1.8E1 '2.6E4 Mn-54 - 0- 7.8E2 . .1.4E3 4.3E2- 7.6E6 8.1E3 ~1.7E2- '1.9E6= C0 4.7E3
- Co'58
- -9.7F3 2.0E4 5.9E2 2.1E6
. Co -- 3.7E4- 7.3E4- '1.6E3 l'.2E8 Sr-89 5.0E4' - 2.6E4 1.7E3 3.1E4 , Sr-90 - 1.0E6 8.1E5 5.5E5 1.3E6 Zr-95 6.3E4 1.1ES 8.'3E2 1.6E6- l Nb-95 -0 ' 2.4E5 ' 4 ~. 5E 5' 5.7E2 1.6E6' 6.5E5 t Te-129m - 6.0E5 4.5ES 2.0E2 > Cs-134 1.4E5 - 1.2E5 4.7E3 3.8E7 i Cs-136 5.1E3 --0 1 4.3E3 8.1E2 8;3E5J Cs~137 - 1.3E5 9.5E4' 3.4E3 5.7E7 Ba-140 -- -0 c ' 5.1E3
- 4.3E3- -1.2E3 1.2E5' .
7.9E4 t Ce-141 -0 1.5E3 2.4E3. 6.6E24 Ce-144 - 1.8E4 3.0E4' 4.5E3: ~4.3E5 I -131 6.6E51 4.4E5- '6.6E4 .7.0E5 I -133 1.6E-2 8.7E-3 1.2E4 1.3E4 I -135 1.1E-18 '6.4E-19 T.5E3 1.4E4 ' UN-ID 1.1E5 - 9.5E4 ' 5.7E? 4.2E6
- s k
4 i i Inhalation Pathway, units
*C /
4 y Food & Ground Pathway, units - (m rem /vr) 2-50 Rev. 21 02-15-90 APPROVED FEB 211990 . J t
TABLE 2 ; l D0SE PARAMETER Rj FOR SECTOR R Page 5 of 5 Pathway = Deer Consumer Distance.= 2.2 miles i X/Q = 1.8E-7 sec/m* D/Q = 8.8E-10 m** l Infant Child Teen Adult Inhala- Food & Inhala- Food &? Inhala- Food &- Inhala- . Food & Radio- tion Ground- tion : Ground- tion Ground tion Ground Kxlide- Pathway Pathway Pathway Pathway Pathway Pathway Pathway Pathway
,=
H -3 2.8E1 2.3E1 3.5El> 3.9El-Cr-51 5.0E4 - 1. 0 E 5 '- 9.1El- - 3 . 2 E 5 --
-Mn-54 .7.7E5- - 1.4E6 2.1E3L 4.1E7 Co-57 -0 . 4.6E6- ' 8.0E6 8.6E2. 2.3E7 .! , Co-58 9.6E6-- - - 1.9E7 2.9E3 ' 4 '. 7 E 7 I Co-60 - 3.6E7- 7. 2E7-- 7.8E3 7.2E8 Sr-89 4.9E7 - ' 2,6E7 -8.3E3 3.1E7 Sr-90 1.0E9 '8.0E8- 2.7E6- 1 2E9 Zr-95 6.2E7 - 1.1E8 4.1E3: 2.0E8' Nb-95 -0 . 2.3E8 4.5E8 2.8E3 8.2E8 Te-129m 5.9E8- 4.5E8< 1.0E3 5.3E8?
Cs-134 0- 1.4E8 '1.2E8 2'.3E4 3.4E8-Cs-136- - 5.1E6 - 4.2E6 4.0E3 19.5E6-Cs-137 1.2E8 9.3E7.- 1.7E4- 4.0E8 Ba-140 5.0E6 4.2E6 6.0E3 7.4E6-
.Ce-141 1.5E6 2.4E6 -3.3E3 4.2E6
, Ce-144 - 1.8E7 - 2.9E7 2.2E4 -4.9E7: I -131 6.5E8 - 4.3E8- 3.'3E5 - 5.9E8. I -133 1.6El 8.6E0 5.9E4 6.7E4 I -135 1.1E-15 - 6.3E-16 1.2E4- 6.9E4 ! UN-ID - 1.1E8 9.4E7 2.8E3 1.4E8-t t, Inhalation Pathway, units = 5" Food & Ground Pathway, units = (m r r) j
-3102c. man 2-51 Rev. 21 l 2-15a0 l APPROVED FEB 211990
.n,
M TABLE 2-10 DOSE PARAMETER R FOR SECTOR A-Page 1 of 3-- Pathway.=CampSanMatgo Distance-- 3.6 miles I X/Q'- 7.1E-8 sec/m D/Q --4.1E-10'm
- Infant. Child _ . Teen : Adult-a Inhala- Food &- Inhala- Food-& Inhala- Food & . Inh al a-- Food'&-
R;dio- tion Ground--tion Ground- tion = ' Ground- tion . Ground ' Nuclide-- Pathway Pathway Pathway Pathway Pathway ' Pathway Pathway Pathway H -3 . 1.3E3 LO-f e.51' - - 3.3E3 3.7E6 ; Mn-54 - - 7.7E4 Ll.1E9 . Co-57 ~3.1E4 '2.7E8-Co-58 '0-1.1ES . -2.0E8 Co-60 ~ 2.8E5 -1.7E10 Sr-89 - -0 : -0 = .3.0E5 1.7E4: Sr-90 0- - 0- 9.9E7 Zr-95 -0 . -0 1.5E5 2.0E8 Nb-95~ - -O'- .-0-- 1.0E5 1.lE8: Te-129m - 13.7E4' 1.6E7 Cs-134 - ~ 8.5E5 5.5E9 Cs-136 ' 1.5E5 -1.2E8 Cs-137 6;2E5l 8.2E9. ' Ba-140 2.2E5 1.6E7 Ce-141 1.2E5- ~1.1E7 - 1 Ce-144 -0 ' - 8.2E5 5.6E7 I -131 1.2E7 1.4E7 I -133 2.2E6 2.0E6 I -135 4.5ES 2.0E6 UN-ID - 1.0E5 6.0E8 9 Inhalation Pathway, units = . !" Food & Ground Pathway, units = I* " "I j 1 l l 2-52 Rev. 21 l 02-15-90 ; APPROVED FEB 2-11990
TABLE 2-10 DOSE-PARAMETER R j F0R. SECTOR A Page'2 of 3 Distance = 0.2 miles _ Pathway = Sheep-(Meat)* X/Q - 6.7E-6 sec/m D/Q = 5.2E-8 m-* ... e Infant ' Child Teen Adult- . Inhala . . Food _&' Inhal a- - Food &' Inhala- Food & Inhala- Food & .; Radio- tion Ground tion. Ground- tion- Ground. tion -Ground ; Nuclide Pathway Pathway Pathway' Pathway Pathway.. Pathway Pathway Pathway - H -3' -0 . -0 . 1.5E0 ' - l '. 2 E0 - 7.0E0' '2.1E0 'i Cr 5.lEl 1.0E2 1.8El- 2. 6 E4-1 . Mn-54 - - . 7 8E2- 1.4E3 4.3E2' 7.6E6 Co 57- .-0. - 4.7E3 8.lE3 1.7E2- 1.9E6- 1
;2.0E4
~Co-58
- 9.7E3 . -. 5 '. 9 E 2 2.1E6 :
Co-60 3.7E4- . L7.3E4 1.6E3. 1,2E8- i Sr-89 : 5.0E4 2.6E4 1.7E3 L3.1E4 *
.Sr-90 ' 1.0E6 8.lE5 .5.5E5 <1.3E6' Zr - 6.3E4 - 1.lE5 8.3E2 1.6E6' '
Nb 95 - 2.4ES: - 4.5ES 5.7ER: 1.6E6 i F Te-129m - 6.0E5 -Oi -4.5E5- :2.0E2 6.5E5 , Cs-134 1.4E5 :1.2E5 4.7E3' 3.8E7 t Cs-135 5.1E3- 4.3E3 !8.lE2' 8.3E5 " Cs-137 - 1.3E5' - 19.5E4 1 3.4E3 5 ~. 7 E 7 - Ba-140 5.1E3 4.3E3 1.2E3 11.2E5 Ce-141 1.5E3 ~ 2.4E3- 6.6E2 7.9E4 : Ce-144 -0 & -- 0 ' l'8E4
. 3.0E4 4.5E3 4.3ES ,
F I -131 6.6E5 . 4.4E5 '6.6E4. 7.0E5 : I -133; 1.6E-2 8.7E-3 1.2E4 1.3E4- l 1 -135 1.lE-18 6.4E-19 2.5E3 1.4E4 UN-ID 1.1E5' -0 . 9.5E4 5.7E2 4.2E6' q l l l L j t
.i
[ i InhalationPathway, units =]j*!" Food & Ground Pathway, units I* */Y"I 2-53 Rev. 21 ; 02-15-90 : APPROVED:-FEB 21 1990
TABLE 2-10 M $E PARANETER Rg FOR $ECTOR A Page 3 of 3 Pathway =DeerConsumeg . Distance = 2.2 miles' X/Q = 1.9E-7 sec/m D/Q = 1.4E-9 m' 1 Infant Child Teen Adult Inhala. Food & Inhala- Food & Inhala- Food & Inhala- Food & Radio- tion Ground tion Ground ' tion Ground tion Ground Nuclide Pathway Pathway Pathway Pathway Pathway Pathway Pathway Pathway H -3 0- 0- 2.8E1 2.3E1 3.5El 3.9El Cr-51 0- 5.0E4 0- 1.0E5 9.1El 3.2E5 Mn 54 0- 7.7E5 1.4E6 2.1E3 4.1E7 Co-57 0- 4.6E6 8.0E6 8.6E2 2.3E7 Co 58 9.6E6 1.9E7 2.9E3 4.7E7 Co-60 3.6E7 7.2E7 7.8E3 7.2E8 Sr-89 0- 0- 4.9E7 2.6E7 S.3E3 3.1E7 Sr 90 0- 1.0E9 8.0E8 2.7E6 1.2E9 Zr-95 0- 6.2E7 1.1E8 4.1E3 2.0E8 Nb 95 0- 0- 2.3E8 0- 4.5E8 2.8E3 8.2E8 Te-129m 0- 0- 5.9E8 4.5E8 1.0E3 5.3E8 Cs-134 1.4E8 1.2E8 2.3E4 3.4E8 Cs-136 0- 5.1E6 4.2E6 4.0E3 9.5E6 Cs-137 0- 1.2EL 9.3E7 1.7E4 4.0E8 ' Ba-140 5.0E6 4.2E6 6.0E3 7.4E6 Ce 141 0- 1.5Ed 0- 2.4E6 3.3E3 4.2E6 Ce 144 0- 1.8E7 2.9E7 2.2E4 4.9E7 I -131 0- 6.5E8 4.3E8 3.3E5 5.9E8 1 -133 0- 1.6El 8.6E0 5.9E4 6.7E4 1 -135 0- 1.1E-15 6.3E-16 1.2E4 6.9E4 UN ID 0- 1.1E8 9.4E7 2.8E3 1.4E8 e ( I i Inhalation Pathway, units = i Food & Ground Pathway, units I" *#V"I c 2-54 Rev. 21 02-15-90 APPROVED FEB 211990 g'
TABLE 2-11 005E PARAMETER Rg FOR $ECTOR B Page 1 of 3 Pathway - Sheep (Meat)' . Distance'= 5.3E0.2 miles' X/Q > 6.lE 6 sec/m 0/0 8 m* Infant Child' Teen Adult Inhala. Food & Inhala- Food & Inhala- Food & Inhal a- Food & Radio- tion Ground tion Ground tion Ground tion Ground Nuclide Pathway Pathway Pathway. Pathway Pathway Pathway Pathway Pathway H -3 0- 1.5E0 1.2E0 7.0E0 2.1E0 Cr-51 0- 5 lEl .l.0E2 1.8El 2.6E4 Mn 54 -0 7.8E2 1.4E3 4.3E2 7.6E6 C0-57 1- 4.7E3 8.lE3 1.7E2 1.9C6 Co-58 0- 9.7E3 2.0E4 5.9E2 2.1E6-Co 60 . 3.7E4- 7.3E4 1.6E3 1.2E8 Sr 89 0- 5.0E4 2.6E4 1.7E3- 3.1E4 Sr 90 0- 1.0E6 8 lE5 5.5E5 1.3E6 Zr-95 6.3E4 0- 1.lES 8.3E2 1.6E6 Nb 95 0- 2.4E5 4.5E5 5.7E2 1.6E6 Te 129m 0- 6.0E5 4.5E5 2.0E2 6.5E5 Cs-134 0- 1.4E5 1.2E5 4.7E3 3.8E7 Cs-136 5.1E3 4.3E3 8.1E2 8.3E5 Cs 137 , 0- 1.3E5 ~4.5E4 3.4E3 5.7E7 Ba 140 5.lE3 4.3E3 1.2E3 1.265 , Ce-141 1.5E3 2.4E3 6.6E2 7.9E4 L Ce-144 0- 1.8E4 3.0E4 4.5E3 4.3E5 I -131 6.6ES 4.4E5 6.6E4 7.0E5 I -133 0- 1.6E-2 8.7E-3 1.2E4 1.3E4 I -135 0- 1.1E-18 6.4E-19 2.5E3 1.4E4 UN ID 0- 1.lES- 9.5E4 5.7E2 4.2E5 , Inhalation Pathway, units = ]f(!" Food & Ground Pathway, units - (m r M j i 2 55 Rev. 21 APPROVUD FEB 211990
.. . . J
TABLE 2-11 DOSE PARAMETER R j FOR $ECTOR B Page 2 of 3 Pathway =DeerConsumep Distance = 1.1 miles
- X/Q = 3.4E 7 sec/m D/Q = 2.4E-9 m*
Infant Child Teen Adult Inhala- Food & Inhala- Food & Inhala- Food & Inhala- Food & Radio- tion Ground tion Ground tion Ground tion Ground Pathway Pathway Pathway Pathway Pathway Pathway Pathway Pathway Nuclide H -3 0- 0- 2.8El 2.3E1 3.5El 3.9El Cr 51 0- 0- 5.0E4 1.0E5 9.lEl 3.2E5 Mn-54 0- 7.7ES 1.4E6 2.1E3 4.lE7 0- 4.6E6 0- 8.0E6 8.6E2 2.3E7 Co 57 Co 58 0- 9.6ES 0- 1.9E7 2.9E3 4.7E7 Co-60 0- 3.6E7 7.2E7 7.8E3 7.2E8 Sr-89 0- 4.9E7 2.6E7 8.3E3 3.1E7 Sr 90 -0 0 1.0E9 0- - 8. ')E8 2.7E6 1.2E9 Zr-95 0- 6.2E7 0- 1.1E8 4.lE3 2.0E8 Nb 95 0- 2.3E8 4.5E8 2.8E3 8.2E8 Te-129m 0- 5.9E8 0- 4.5E8 1.0E3 5.3E8 Cs-134 1.4E8 0- 1.2E8 2.3E4 3.4E8 Cs-136 5.1E6 4.2E6 4.0E3 9.5E6 Cs-137 1.2E8 9.3E7 1.7E4 4.0E8 Ba-140 5.0E6 4.2E6 6.0E3 7.4E6 Ce 141 1.5E6 2.4E6 3.3E3 4.2E6 Ce-144 1.8E7 2.9E7 ,2.2E4 4.9E7 I -131 6.5E8 4.3E8 3.3E5 5.9E8 I 133 -0 0- 1.6El 0- 8.6E0 5.9E4 6.7E4 I 135 0- 1.1E 15 6.3E-16 1.2E4 6.9E4 UN-ID 1.lE8 9.4E7 2.8E3 1.4E8 Inhalation Pathway, units y= *]f(l" I* * "I Food & Ground Pathway, units
- 2-56 Rev. 21 02-15-90 APPROVED FEB 2 L 1990 ,
.a
a TABLE 2-11 00$E PARAMETER R g FOR $ECTOR 8 Page 3 of 3 Pathway = Sanitary Langfill Distance a 2.1 miles X/Q =- 1.4E 7 cec /m D/Q = 1.2E 9 m ' .__ Infant Child Teen Adult Inhala- Food & Inhala. Food & Inhala- Food & Inhala- Food & Radio- tion Ground tion Ground tion Ground tion- Ground Nuclide Pathway Pathway Pathway Pathway Pathway Pathway Pathway . Pathway H3 0- 0 2.9E2- Cr 51 0- 0- 0- 0- 7.6E2 1.lE6 Mn 54 0- 1.8E4 ,
.3.2EB.
Co 57 0- 4 0- 0- 7.2E3 7.8E7 Co 58 -0 . 2.4E4 8.7E7 ' Co 60 -0+ -0 4 0- - 6.5E4 4.9E9 Sr-89 0- 0- 0- 6.9E4 4.'9E3 Sr-90 0- 0- 0- 2.3E7 Zr-95 0- 0- ! - 0,- 3.4E4 5.7E7 Nb 95 . 0- 0- 2.4E41 3.lE7 Te-129m , 8.3E3' 4.5E6 Cs-134 0- 0- 0- 1.9E5 1.6E9 I Cs 136 0- 0- 3.3E4 3.4E7 l
, 1.4E5 Cs-137 0- 2.3E9 Ba-140 0-' 5.0E4 4.7E6 Ce-141 ' 0- 0- 2.7E4' 3.lE6 i i' Ce-144 1.9ES 1.6E7 i
! -131 0- 0- 2.7E6 3.9E6 I 133 0- 4.9ES 5.6E5-I -135 0- 0- 1.0E4 5.8E5 UN ID 2.4E4 1.7E8 !
I
-l f
Inhalation Pathway, units = ym]jmyr Food & Ground Pathway, units = I" " "I 7 a 2-57 Rev. 21 02-15 90 i APPROVED- FFR S 1 1990
. l
TABLE 2-12 00$E PARAMETER Rg FOR SECTOR C Page 1 of 5
. Pathway = Camp San Onoire Distance = 2.6 milts '
X/Q ='9.2E-8 sec/m' D/Q = 8.4E-10 m-Infant Child Teen Adult Inhala- Food & Inhala- Food & Inhala- Food & Inhala- Food & Radio . tion Ground tion Ground tion Ground tion Ground Nuclide Pathway. Pathway Pathway Pathway Pathway Pathway Pathway Pathway H -3 0- 0-- 1.3E3 Cr-51 0- -0 . 3.3E3 3.7E6 Mn-54 7.7E4 1.lE9 Co 57 0- 0- 3.lE4 2.7E8
-Co-58 0- 1.lE5 3.0E8 Co-60 0- 0- -0 2.8E5 '1.7E10 Sr-89 0 0- 0- 3.0E5 1.7E4 Sr 90 0- -0 0- 9.9E7 Zr 95 0- 0- 0- 1.5E5 2.0E8 Nb-95 0- 0- 1.0E5 1.1F8 Te 129m 0- 3.7E4 1.6E7 Cs-134 -0 8.5ES 5.5E9 Cs-136 0- 0- 1.5E5 1.2E8 Cs-137 0- 6.2E5 8.2E9 Ba-140 0- 0- 2.2E5 1.6E7 Ce-141 0- 1.2E5 1.1E7 Ce-144 0- 0- 8.2E5 5.6E7 1 -131 1.2E7 1.4E7 I 133 2.2E6 2.0E6 I -135 0- 4.5E5 2.0E6 UN-ID 0- 1.0E5 6.0E8 l
i InhalationPathway, units ="C$/ I* ""#yr) Food & Ground Pathway, units j c l
- 2-58 Rev. 21 APPROVED FEB 2 3 3999
TABLE 2-12 00$E PARAMETER Rg FOR SECTOR C ; Page 2 of 5 l Pathway-CampSanOno{reFr.Stn Distance = 2.3 miles' X/Q = 1.lE-7 sec/m D/Q = 1.lE-9 m-Infant Child Teen Adult Inhala- Food & Inhala- Food & Inhala- Food & Inhala- Food & Radio- tion Ground tion Ground tion Ground tion Ground ; Nuclide. Pathway Pathway Pathway' Pathway Pathway Pathway Pathway Pathway j I H -3 0- 0- 5.2E2 ' Cr-51 - 0- 1.4E3 1.9E6-Mn 54 0- 3.2E4 5.7E8 C0 57 -1.3E4 1.4E8 ' Co 58 0- 4.4E4 1.6E8 ! Co 60 0- 1.2E5 8.8E9 Sr-89 0- 0- 1.2E5 8.9E3 , Sr 90 0- -0 ' 4.lE7 0. Zr-95 0- ' 0-
- 0- 6.2E4 1.0E8 -
Nb 95 0- 0- 4.3E4 5.6E7 -i Te 129m 0 0- -1.5E4 8.lE6 Cs-134 0- 3.5ES E.8E9-Cs-136 - 6.0E4 6.2E7 t Cs-137 2.6E5 4.2E9 : Ba-140 -0. 9.0E4 8.4E6 i Ce-141 4.9E4 5.6E6 Ce 144 0- 0- 3.4E5 2.9E7 , 1 -131 4.9E6 7.lE6 1 -133 0- 8.8E5 1.0E6 . I -135 - 1.8E5 1.0E6 ' UN-ID. 0- -4.2E4 3.lE8 inhalation Pathway, units *]j"(!" y Food & Ground Pathway, units = I" " "I j k h e 2-59 Rev. 21 02-15-90 APPROVED FEB 21.1990 , t
TABLE 2-12 DOSE PARANETER Rg FOR SECTOR C Page 3 of 5 t Pathway Sewage Faciljty Distance = 1.2E-9 2.2 miles' m-X/0 = 1.2E-7 sec/m D/Q . i Infant Child Teen ' Adult ; t Inhala- Food & Inhala- Food & Inhala- Food & Inhala- Food & ! Radio- tion : Ground tion Ground tion Ground tion Ground . Nuclide Pathway Pathway Pathway Pathway Pathway Pathway Pathway Pathway - H -3 -;0- 2.9E2 , 0- 7.6E2 1.1ES Cr-51 0-Mn 54 -0. 0 0- 1.8E4 3.2E8- t Co 57 0- 0- 7.2E3 7.8E7 , Co 58 0- -0 . 2.4E4- 8.7E7 Co 60 0- 0- 0- 6.5E4 4.9E9 Sr 89 0- 6.9E4 -4.9E3 i Sr-90 0- 0- 0- 2.3E7 Zr 95 0- 0- 3.4E4 5.7E7 : Nb 95 0- 2.4E4 3.1E7 Te-129m 0- 0- 8.3E3 4.EE6 Cs-134- 1.9ES 1.6E9 Cs-136 0- 3.3E4 3.4E7 Cs-137 0- 1.4E5 2.3E9 Ba-140- 0- 5.0E4 4.7E6 ' Ce-141 0- 2.7E4 3.lE6 Ce-144 1.9E5 1.6E7 ' I -131 0- 0- ~2.7E6 3.9E6 I 133 4.9E5 5.6E5 1 135 0- 0- 0- 1.0E5 5.8E5 UN 10 2.4E4 1.7E8 r
^
Inhalation Pathway, units = $# Food & Ground Pathway, units I" " "I
~
j T 2-60 Rev. 21 APPROVED FEB 211990
TABLE 2-12 l FOR SECTOR C . DOSE PARAMETER R9 Page 4 of 5 { Pathway Sheep (Meat)' Distance = 0.2 miles ! X/Q = 6.5E 6 sec/m D/Q = 5.3E-8 m ' Infant Child Teen Adult Inhala- Food & Inhala- Food & Inhala- Food & Inhala- Food &- 4 Radio- tion Ground tion Ground tion Ground tion Ground ,
^
Pathway Pathway Pathway Pathway Pathway . Pathway Pathway Pathway Nuclide H3 0- -0 1.5E0 1.2E0 7.0E0 2.lE0 5.lEl 1.0E2 1.8E1 2.6E4 Cr-51 0- 0- 7.8E2 1.4E3 4.3E2 7.6E6 Mn-54 Co-57 0- -0 4.7E3- -0 8.lE3 1.7E2 1.9E6 C0-58 9.7E3 2.0E4- 5.9E2 2.lE6 C0 60 0- 0- 3.7E4 0- 7.3E4- 1.6E3 1.2E8 Sr 89 5.0E4 2.6E4 1.7E3 3.1E4-Sr-90 1.0E6 8.lES 5.5E5 1.3E6 Zr-95 0- 6.3E4 1.lES 8.3E2 1.6E6 Nb 95 0- 2.4E5 4.5E5 5.7E2 1.6E6-Te-129m 0- 0- 6.0E5 4.5E5 2.0E2 6.5E5 f Cs-134 0- 1.4E5 1.2E5 4.7E3 3.8E7 Cs-136 0- 0- 5.1E3 0- 4.3E3 8.1E2 8.3E5 Cs-137 0- 1.3E5 9.5E4 3.4E3 5.7E7 Ba 140 0- 5.lE3 4.3E3 1.2E3 1.2Eb Ce-141 0- 1.5E3 2.4E3 6.6E2- 7.9E4 Ce-144 0- 1.8E4 3.0E4 4.5E3 4.3E5 6.6E5 4.4E5 6.6E4 7,0E5 I -131 I -133 1.6E-2 -0 8.7E-3 1.2E4 1.3E4 1 -135 0- 1.lE-18 -0 6.4E-19 2.5E3 1.4E4 UN-10 0- 1.lES 9.5E4 5.7E2 4.2E6 I Inhalation Pathway, units *]j"(5" y I* " "I Food & Ground Pathway, units j l I 1 E-61 Rev. 21' 02-15-90 APPROVED FEB 211990 .
~
TABLE 2-12 DOSE PARAMETER R j FOR SECTOR C Page 5 of 5 Pathway = Deer Consumer Distance = 1.0 miles i X/Q = 3.4E-7 sec/m' D/Q = 5.1E-9 m-* Infant Child Teen- Adult i Inhala- Food & Inhala- Food & Inhala- Food & -Inhal a- Food & Radio- tion Ground tion Ground I an Ground tion G" nnd Nuclide Pathway Pathway Pathway. Pathway Pathway Pathway Pathway luthway . j 2.8E1 2.3E1 3.5El 3.9El j H -3 Cr-51 0- 5.0E4 1.025 9.1El 3.2E5 .1 Mn-54 7.7ES 1.4E6 2.1E3 4.1E7 l Co-57 4.6E6 8.0E6 8.6E2 2.3E7 Co-58 9.6E6 1.9E7 2.9E3 4.7E7 Co-60 3.6E7 7.2E7 7.8E3 7.2E8 Sr-89 4.9E7 2.6E7 8.3E3 3.1E7 , Sr-90 1.0E9 8.0E8 2.7E6- .1.2E9 , Zr-95 6.2E7 - 0.- 1.1EB 4.1E3 2.0E8 Hb 95 0- 2.3E8 4.5E8 2.8E3 8.2E8 - Te-129m 5.9E8 4.5E8 1.0E3 5.3E8 Cs-134 0- 1.4E8 1.2E8 2.3E4 3.4E8 Cs-136 5.1E6 4.2E6 4.0E3 9.5E6 Cs-137 0- 1.2E8 9.3E7' 1.7E4 4.0E8 Ba-140 -a- -0~ 5.0E6 4.2E6 6.0E3 7.4E6 Ce-141 1.5E6 2.4E6 3.3E3 4.2E6 Ce-144 1.8E7 2.9E7 2.2E4 4.9E7 I -131 6.5E8 4.3E8 3.3E5 5.9E8 I -133 1.6El 8.6E0 5.9E4 6.7E4 . I -135 1.lE-15 6.3E-16 1.2E4 6.9E4 < UN-ID 1.1E8 9.4E7 2,8E3 1.4E8
+
Inhalation Pathway, units = y*C / P Food & Ground Pathway, units = l* " "I j l 2-62 Rev. 21 APPROVED FF8.21 1999 _
TABLE 2-13 DOSE PARAMETER R g FOR SECTOR D . Page 1 of 3 Pathway =CampSanOno{re Distance = 2.8 miles X/Q = 6.6E-8 sec/m D/Q = 6.4E 10 m ' Infant Child Teen Adult inhala- Food & Inhala- Food & Inhala- Food & Inhala- Food & Radio- tion Ground tion Ground tion Ground tion Ground Nuclide Pathway Pathway Pathway athway Pathway Pathway Pathway Pothway ! H -3 0- 0- 1.3E3 Cr-51 0- 0- 0- 3.3E3 3.7E6 Mn-54 0- 0- 7.7E4 1.1E9 Co 57 -0 ' 0- 0- 0- 3.lE4- 2.7E8 : Co 58 0- 0- 1.lES 3.0E8 Co 60 0- 0- 0- 0- 0- 2.8E5_ l.7E10 , Sr 89 0- -0 3.0E5 .1.7E4 Sr 90 0- 0- 0- 9.9E7 0- i Zr-95 0- 0- 0- 1.5E5 2.0E8 Nb-95 0- 0- 0- 1.0E5 1.lE8 Te-129m 0- 0- -0 3.7E4 1.6E7 ! Cs-134 8.5E5 5.5E9 > Cs-136 0- 1.5ES 1.2E8 Cs-137 0- 6.2E5- 8.2E9 Ba-140 0- 2.2E5- 1.6E7 Ce-141 1.2E5 1 lE7 Ce 144 0- 0- 8.2E5 5.6E7 : I -131 1.2E7- 1.4E7 I -133 0- 2.2E6 2.0E6 I -135 4.5ES 2.0E6 UN-ID 0- -0 1.0E5 6.0E8 t InhalationPathway, units =]j"(!" Food & Ground Pathway, units = '* I "'
/ c 2-63 Rev. 21
' APPROVED rF8 211990
i TABLE 2-13 l l DO5E PARANETER Rg FOR SECTOR D Page 2 of 3 1 Pathway Sheep (Meat)' Distance = 0.2 miles * . X/Q = 6.3E-6 sec/m D/Q = 6.6E 8 m-
. Infant Child Teen Adult j Inhala. Food & Inhala. Food & Inhala-- Food & Inhala- Food &
Radio- tion Ground tion Ground tion Ground tion Ground Nuclide Pathway Pathway Pathway Pathway Pathway Pathway Pathway Pathway H -3 0- 0- 1.5E0 1.2E0 7.0E0 e. 1 E0 t Cr-51 0- 5.1El 1.0ER 1.8E1 2.6E4 i Mn-54 0- 0- 7.8E2 0- 1.4E3 4.3E2 7.6E6- ' Co 57 4.7E3 8.1E3 1.7E2 1.9E6 Co-58 0- 9.7E3 2.0E4 5.9E2 2.1E6 Co 60 0- 3.7E4 27.3E4 1.6E3 1.2ES i Sr 89 -D- -0 5.0E4 2.6E4 3.1.7E3 3.lE4 Sr 90 1;0E6 0- 8.1E5 5.5E5 1.3E6 Zr-95 0- 6.3E4 1.1ES 8.3E2 1.6E6 Nb-95 0- 2.4E5 4.5ES 5.7E2 1.6E6 Te 129m 6.0E5 .4.5E5 2.0E2 6.5E5 . Cs-134 1.4E5 i 1.2E5 4.7E3' 3.8E7 Cs 136 5.1E3 4.3E3 8.1 E2 - 8.3E5 Cs-137 0- 0- 1.3E5 9.5E4 3.4E3 5.7E7 Ba-140 5.1E3 4.3E3 1.2E3 1.2E5 Ce-141 1.5E3 2.4E3 6.6E2 7.9E4 Ce 144 1.8E4 3.0E4 4.5E3 , 4.3E5 1 -131 6.6E5 4.4E5 6.6E4 7.0EE I -133 1.6E-2 8.7E 3 1.2E4 1.3E4-I -135 1.1E-18 6.4E-19 2.5E3 1.4E4 UN 10 0- 0- 0- 1.1ES 9.5E4 5.7E2 4.2E6 Inhalation Pathway, units =
- Food & Ground Pathway, units I* "d j [
2-64 Rev. 21 02-15-90 APPROVED FEB 211990
., . . . ~
IABLE 2-13 : D0SE PARAMETER Rg FCR SECTOR D Page 3 of 3 Pathway = Deer Consumer Distance = 1.0 miles i X/Q = 3.3E-7 sec/m* D/Q = 3.3E-9 m * , Infant Child Teen Adult l Inhala- Food & Inhal a- - Food & Inhala- Foo[& Inhala- Food & ' Radio- tion Ground tion Ground tion Ground ' tion Ground Nuclide Pathway Pathway Pathway Pathway Pathway Pathway Pathway Pathway ; H -3 2.8E1 2.3E1 3.EE1 3.9El Cr 5.0E4 1.0E5 9.1EL 3.2E5 Mn-54 7.7ES 1.4E6 2.1E3 4.1E7-Co 57 4.6E6 8.0E6 8.6E2 2.3E7 Co-58 .9.6E6 '1.9E7- 2.9E3 4.7E7 Co 3.6E7 7.2E7 7.8E3 7.2ES .. Sc 89 4.9E7 2.6E7 8.3E3 3.1E7' ' Sr-90 1.0E9- 8.0E8 2.7E6 1.2E9 Zr-95 6.2E7 1.1E8 4.1E3 2.0E8 Nb-95 2.3E8 4.5E8' 2.8E3 8.2E8 Te-129m 0- 5.9E8 4.5E8 1.0E3 5.3E8
- Cs-134 1.4E8 1.2E8 2,3E4 '3.4E8 Cs-136 5.1E6 4.2E6 4.0E3 9.5E6 Cs-137 1.2E8 9.3E7 1.7E4 4.0E8 Ba-140 5.0E6 4.2E6 6.0E3 7.4E6 Ce-141 1.5E6 2.4'6
. 3.3E3 4.2E6 Ce-144 0- 1.8E7 2.9E7 2.2E4 4.9E7 .:'
I -131 5.5E8 4.3E8 3.3E5 5.?E8 I -133 1.6El 8.6E0 5.9E4 ' 6.7E4 ? 1 -135 1.1E-15 6.3E 16 1. ? D. 6.9E4 UN-ID 1.1E8 9,4E7 2.ou 1.4E8 ; [ T InhalationPathway, unitsy=*]f,[" I* Food & Ground Pathway, units {#yr) c 2-65 Rev. 21 Avenoygg gggg ,,990
- y. .
m , t TABLE 2.$4 6 t DOSE PARAMETER R g FOR SECTOR E Page 1 of'3 , Pathway = Camp Horno i Distance = 4.0 miles ' ' X/Q = 6.6E-8 sec/m* D/Q = 6.4E-10 m- , t Infant Child Teen- Adult Inhala- Food & Inhala- Food & Inhala- Food & Inhala- Food as , Radio- tion Ground tion Ground tion Ground tion: Ground ; Nuclide Pathway Pathway Pathway Pathway Pathway Pathway Pathwaj Pathway 4 H - 0.- 1.3E3 , Cr-51 3.3E3 3.7E6-Mn-54 0- -0, 7.7E4- 1.lE9 Co-57 3.1E4 2'.7E8 ; Co-58 -0, 1.1ES 3.0E8 - Co-60 0- 2.8E5 l ~.7 E10 Sr-89 0- 3.0E5 1./E4 ' Sr-90 9.9E7 Zr-95 1.5E5 2.0E8 Nb-95 0- 0- 1.0E5- 1.lE8 Te-129m 3.7E4 1,6E7 Cs-134 8.5E5 5.5E9 Cs 136- 1.5E5 1.2E8 > n Cs-137' 0- 0- 6.2E5 -8.2E9 . Ba-140 0- 2.2E5 1.6E7 . Ce-141 1.2E5 1.1E7 Ce-la4 8.lE 5 5.6E7 . I -131 1.2E7 1.4E7 1 I -133 2.2E6 2.0E6 I -135 0- 0- -J- 4:.5ES 2.0E6 UN-lO l'.0E5 G.0ES 1 l InhalationPathay, units-]fh" , Food & Ground Pathway, units = I* 7 J s APPROVED FEB'211990 2-66 Rev. 21 02-15-90 m 's -:
m ny
' TABLE 2-14 i D0SE PARAMETER Rg FOR SECTOR E !
Page 2 of 3 Pathway Sheep (Meat)' Distance = 0.3 miles ' X/Q = 4.5E-6 sec/m D/Q = 5.9E 8 m"' Adult-Infant Child Teen Inhala- Food & Inhala- Food Inhala- Fodd & Inhala- Food &. Radio- tion Ground tion Ground tion Ground tion Ground ; Nuclide Pathway Pathway Pathway Pathway Pathway Pathway Pathway Pathway H3 0- 1.5E3 1.2E0 7 0E0 '2.1E0 .! Cr 51 0- 5.1E1 ;0- 1.0E2 1.8El 2.6E4 Mn 54 0. 7.8E2 1.4E3 4.3E2 7.6E6 Co 57 0- 4.7E3 8.1E4 1.7E2 1.9E6 Co 58 0- 9.7E3 2.0E4 5.9E2- '2.lE6 , 00-60 0- 3.7E4 7.3E4 1.6E3- 1.2E8 Sr 89 5.0E4 2.6E4 1.7E3 3 lE4 0- 1.0E6 8.1ES 5.5E5 -1;3E6 Sr 90 Zr-95 0- 6.3E4 1.lES 8.3E2 .l.6E6 , Nb 95 0- 2.4E5 4.5ES 5.7E2 1.6E6 Te l?9m 6.0E5 4.5Eh 2.0E2' 6.5ES Cs-134 .0- 1.4E5 1 2E5 4.7E3 3.8E7-Cs 136 0- 5.lE3 4.3E3 1.1E2 8.3E5 Cs 137 1.3E5 9.5E4 3.4E3 . 5.7E7
- Ba 140 5 lE3 4.3E3 -1.2E3 1.2E5 -
Ce-111 1.5E3 2.4E3 S.6E2 7:9E4 Ce-144 1.8E4 0- 3.0E4- 4.5E3 4.3E5 I -131 6.6ES 4.4E5 6.6E4 7.0E5 I 133 0- 1.6E-2 8.7E-3 1.2E4 1.3E4 6.4E-19 2.5E3 1.4E4 I 135 1.lE-18 UN ID 0- 1.1ES 9.5E4- 5.7E2 4.2E6 1 Inhalation Pathway, units = ] h" Food & Ground Pathway, units Im r vr) j t APPROVED FEB 211990 ' 2-67 iRev. 21 1
'02.-15-90 T
~
\ .
1 I&BLE 2-14 l DOSE PARAMETER R g FOR SECTOR E Pathway . Deer Consumep Distance = 1.2 miles' ; X/Q = 3.7E-7 sec/m D/Q = 8.3E-9 m-Infant Child Teen Adult Inhala. Food & Inhala. Food & Inhala- Food & Inhala- Food & ' Radio- tion Ground tion Ground tion Ground tion Ground
- Pathway Pathway Pathway Pathway Pathway Pathway Fathway Pathway Nuclide l
t H -3 0- 2.8E1 0- 2.3E1 3.5El 3.9El Cr 51 0' -0 5.0E4 0- 1.0E5 9.1El -3.2E5 Mn 54 -0 7.7ES 1.4E6 2.lE3 4.1E7 + Co 57 4.6E6 0- 8.0E6 8.6E2 2.3E7 0- 9.6E6 1.9E7 2.9E3 4.7E7 Co 58 Co 60 0- - 3.5E7 7.2E7 7.8E3 7.2E8 Sr-89 0- 0- 4.9E7 2.6E7 8.3E3 3.lE7 , Sr 90 0- 0- 0- 1.0E9 0 8.0E8 2.7E6 1.2E9 Zr-95 0- 6.2E7 1.lE8 4 lE3 2.0E8 , Nb 95 0- 2.3E8 0- 4.5E8 2.8E3 8.2E8-Te-129m .0- 5.9E8 0- 4.5E8 1.0E3 5.3E8 Cs 134 1.4E8 0- 1.2E8 2.3E4 3.4E8 Cs-136 0- 5.1E6 4.2E6 4.0E3 9.5E6 Cs-137 1.2E8 9.3E7 1.7E4 4.0E8 Ba-140~ 5.0E6 0- 4.2E6 6.0E3 7.4E6 Ce-141 0- 1.5E6 2.4E6 3.3E3 4.2E6 Ce-144 1.8E7 2.9E7 2.2E4 4.9E7 I -131 0- 0- 6.5E8 4.3E8 3.3E5 5.9E8 1 -133 0- 0- 1.6El 8.6E0 5.9E4 6.7E4 1 -135 1.lE-15 6.3E-16 1.2E4 6.9E4
- UN-ID 1.lE8 0- 9.4E7 2,8E3 1.4E8 ;
I 4 1 a4 Inhalation Pathway, units = *C$/
^
'VII Food & Ground Pathway, units =
A i APPROVED FEB 211990 l
; 2-68 Rev. 21 02-15-90 ,
a~
-f- ,, ,
TABLE 2+15 DOSE PARAMETER R g FOR SECTOR F Page 1 of 5 j Pathway San Onofre S} ate Park Guard Shack Distance = 0.8 miles j ' X/Q = 8.lE 7 sec/m D/Q = 7.lE 9 m ' i Infant Child Teen Adult ] Inhala- Food & Inhala- Food & Inhala- food & Inhala- Food & l' Radio- tion Ground tion Ground tion Ground tion- Ground Nuclide Pathway Pathway Pathway Pathway Pathway Pathway Pathway- Pathway ; l 1 H -3 0- 0- 7.2El 0- ( 2.7ES Cr-51 0- 0- 1.9E2 Mn 54 -0, 0- 4.4E3 7.9E7 C0-57 0- 1.8E3 2.0E7 C0 58 0- 0- 6.lE3 2.2E7 i Co 60 0- 1.6E4 1.2E9 : Sr-89 0- -0 1.7E4 1.2E3 : Sr-90 0- 0- 5.7E6 0 Zr-95 0- 0- 8.6E3 1.4E7 Nb 95 0- 0- 5.9E3 7.8E6 Te-129m 0- 2.lE3 1.1E6 Cs-134 0 0- 0- 4.8E4 3.9E8 Cs-136 0- 8.4E3 8.6E6 , Cs-137 3.5E4 5.9E8 Ba-140 -0 0- 0- 1.2E4 1.2E6-Ce 141 0- 6.9E3 7.8E5 - i Ce-144 4.7E4 4.0E6
! -131 0- 0- 6.8EC 9.8E5 I -133 1.2E5 1.4E5 i
. 1 135 2.6E4 1.4E5 i
'!N 10 5.9E3 4.3E7 Inhalation Pathway, units =
Food & Ground Pathway, units - (m r r) j APPROVED FEB 211990 2 69 Rev. 21 02-15-90
t TABLE 2015 l DOSE PARAMETER R g FOR SECTOR F Page 2 of 5 Pathway = Beach Concession Distance = 0.9 miles X/Q = 6.9E-7 sec/m* O/Q = 6.0E-9 m 2 Infant Child Teen Adult Inhala- Food & Inhala- Food & Inhala- Food & Inhala-l Food &- I Radio- tion Ground tion Ground tion Ground tion Ground Nuclide Pathway Pathway Pathway Pathway Pathway Pathway Fathway_ Pathway H -3 0- 0- 0- 'l.2E2 Cr-51 0- 0- 3.lE2 4.4E5 Mn-54 0- 0- 0- 7.2E3 1.3E9 , Co-57 0- 2.9E3 3.2E7 Co 58 0- 0 1.0E4 3.6E7 ; Co 60 0- 0- 0- 2.7E4 2.0E9 - Sr-89 0- 0- 2.8E4 240E3-Sr-90 -0 9.3E6- . Zr-95 1.4E4 2.4E7 i Nb-95 0- 9.7E3 1.3E7 Te-129m 0- 3.4E3 1.8E6 l Cs-134 7.9E4 6.4E8 Cs-136 1.4E4 1.4E7 Cs-137 0- - 5.8E4 9.6E8 Ba-140 2.0E4 1.9E6 Ce-141 0- ' l.1E4- 1.3E6 Ce-144 7.6E4 6.5E6 : I -131 0- 0- 1.lE6 1.6E6 I -133 -0 0- 2.0E5 2.3E5 1 -135 0- 4.2E4 2.4E5 UN-10 0- 9.7E3 7.0E7 1 1 Inhalation Pathway, units = " Food & Ground Pathway, t.,its I* V"I 2-70 Rev. 21 ! APPROVED FEB 211990
TABLE 2-15 l D0SE PARAMETER R FOR SECTOR F i 9 Pa0e 3 of 5 ; Pathway = Border Patrol checkpt. Distance = 1.8 miles ! ' X/Q = 2.4E-7 sec/m D/Q = 1.8E 9 m ' Infant Child Teen Adult ; Inhala- Food & Inhal t.- Food & Inhala- Food & Inhala- Food & I Radio- tion Ground tion Ground tion Ground tion Ground Nuclide Pathway Pathway Pathway Pathway Pathway Pathway Pathway Pathway H -3 0- 0- 3.6E2 Cr 51 0- 0- 9.5E2' l.3E6 Mn-54 2.2E4 3.9E8 Co-57 0- 9.0E3 9,8E7 Co-58 0- 0- 0- 3.0E4 1.lE8 : Co 60 0- 8.lE4 6.1E9 Sr 89 0- 0- 8.7E4 6.2E3 ' Sr-90 0- 2.8E7 -0 Zr-95 0- 4.3E4 7.2E7 Nb-95 0- 0- 0- 3.0E4 3.9E7 Te-129m 0- 0- 1.0E4 5.6E6 Cs 134 - 0- 0- 2.4E5 1.9E9 Cs-136 0- .0- 4.2E4 4.3E7 - Cs-137 0- - 1.8E5 2.9E9 i Ba-140 6.2E4 5.9E6 Ce-141 - O '- 3.4E4 3.9E6 Ce-144 2.3E5 2.0E7 1 -131 3.4E6 4.9E6 I -133 -6.lE5 7.0E5 1 -135 0- 1.3E5 2.2E5 UN-ID 0- 0- 2.9E4 2.lE8 , J l . . Inhalation Pathway, units = [" i I Food & Ground Pathway, units I*2 " "I j 4 J 2-71 Rev. 21 02-15-90 APPROVED FEB 211990
i I& DIE 2-15 I 005E PARAMETER R FOR SECTOR F Page 4 of 5 I Pathway - Sheep (Meat)' Distance = 0.5 miles { X/Q = 1.9E-6 sec/m D/Q = 1.7E-8 m ' l Infant Child Teen Adult ; Inhala- Food & Inhala- Food & Inhala- Food & Inhala . Food & l Radio- tion Ground tion Ground tion Ground tion Ground Nuclide Pathway Pathway Pathway Pathway Pathway Pathway Pathway Pathway i H3 0- 1.5E0 1.2E0 7.0E0 2.1E0 - Cr 51- 0- 5.lEl 1.0E2 1.8El 2.6E4 Mn 54~ 0- 0 7.8E2 1.4E3 4.3E2 7.6E6 Co 57 0- 4.7E3 8.1E3 1.7E2 1.9E6 C0 58 9.7E3 2.0E4 5.SE2 2.lE6 Co-60 0- 0- 3.7E4 7.3E4 1.6E3 1.2E8 Sr 89 5.0E4 0- 2.6E4 1.7E3 3.1E4 Sr-90 0- 1.0E6' 8.lE5 5.5E5 1.3E6 Zr-95' 6.3E4 0- 1.1ES 8.3E2. 1.6E6 Hb 95 2.4E5 -O' 4.5E5 5.7E2 1.6E6 Te-129t 6.0E5 - 4.5E5 2.0E2 6.5ES Cs-134 1.4E5 1.265 4.7E3 3.8E7 Cs-136 5.1E3- 4.3E3 8.1E2 8.3E5 Cs-137 1.3E5 9.5E4 3.4E3 5.7E7 Ba-140 5.lE3 -0< 4.3E3 -1.2E3 1.2E5 Ce-141 1.5E3 2.4E3 6.6E2 7.9E4 Ce-144 1.8E4 3.0E4 4.5E3 4.3E5 I 131 6.6ES 4.4E5 6.6E4 7.0E5 I -133 1.6E 2 - 8.7E-3 1.2E4 1.3E4 I -135 1.1E 18 6.4E-19 2.5E3 1.4E4 , UN ID 0- 1.lE5 9.5E4 5.7E2 4.2E6 4 m InhalationPathway, units =]jhr Food & Ground Pathway, units I" " "I j 2-72 Rev. 21 02-15-90 1 APPROVED FEB 211990
i l TABLE 2-16 -- D0SE PARAMETER Rg FOR SECTOR F Page 5 of 5 Pathway = Deer Consumer Distance = 1.4 miles X/Q =~ 3.0E-7 sec/m D/Q = 2.3E-9 m '
' infant Child Teen Adult
=
Inhala- Food & Inhala- Food & Inhala- Food & Inhala- Food & Radio- tion Ground tion Ground tion Ground tion Ground c Nuclide Pathway Pathway Pathway Pathway Pathway. Pathway Pathway Pathway H -3 2.8El 2.3El- 3.5El 3.9El Cr-51 5.0E4 1.0E5 9.lEl 3.2E5 Mn-54 7.7E5 1.4E6 2.1E3 4.1E7 - Co-57 4.6E6 8.0E6 8.6E2. 2.3E7 Co 0- 9.6E6 -0. 1.9E7 2.9E3 4.7E7 i Co 60 0- 3.6E7 7.2E7 7.8E3~ 7.2E8 [ Sr 89 0- 0- 4.9E7 2.6E7 8.3E3 3.lE7
, Sr 90 0- 0- 1.0E9 8.0E8 2.7E6- 1.2E9 Zr 95 0- 6.2E7 1.1E8 4.lE3 2.0E8 -
Nb-95 2.3E8 4.5E8 2.8E3 8.2E8 , Te-129m 5.9E8 4.5E8 1.0E3 5.3E8 T Cs-134 0- 1.4E8 1.2E8 2.3E4 3.4E8 i Cs-136 0- 0- . 5.lE6 /,.2E6 4.0E3 9.5E6 Cs 137 1.2E8 9.3E7 1.7E4 '4.0E8 Ba-140 ' 5.0E6 4dE6 6.0E3 7.4E6 Ce-141 1.5E6 ? MS 3.3E3 4.2E6 Ce-144 1.8E7 ;-3E7 2.2E4 4.9E7 . I -131 0- 6.5E8 f.3E8 3.3E5 5.9E8 I -133 0- 0- 1.6El 8.6E0 5.9E4 6.7E4 ' I -135 1.lE-15 6.3E-16 1.2E4 6.9E4 UN-ID 1.lE8 0.4E7 2.8E3 1.4E8 Inhalation Pathway, units = [" I" " "'yr) Food & Ground Pathway, units c 2-73 Rev. 21
, 02-15,90 APPROVED FEB 21.1990
TABLE 2-16 00$E PARAMETER Rg FOR SECTOR 6 Page 1 of 4 Pathway - San Onofre State Beach Camprgound Distance - 0.8 miles X/Q = 7.7E-7 sec/m' D/0 - 3.9E 9 m
- Infant Child Teen Adult Inhala- Food & Inhala. Food &- Inhala- Food & Inhala- Food &
1 Radio- tion. Ground tion Ground tion Ground tion Ground Nuclide Pathway - Pathway Pathway _ . Pathway Pathway Pathway Pathway- Pathway H -3 8.0El 1.4E2 0-- 1.6E2 1.6E2 0-Cr 51 4.4E1 5.7E5 l>3E2 5.7E5 3.7E2 5.7E5 4.1E2 5.7E5 Mn-54 3.1E3 1.7E8 5.3E3 1.7E8- 8.2E3 1.7E8- 9.5E3 1.7E8 Co 57 6.0E2 4.2E7 1.6E3. 4.2E7 3.9E3- 4.2E7 3.9E3 4.2E7 C0 58 1.aE3 4.7E7 4.2E3 4.7E7 1.2E4' 4.7E7 1.3E4 4.7E7. Co 60 3.9E3 2.7E9' 1.2E4 2.7E9 3.2E4 2.7E9 3.5E4 2.7E9 Sr 89 4.9E4 2.7E3 7.4E4- 2.7E3 5.4E4 2.7E3 3.7E4 2.7E3 Sr 90 5.0E6 1.2E7 1.3E7 0- 1,2E7 Zr 95 2.7E3 3.1E7 7.5E3 3.1E7 1.8E4~ 3.1E7 1.9E4 3.1E7 Nb-95 1.6E3 1.7E7 4.6E3 1.7E7 1.2E4 1.7E7 1.3E4 1.7E7 Te 129m 3.9E3 2.4E6 6.2E3 2.4E6 6.4E3 2.4E6 4.5E3 2.4E6 Cs-134 8.7E4 8.4F8 1.3E5 8.4E8 1.4E5 8.4E8 1.0E5 8.4E8 f Cs 136 1.7E4 1.9E7 2.lE4 1.9E7 2.4E4 1.9E7 1.8E4 1.9E7 Cs-137 7.5E4 1.3E9 1.0E5 1.3E9 1.0E5 1.3E9 7.7E4 1.3E9 Ba-140 6.9E3 2.5E6 9.1E3 2.5E6 2.8E4 2.5E6 2.7E4 2.5E6 l Ce-141' 2.7E3 1.7E6 7.0E3 1.7E6 1.6E4 1.7E6 1.5E4 1.7E6 Ce-144 1.8E4 8.6E6 4.8E4 8.6E6 1.lES 8.6E6 1.0E5 8.6E6 1 -131 1.8E6 2'.1E6 2.0E6 2.lE6 1.8E6 2.1E6 1.5E6- 2.lE6 1 133 4.4E5 3.0E5 4.7ES 3.0E5 3.6E5 3.0E5 2.7E5 3.0E6 I -135 8.6E4 3.1E5 9.8E4 3.1ES 7.7E4 3.1ES 5.5E4' 3.lE5 UN ID 7.7E3 9.2E7 1.4E4 9.2E7 1.6E4 .9.2E7 1.3E4' 9.2E7
" I Inhalation Pathway, units -
Food & Grnund Pathway, units - (m r vr) je 1 1 2-74 Rev. 21 APPROVED FEB 211990
7 . I l l TABLE 2-16, DOSE PARAMETER Rg FOR SECTOR G Page 2 of 4 Pathway =HwyPatrolWgighStation Distance = 2.0 miles
- X/Q = 2.0E-7 sec/m D/Q = 8.5E-10 m-Infant Child ' Teen Adult-Inhala- Food & Inhala- Food & Inhala- Food & Inhala- Food &
Radio- tion Ground tion Ground tion Ground tion Ground Nuclide Pathway Pathway Pathway Pathway Pathway Pathway Pathway Pathway H.-3 2.9E2 Cr-bl 7.6E2' 1.1E6 Mn 54 0- 0- 0-- '1.8E4 3.2E8 Co-57 0- 7.2E3 7.8E7 C0-58 . 2.4E4 8.7E7 Co-60 0- 0- 0- 6.5E4 4.9E9 Sr 89 0- 6.9E4 4.9E3 Sr-90 0- .2.3E7 Zr 95 0- 3.4E4 5.7E7 Nb 95 0- 0- 2.4E4 3.1E7 Te 129m 0- 8.3E3 4.5E6 Cs-134 1.9E5 1.6E9 Cs 136 3.3E4 3.4E7 Cs 137 1.4E5 2.3E9 Ba 140 0- 0- 5.0E4 4.7E6 Ce-141 0- 2.7E4 3.1E6 Ce-144 1.9ES~ 1.6E7 I 131 -0 , 2.7E5. 3.9E6 I -133 4.9E5 5.6E5 ' I -135 1.0E5 5.8E5 UN-10 0- 0- 2.4E4 1.7E8 Inhalation Pathway, units = [" i I* *#yr) Food & Ground Pathway, units a c i 2-75 Rev. 21 2-15-90 APPROVED FEB 211990
TABLE 2-16 DOSE PARAMETER R g FOR SECTOR G Page 3 of 4 Pathway = Sheep (Meat)' Distance = 2.7 miles ' i X/t) = 1.2E-7 sec/m D/0 = 4.8E-10 m- .
-- l Infant ' Child Teen Adult !
Inhala ~ Food & Inhala- Food & Inhala- Food & Inhala- ' Food & Radio- tion Ground tion Ground tion Ground tion Ground Nuclide Pathway Pathway Pathway Pathway Pathway Pathway Pathway Pathway j 1 l H -3: - 1.5E0 1.2E0' 7.0E0 2.lE0 l Cr 51 0- -0 . 5.lEl 1.0E2 1.8E1 2.6E4 Mn-54 7.SE2 1.4E3 4.3E2 7.6E6 Co-57 0- 4.7E3 8.1E3 1.7E2 -1.9E6 Co-58 0- 9.7E3 2.0E4 5.9E2 2.lE6 l Co-60 0- 3.7E4 7.3E4 1.6E3 1.2E8 Sr-89 5.0E4 2.6E4 1.7E3' 3;1E4-Sr-90 1.0E6 8.1E5 5.5E5 1.3E6 . Zr-95 6.3E4 1.lES 8.3E2 1.6E6 Nb-95 2.4E5 4.5E5 5.7E2 1.6E6 Te-129m 6.0E5 4.5E5 2.0E2 6.5E5 . Cs-134 1.4ES. 1.2E5 4.7E3 3.8E7 Cs-136 5.lE3 4.3E3 8.lE2 8.3E5 Cs-137 1.3E5 9.5E4 3.4E3 5.7E7 Ba-140 .5.1E3 4.3E3. 1.2E3 l'.2E5 Ce-141 1.5E3 2.4E3 6.6E2 7.9E4 Ce-144 -0' 1.8E4 3.0E4 4.5E3 4.3E5 I -131 6.6ES -0 ' 4.4E5 -6.6E4 7.0E5 I 133 1.6E-2 8.7E-3 1.2E4 1.3E4 I -135 1.lE-18 6.4E-19 2.5E3 1.4E4 UN-ID 1.lE5 9.5E4 5.7E2' 4.2E6 InhalationPathway, units-]fh" Food & Ground Pathway, units - (m r r) j l f 2-76 Rev. 21 02-15-90 APPROVED #EB 211990
TABLE 2-16 D0SE PARAMETER Rg FOR SECTOR G Page 4 of 4 Pathway = Deer Consumer Distance = 3.3 miles X/Q = 8.8E-8 sec/m' D/Q = 3.2E-10 m ' 1 Infant Child Teen , Adult ] Inhala- Food & Inhala- Food & Inhala- Food &- Inhala- Food & ; Radio- tion Ground tion Ground' tion Ground tion Ground i Nuclide Pathway Pathway Pathway Pathway Pathway Pathway Pathway Pathway q l H -3 2.8El- 2.3E1 3.5El 3.9El Cr 51 5.0E4 1.0EC 9.1El 3.2E5 l Mn-54 7.7E5 1.4E6 .2.lE3 4.lE7 Co-57 0- 4.6E6 8.0E6 8.6E2- ._2 . 3 E 7 Co-58 , 9.6E6- 1.9E7 2.9E3- 4.7E7 Co 60 0- 3.6E7 7.2E7_ 7.8E3 7.2E8 Sr-89 4.9E7 2.6E7 8.3E3 3.1E7 Sr-90 1.0E9 8.0E8 2.7E6 1.2E9 Zr 95 0- 6.2E7 1.lE8 4.lE3 2.0E8 Nb-95 0- 2.3E8 4.5E8 ' 2.8E3 8.2E8 Te-129m 5.9E8 4.5E8 .1.0E3 5.3E8 Cs-134 0- 1.4E8 1.2E8 2.3E4 3.4E8 Cs-136 5.1E6 4.2E6 4.0E3 9.5E6 Cs-137 1.2E8 9.3E7 -1.7E4 4.0E8 Ba-140 5.0E6 4.2E6 6.0E3' 7.4E6 Ce-141 1.5E6 2.4E6 3.3E3 _4.2E6 Ce-144 0- 1.8E7 2.9E7- ~2.2E4 4.9E7 - I 131 6.5E8 4.3E8 3.3E5 5.9E8 1.-133 1.6El 8.6E0 5.9E4 '6.7E4 1 -135 1 lE-15 6.3E-16 1.2E4 6.9E4 UN ID 1.lE8 '9.4E7 2.8E3 1.4E8 InhalationPathway, units y=*]j*h"
" "'V"I Food i i.-Jund Pathway, units = I*
i 2-77 Rev. 21 g 02 15 90 APPROVED FEB 211990 >
2c9 TOTAL DOSE CALCULATIONS 2.9.1 Total Dose to Most Likely Member of the Public l The total annual dose or total dose commitment to any i member of the public, due to releases of radioactivity and i to radiation, from uranium' fuel cycle sources within 5 miles of the Site is.cticulated using..the-following expressions. This methodology is used to meet the dose ! limitations of'40 CFR 190 per twelve consecutive months . I The transportation of radioactive material is excluded 1 from the dose calculations. The. Annual Total Dose is determined monthly for maximum i organ (gas.& liquid), whole body-(gas' & liquid) and thyroid-(gas & liquid) to verify that the Site total (Units 1, 2 and 3) is less than or equal to 25 mrem, 25 mrem and 75 mrem respectively.
.1 Annual Total Organ Dose (kOT(organ)) -
, 12 2/3 -
D (organ) = Z E D (0G) + 0 (0L) + D H,(OG) (2-20) TOT 1-1 j=1 j1 j1 j1 ; ; j = Vnits 1, 2 and 3 1 = months l'- 12** ;
- NOTE: DH8(OG) = 0 for bone j1
**All to be summed over the most recent 12 months.-
Where: n (2-21)- D (0G) = K E C)Riki 4 N k; 1 > each isotope in j1 i=1 specific organ category. year-uci K = 3.1688E-2 sec-Ci 2-78 Rev. 21 02-15-90 4 APPROVED FEB 211990 *- _1. .
-2.9.1 Total Dose to Most 1.ikely Member of the Public (Continued) n = Number of isotopes in the specified organ category
~
Cj ) = Total particulate gas curies released for the month R ik Nk = Controlling location factor,s from ODCM Tables 2 6, Units 1 and 2/3 D
-jl(0L) = month.
Liquid [organ dose for Units the specified organ in mrem for t
~
Reference ODCM 2/3 (1-19), Unit 1 (1-13)) DN '(OG) = Gas organ dose form tritium in mrem for the month. ji (tiote: H
- bone contribution = 0)
.2 A'nnual Total Whole Body Dose (Dg,0fB11 12 2/3 -
D (WB) = r I D (WBL) + DHs(OG) + 0.9 0 (y) + D(Direct);: (2-22) TOT l=1 j=1 jl. jl ji
. ' j.= Units 1, 2 and 3
-1 = months 1 - 12*
*To be summed over the most recent.12 months.'
Where: D (WBL) Liquid whole body organ dose in mrem for the whole month.
.jl (Reference ODCM Units 2/3 (1-19), Unit 1 ODCM (1-13)]l i
DN '(0G) - Gas organ dose'from t'ritium in mrem for the month, ji (from-(2-21)) 0 (y) = Gamma air dose in mrad for the month, ji 0.9 converts mrad to mrem.. (Reference ODCM Units 2/3 (2-14), Unit 1 ODCM (2-10))
.\
4 n 0 (Direct) = r max (D(beach)j] I .0342 (2-23)- j=1 i=1 D(bkgd)4 n i = for.all TLDs per quarter j = for Quarters 1-4 i 2-79 Rev. 21 l 2'15^9 APPR OV ED UR 9.1 1990 l m
2.9.1.2 Annual Total Whole Body Dose (O g iWB).). (Continued) i
- Direct Radiation i The direct radiation levels are evaluated most recently using' cadmium covered TLDs. The TLDs are placed at 59 locations around the site. The average dose from TLDs I 5 to 50 miles from the site'is used as background. These q sites are subject to change.
The background is subtracted from the highest reading olant surrounding area TLD. This value is the direct dose but must be prorated by the occupancy fictor' Example: beach time of 300 hours, or 8' hours -for landward occupancy.
.yr yr.
.3 Annual Total Thyroid Dose (f0T(THYR 0!D))
12 2/3 - - D (THYROID) = r I (D (OG) + D (0L) ; (2-24) TOT 1=1 j=1 j1 j1 j = Units 1, 2 and 3 1 = months 1 - 12*
*To be summed over the most recent 12 months.
Where: D (0G) = Thyroid organ dose from gaseous iodine for the month ji in mrem. (from 2-21) 0 (OL) - Liquid thyroid organ dose for the month in mrem. j1 (Reference ODCM Units 2/3 (1-19), Unit 1 ODCM (1-13)] 3 l i~ i l 2 80 Rev. 21 i- 02-15 90- -i i
-APPROVED FEB 211990
3.0' PROJECTED DOSES 3.1 Liquid Dose Projection The methodology used for projecting _a liquid dose over 31 days. l for Specificat, ion 1.3.1.1 is as follows: j
- 1. Determine the monthly total body and organ doses resulting from releases during the previous twelve months . j l
- 2. Projected dose - Previous 12 months' dose divided by 12 for the total body and each organ. 4
~
3.2 Gaseous Dose Projection The methodology used for projecting a gaseous dose over 31 days for specification 2.4.1.1 is as followsi' ; t
- 1. Determinethemonthiygammabetaandorgandoseresulting ;
. from releases during the previous twelve months.. [
)
- 2. Projected dose = Previous 12 months' dose divided by112 for the gamma, beta and organ doses. .
t 3 t r t i Y 3-1 Rev. 21 02-15-90. APPROVED FEB 211990 f
m 4.0- EQUIPMENT 4W RADIr. ACTIVE LIOUIU~ EFFLUENT MONITORING'INSTRUMENTdTION 9 SPECIFICATION' 4 .1.1 - . The radioactive liquid effluent monitoring : instrumentation - _U
. ichannels showniin Table 4-1 shall be OPERABLE with their j'
alarm / trip setpoints set to ensure:that the limits of JSpecific'ation 1.1.1.are not exceeded. The alar:n/ trip'setpoints - '{ of these channels shall be determined'in accordance with j Section 1.4. APPLICABILITY: At- all times , ACTION: y
~
a.- With a radioactive liquid effluent monitoring instruNentation
- channel alarm / trip setpoint:less conservative than required by the- above- specification, immediately suspend-the release of' radioactive liquid effluents' monitorediby .the affected channel or declare the channel- inoperable. :j
'b. With less.than the' minimum number of radioactive liquid ._ .
j
. effluent monitoring- instrumentat'i6n channels OPERABLE, take the '
ACTION shown in Table 4-1. Exert best efforts to return the- P instrument to OPERABLE status _within 30 days:and, additionally, , if the inoperable instrument (s) remain inoperable for greater. than 30-days,. explain in the' next -Semiannual Radioactive Jl Effluent -Release Report why the inoperability._was not-corrected : in a timely manner.. "_ l i SURVEILLANCE REQUIREMENTS 1 i a .1 Each radioactive' liquid effluent monitoring instrumentation channel 1 shall be demonstrated OPERABLE by performance of the CHANNEL CHECK, o SOURCE. CHECK, CHANNEL CALIBRATION and CilANNEL FUNCTIONAL TEST ; r " operations -at the; frequencie's shown in Table '4~-2.
.2 At least once per 4: hours, all, pumps required to be providing ,
dilution to meet'the site radioactive effluent concentration limits l' of Specification 1.1.1 shall be determined to be operating:and' providing dilution to the'discha'ge structure. F 1 _ l 1 v 4-1 Rev. 21 02-15-90 APPROVED' FEB 21 1990 . , j _s .
+- -~
y ,
.7 _
h__ s:., . _ . . , . -_. .
- s. '.. .,. ,- . ...
~ -
TABLE 4-1 RADI0 ACTIVE LIQUID EFFLUENT MONITORING' INSTRUMENTATION- _ d MINIMUM CHANNELS- ~ OPERABLE ACT10N
. INSTRUMENT'
- 1. GROSS RADI0 ACTIVITY MONITORS PROVIDING ALARM TERMINATION 0F RELEASE
- a. ' Liquid Radwaste Effluent Line - 2/3 RT ~- 7813 -- 1- 28.
- b. . Steam. Generator Blowdown (Neutralization Sump).
.1- 29
- Effluent Line '- 2(3)RT. - 7817 Turbine. Building Sumps. Effluent Line - 2(3)RT .7821 1 30 c..
~
- d. Steam Generator (E088) 81owdown Effluent-1 29 Line - 2(3)RT6759
- e. Steam Generator-(E089) Blowdown Effluent 29 1.
Line .2(3)RT6753:
~
- 2. FLOW RATE HEASUREMENT DEVICES I -- 31
- a. Liquid Radwaste Effluent :Line.
- b. Steam Generator _ BlowdownL (Neutralization Sump):
1, 31
.. Effluent Line - ..u 1 31 -
Steam Generator:(E088) Blowdown Bypass" Effluent Line
~
c. Steam Generator (E089) Blowdown ' Bypass Effluent Line _ I. 3L d. _.,.+-
~
4-2: Rev. 21-02-15-90.
- APPROVED FEB 2l11990
TABLE 4-1 (Continued) TABLE NOTATION ACTION 28 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirements, effluent releases may continue provided that prior to initiating a release:
- a. At least two independent samples are analyzed in accordance with Specification 1.1.1.1 and i b. At least two technically qualified members of the Facility
} Staff independently verify the release rate calculation and 4 discharge line valving; Otherwise, suspend release of radioactive effluents via this pathway. ACTION 29 - With the number of channele OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this l pa + v may continue provided grab samples are analyzed for gross raoiv ntivity (beta or gamma) at a limit of detection of at least 10 ' microcuries/ gram:
- a. At least once per 8 hours when the specific activity of the secondary coolant is greater than 0.01 microcuries/ gram DOSE EQUIVALENT I-131;
- b. At least once per 24 hours when the specific activity of the secondary coolant is less than or equal to 0.01
=
microcuries/ gram DOSE EQUIVALENT I-131: or
- c. Lock closed valve HV 3773 and divert flow to T-064 for processing as liquid radwaste. i ACTION 30 - With the number of channels 0PERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue provided that, at least once per 8 hours, grab j samples are collected and analyzed for gross radioactivity (beta or '
gamma) at a limit of detection of at least 10 ' microcuries/mi or lock closed valve S22U19-MUO77 er S22U19-MUO78 and divert flow to the radwaste sump for processing as liquid radwaste. ACTION 31 - With the number of channels OPERABLE less than required by the , Minimum Channels OPERABLE requirement, effluent releases via this pathway may contir,ue previded the flow rate is estimated at least {; once per 4 hours duri:19 actual releases. Pump curves may be used to I estimate flow.
~
4-3 Rev. 21 02-15-90
,$ i
\
9 APPROVED FEB 211990 l
.. . . . _ . . . _ . _ _ - _ _ _ _ _ = - _ - . . . - . . . - . ..-- .
TABLE 4-2 RADI0 ACTIVE LIOUID EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS CHANNEL CHANNEL SOURCE- CHANNELS FUNCTIONAL INSTRUMENT CHECK : CHECK CALIBRATION- TEST-l l' 1. GROSS BETA' OR GAMA RADI0 ACTIVITY MONITORS PROVIDING ALARM AND AUTOMATICLTERMINATION l OF RELEASE y1
'l
- a. Liquid Radwaste Effluents Line -
.(1)-
2/3 RT - 7813 0 -P -R(2)- Q l- ,
- b. Steam Generator _ Blowdown (Neutralization Sump) . .
a Effluent Line - 2(3)RT .7817 D M R(2). Q(1).
~
- c. Turbine- Building Sumps- Effluent Line ---
D- 'M R(2). .Q(1)
, 2(3)RT - 7821
- d. Steam Generator (E088) Blowdown Bypass Effluent Line' -:2(3)RT-6759 ~ D- :M' R_(2) -Q(I);
- e. Steam Generator.(E089) Blowdown Bypass '
Line D .M- . R(2). Q(1) .. 2(3)RT6753 1
- 2. FLOW RATE MEASUREMENT DEVICES.- -
- a. Liquid Radwaste Effluent line D(3) N.A 'R -Q j
- b. Steam Generator Blowdown'(Neutralization ^ Sump) .
N.A D(3) ~R Q Effluent Line -
- c. Steam Generator'(E088) Blowdown Bypass .
,. ~ D(3): N.A :R. 'Q Effluent Line L
- d. . Steam Generator'(E089) Blowdown Bypass-
- Ls 3) N. A - .R 'Q Effluent Line '
4 -Rev. 21-
'02-15 l -
A
- APPROVEDTFR 2 Y1990
~
l., - _ _ . _ __ _. _ . _ m . v. _ . 2 _ . _ . . . , . ~ e d ._. _ _ ____ __ __ ____ _ __
c -- -
^
., y <
b 1
, < l I
' TABLE 4-2 (Continuedt f , ,
Ig(E NOTATION
-(1) The CHANNEL FUNCTIONAL TEST shall also demonstrate that automatic isolation of: this pathway and control. room alarm. annunciation _ occurs if
- any .of the followingsconditions; exists:*
;1. Instrument-indicates measured levels 'above' the alarm / trip'.setpoint.
I
, .2. Circuit failure.: >
m ?3. Instrument;inbeates aidownscale failure.
~
The_ initial / CHANNkL CALIBRATION shall. be performed' using .one or_ morel of (2)- the referenceistandards certified by. the National, Bureau'of Standards or. usingtstandards thatihave been:obtained from suppliers that participate- , in measbrement assurance activities with NBS.- sThese standardsishall permit! calibrating ~ the syrtem over its intended range of energy and ? ! measurement range.~ For subsequent ~ CHANNEL CAL 1 BRAT. ION, sources that have
~
been-relatea to the initial calibration shall-be wcd.- ; (3)- CHANNEL CHECKi shall consist of verifying: indication.of' flow dc. ing. . periods of release CHANNEL CHECK shall be made at least once per 24 hours on days on which continuous, periodic c or batch releases are made. i
.i I -t r
'I l
p
*If the instrument controls are not in the operate mo'de, n.w iures shall require- !
[ - that the channel be declared inoperable.
'~
!~ i I' L i s - 4-5 Rev. 21; 02-'15 r 1-
.i 1 APPROVED FEB 211990
i N y 4.0, E0VIPMENT : 3
-4.2L RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION SPECIFICATION 4.2.1 The radioactive gaseous effluent monitoring instrumentation 1
channels shown-in Table 4-3 shall.be OPERABLE with-their-
- alarm / trip setpoints set to ensure,that the: limits of ..
Specification 2.1.1 are not exceeded; The; alarm /trir setpoints J.. of these channels shall be determined in accordance with:00CM.- t
- .APPLICABILITYi Atf all t'imes : .l ACTION:: , f
- a. . ~ With a-radioactive gaseous effluent: monitoring instrumentation c;
, channel alarm / trip setpoint less- conservative than, required by, y the above specification,,immediately suspend the release ofi .i4 radioactive gaseous effluents. monitored by the affected channel or-declare the channel' inoperable. b.- With..less'than theiminimum, number of radioactive. gaseous _ . effluent monitoring instrumentation channels:0PERABLE, take the: < ACTION shown in Table 4-3. . Exert best efforts,to returri >the instrument to OPERABLE status within 30 days--and,7 addit.ionally, if the inoperable instrument (s) remain inoperable:for greater: than 30 days,; explain ~in the next Semiannual- Radioactive i Effluent Release-Report why the;inoperability was not corrected. in a timely manner. . SURVEILLANCE RE0VIREMENTSL
.1 Each radioactive ga'seous effluent monitoring: instrumentation channel -
shall be demonstrated. OPERABLE by performance of the. CHANNEL CHECK, SOURCE CHECK, CHANNEL CALIBRATION and' CHANNEL FUNCTIONAL TEST operations'at the frequencies shown in Table 4-4. ; j 1 1 6 l i + 1
. 1 4-6 Rev. 21 ,
I i L#
- dPPROVED - FEB 21 1990 g
u --- 4
+..-
TABLE ~4-3 ' RADI0 ACTIVE GASE0US EFFLUENT MONITORING INSTRUMENTATION - MINIMUM CHANNELS INSTRUMENT : OPERABLE APPLICABILITY: ACTIONi m
- 1. WASTE GAS HOLDUP SYSTEM .
L -a. Noble Gas Activity Monitor - Providing Alarm and Automatic Termination'of Release - 1 -* '35- - 2/3 RT 7808,'2 RT-7865-1 or 3 RT-7365-1
- b. Pror :ss Flow Rate Monitoring Device 1 :
- 36
- 2. CONDENSER EVACUA110N SYSTEM
- a. -
.as Activity Monitor - 2(3)RT-7818 or 2(3)RT -.7870 '1
** 37'
- b. V -
Sampier. '1- ** 40~ c
- c. t '41 ate Sampler -l ** '40
.a 0 >cted Sample Flow Measuring Device **
t d. 1 ..
;36
- e. Pr.vu ' Flow Rate Monitoring Device ,
1(1) ^ *
- 36
- 3. PLAN ~. < TACK
- a. Noble Gas' Activity Monitor - 2/3 RT -.7808f2RT-7865-1 1
*' 37. -
-- l or'3RT-7865-1
'b. Iodine Sampler- 1 /* 40^
- c. -Particulate Sampler _ . 1 *. -40 'j
- 36--
Associated Sample.Flcw Measuring Device:
- d. 'l-
^* -
- e. Process: Flow Rate Monitoring Device 1(2)- 36 .
H
- 4. CONTAINMENT PURGE SYSTEM
~
- .j
-a. Noble Gas Activity Monitor - Providing Alarm and Automatic H Termination of~ Release -'2(3)RT.-'7828,-or.2(3)RT-7865-1 1
*- 38:
- 40 u b. Iodine:Samplerf. - 1-Particulate Sampler 40
- c. ._
1 . Process. Flow Rate Monitoring Device 1*- ' 36 '
- d. 1
~
; Associated Sample Flow' Measuring Device 1: 36- ,i
- e. _
~
~
7 :Rev.n21'
; :02-15-90'
- APPROVED FEB 2:11990.
r __~ _,.~s - - . . . , , . .,,..o-,.. -- , ~ ~ .; J, - u. . A.M .- ...-J . . . , . _ - ,_-.-.c,--,
f si i TABLE 4-3 -(ContinuedF
-. TABLE NOTATION t '* At all' times.
j
~ **- MODES 1-4 with any main- st'eam isolat' ion valve and/or 'any main steam L
isolating. bypass valve not fully closed. (1), 2(3)RT-7818 is: not equipped to monitor process flow. If another means of continuously _ monitoring process flow is not available,e then comply with-i
-ACTION 36.
l, (2) 2/3 RT-7808 is not equipped to' monitor- process flow. -If another means of-continuously monitoring plant vent stack flow is _not- available, then ' d
' comply with ACTION 36.
ACTION 35 - With the number of channels OPERABLE less than required by the . Minimum Channels OPERABLE requirement, the contents of the' tank (s) 3 may be released;to_ the environment: provided that: prior to initiating
'the release: ,
- a. At least two independent' samples _of the tank's: contents are. 3 analyzed, and
- b. At least two technically qualified members of the Facility Staff independently verify.the release rate calculations:and~ i discharge valve lineup; Otherwise, suspend releases' of' radio' active . effluents via thisL pathway.
ACTION 36 - With the' number ofJchannels 0PERABLE:less than required by the - a Minimum channels OPERABLE requirement = ; effluent srelet.ses via this pathway may continue provided the flow rate ist estimated at least l once per 8 hours. System design characteristics may be used to o estimate - flow. ( ACTION 37 - With the number of channels OPERABLE.less than required by. the , l
- Minimam Channels OPERABLE requirement,: eftluent releases via thic !
pathway may continue provided grab; samples are .taken at least once per 12 hours and these samples are analyzed tor _ grossiactivity 3 within 24 hours. ACTION 38 - With the number of channels _0PERABLE'.less than required by the r Minimum Channels OPERABLE requirement, immediately- suspend PURGING- - of radioactive effluents via this pathway. ACTION '9 - Remaining in Technical Specifications. ACTION 43 - With the number 'of channels OPERABLE less than required by the ! Minimum Channels OPERABLE requirement, effluent releases via the i effected pathway may- continue provided samples- are continuously collected with auxiliary sampling equipment as required in y Table 2-1. a j, APPROVdD FEB 2119?P 4-8 rv 21 '
>l- 90
- 4. . -
TABLE 4-4 4
.RADI0 ACTIVE. GASEOUS EFFLUENT MONITORING INSTRUMENTATION SURVIELLANCE REQUIREMENTS CHANNEL MODE FOR WHICH CHANNEL ' SOURCE' ~ CHANNELS FUNCTIONAL- SURVEILLANCE INSTRUfiENT , CHECK CHECK ~ CALIBRATION TEST IS REQUIRED
- 1. WASTE GAS HOLDUP SYSTEM
-a.- Noble Gas Activity Monitor -
Providing Alarm and Automatic .
- Termination of Release -
2/3 RT-7808,~2RT-7865-1, , 3RT-7865-1. P'
- P. R(3)- :Q(1)-
- b. Process Flow Rate Monitoring
' Device P 'N.A R .* J. . ,
Q.
- 2. CONDENSER EVACUATION SYSTEM- ,
^
^
- a. Noble Gas Activity Monitor..-
2(3)RT-7818, 2(3)RT - 7870-1 0 ;M; R(3) -Q(2)- ' ** ', '
. Iodine-Sampler- N.A N.A- **-
_. b. W N. A '
.c. Particulate Sampler . W N.A - N. A ' N.A ** 1
- d. Associated' Sample Flow; q
. Measuring Device. D- N.A' .R Q~
** i
- e. Process Flow Rate Monitoring -
. Device ~(2(3)RT-7870-1) D -N.A R - Q-a q
.i '
.]
~l
{ 4-9 Rev.~21L. .j
~._
02-15-90' , i+. ! - APPROVED FEB 211990
. + .
w.., , . - . -.. - _ , ~ . . ~ , - , , - m .- # .
,. . , - , . ,r,w... - -,. ~. - . - , _ -,,,_m________,___.__.,m,m.
TABLE 4-4 ~(Continued) _
~ - -RADI0 ACTIVE LIOUID EFFLUENT MONITORING INSTRUMENTATION SURVEILL' alice REQUIREMENTS-CHANNEL' MODE FOR WHICH' CHANNEL ' SOURCE CHANNEL. FUNCTIONAL: SURVEILLANCE-INSTRUMENT -CHECK CHECK- CALIBRATIO_N_ TEST IS REQUIRED
- 3. ' PLANT VENT STACK
;Q(2)
.a. . Noble Gas Activity Monitor - D M R(3)~ ,
'2/3'RT-7808,2RT-7865-1, 3RT-7865 *
- b. . Iodine Sampler;
~
W N.A N.A' 'N.A -
. Particulate Sampler N.A- 'N.A.
.. N . A
- c. W .
.l" d .- ' Associated. Sample Flow . .
- O Measureing Device D- N.A R Q
- e. Process Flow Rate Monitoring *
- . Device D N.A 'R Q.
- 4. .'. CONTAINMENT PURGE SYSTEM
.a. = Noble: Gas Activity Monitor -
Providing Alarm and' Automatic. Termination of Release -
- 2(3)RT-7828,2(3)RT-27865-1 .D. .P(4) R(3)- 'Q(1) -*.
~ Iodine Stapler N.A 'N.A- N.A: -
- b. WL N.A- *
- c. Partict. late .Sampleri W .N.A N.A c-
- d. Process Flow Rate Monitoring- *
- Device . .
- D- .N.A R Q
- e. Associated Sample' Flow *-
Measuring Device D JN.A- 'R Q
.h
~ . ,
V 1
~
4-10 Rev. 21 02-15-90 ~ APPROVED FEB 211990 q m-
- s
- _ . . . _ _ . , . _ . , _ ~~. ,,_w.. _ - _ _. - . . . . , . . . . ,. _ .r -,~_.2.%-,-._,_ . - , - - . . ,__.~ ..- ._. . .- . ..,,,
. p ,
t [ TABLE 4-4 (Continued) : TABLE NOTATION. 4
- At lall times. .
- p , ,.
! '** Modes- 1-4 with any main steam isol'ation v'alve and/or any main steam isolating ~ bypass valve- not. fully closed. . (1)~ The' CHANNEL FUNCTIONAL TEST shall= also demonstrate that automatic.- isolation _of this pathway and control _ room alarm annunciation-occurs if any of the following conditions; exists:#; <
- l. ~
l'. - Instrument indicates me'asured levels- above the alarm / trip setpoint.
- 2. ~ Circuit 1 failure.
- 3. . Instrument : indicate,s- a downscale failure; - 0
'(2) The CHANNEL FUNCTIONAL TEST. shall also demonstrate' tht control room" alarm:
. annunciation occurs if any of the' following conditions exists:# -
- 1. Instrument indicates measureblevels. above the alarm lseEpoint. . 1
- 2. Circuit failure.
- 3. ' Instrument ' indicate; a 'downscale failure, (3) Thel initial CHANNEL CAllBRAliM shall be' performed using one- or more of the reference standards certified by the National Bureau of Standards or ;
using standards that have been obtained from suppliers;that participate in measurement assurance activities:with NBS. 'Thest, standards shall permit' calibrating the system over its intended range of energ'y'and .. ' measurement range. For. subsequent CHANNEL-CALIBRATION,: sources that have been related to the initial. calibration shall be used. (4) Prior to each release and at least once per month. $ #If the instrument controls are not set in the operate mode, procedures shall ; call for declaring the channel inoperable. - r . i
.)
.,s 4
4, e i t 4 APPROVED FEB 211990 1 i. 4-11 Rev. 21-02-15-90 < s
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\d a flow diagrams defining the' treatment paths and the components of- the radioactive liquid; gaseous ~and; solid waste management systems >are'shown' fI
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FIGURE 4-5 SONGS ~2 & 3'RADI0 ACTIVE 1.IQUID W4STE TRFfJMENT SYSTEMS ,,( F . 4-13' '- ' Rev. 211 ~
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~-
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~
APPiOVED FEB 21.1990
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2 5.0 RADIOLOGICAL ENVIRONNENTAL N0NITORING
-5.1 The radiologicalienvironmental monitoring. program shall be conducted as j
specified in Table 5-1. ' The requirements are applicable. nt all times ~, j l 5.'1.1 Should the radiological environmental monitoring program l not be conducted as specified in Table 5-1, in lieu of,any ' 1 4
-other report required by-Technict.1' Specification (s)
(U-2,3) 6.9.1, prepare and submit to the Commission,.in: 1 the Annual Radiological Operating ReportJ(see Section. 5.4), ,
' jj a description of the reasons for not conducting.the program '
j as: required.and<the plans-for preventing a recurrence. 5.1 -. 2 : Should the l'evel of radioactivity in:an environmental ' o sampling medium exceed the reporting -levels.of Table 5-2 when averaged over! any calendar quarter, in lieu of any A other report required by Technical: Specification (s). ; (U 2,3) 6.9.1, prepare and' submit to the Commission,L within 30 days from the end of theiaffected calendar? , , quarter.a' Report pursuant to.. Technical Specification (s)' , (U~2,3)-6.9.1.15. When.more than one of,the radionuclides < in Table 5-2 are-detected;in the sampling medium,- this s o report shall be. submitted if: concentration:(1)
~
+ ' concentration'(2) -
+ . h l '. 0 1
-limit level (1) . ii.mit- level .(2) ,
i When radionuclides other then those in Table-5-2 are- .
' detected and are the result of! plant effluents, thisLreport shall be submitted if the potential annual dose to=an h; individual is equal to!or greater than the calendarEyear!
- limits of Specification (s)'(U 2,3)'1.2.1, (U 2,3); 2.2.1: or (U 2,3) 2.3.1, as-appropriate. Thi.s report. is noti required ; if the measured level of radioact41ty was not the result ' of plant effluents;"however, in. such an event, the - condition shall be reported.and: described in the Annual Radiological Environmental OperatingiReport- (see Section j 5.4).. 5.1.3 With fresh leafy vegetable samplescor fleshy' vegetable W camples unavailable from.one or more of the sample; . . . locationst required by) Table: 5-1,i prepare and submit to the ! l s commission' wi thin 30 days, pursuant to? Technical .1 . a 9, Specifications-(U2,3)g6.9.1,;a Special'Repert whick ' ' t , identifies the cause of.. the unavailability of samples and. ' Y, identifies locations for, obtaining replacementssamples. ? d The locations trom'which samples wereLunavailable may then
- Rt ~
q? be' deleted from those required byl Table"5-l', provided the! l 9 4' , , locations- from Lwhich the replacement' samples 'were .obtainedl j r are added to the environmental monitori'ng: program af ?"' g p p, replacementjlocations; L " , q] i , ,1 D1 P y,
- 5.1.4 The radiological environmenthfmonito.'ingNamples shall t z a
, collected pursuant to' Table 5-llfrom ths Jlccatio,ns"giveli in' >Q Tables 5e4 and 5-5 anctfigurei5eleandssh @ bethnalyzede , ,A W'V ;
v
. pursuant to the requiremerats of; Tables 15-1, and EMS. s; f; I a
" 5.1.5 The requiremn'ts of Se: tion' 5.1' are applicable at Mh[ n p[S-i , tines. ty,,, , g o f ",
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TABLE'5-1 -(Co'ntinued) . . _r- ..e
~
Idd5% ' ' RADIOLOGICAL EWIROMENTAL: MONITORING PROGRAM 97 , s - H. Exposure Pathway Nusber of Samples Sampling and ^ - K 36d/or SanetRe - and Gamole Locationsa Collection Freauencva Type and Freauency'of Analyses
'3. -WATERBORNE -
.q:.
- a. ' Ocean 4 10 cations At least once per . Gamma' isotopic analysi' s of each.
month and compcsited f monthly sample. ' Tritium analysis quarterly of cor;:osite sample at least once per 92' days; .
,7
- b. .Orinking Z lodations Monthly at each -
Gamma: isotopic and tritium
- ~ location. analyses of each.' sample'. -
- c. Sediment 4 locations At least once per ' Gamma : isotopic' analysis of each from 184 days. sample.
. . Shoreline ,
~;
i d._ Ocean 5 locations At least once per . Gamma isotopic analysis'of.each
- . Bottom 184 days. - ' sample.
^
~
, Sediments -
',.sqYI' j s
y.
~..
. APPROVED FEB 211990 .
5-3 Rew 21 - s:
.;02-15-90 ~
~
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unmu.a, = I. m - --m.a ew,- n .- a.-. =
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- _ TABLE 5-1 (Continued)
RADIOLOGICAL ENVIROINIENTAL NONITORING ~ PROGRAN Exposure Pathway Number of Samples .
. Sampling and:
- and/or Sample- and Samle locationsa Collection'Freauencva .
Type ~ and Freauency of Analyses
- 4. INGESTION ~
- a. Nonmigratory 3 locations One sample in seasor., ~ Gamma isotopic' analysis 0f. each .
Marine or at least once per~ - edible portions. Animals 184 days ~if not . seasonal. One sample - of each of the follow-ing species: ,,
- l. Fish-2 adult.: species .
such'as perch or - sheephead. . 2'.'Crustaceae-such as crab'or lobster.
- 3. Mollusks-such~as limpets, seahares or class. .
'b. Local Crops 2 locations. Representative. . .
Gamma isotopic. analysis.on edible a - ' vegetables, normally
- portions ' semiannually and;I-131
- l1 leafy. and l' fleshy anal ysis for leafy crops;
- collected at harvest-time.
At;least 2 vegetables collected semiannually
-from each location. ;
' APPROVED ccqmm l 15 Rev.'21~
. 02-15 .
o O w 1,,#%de 9e- g
.T Av w ga.N-nm , . - 4 m.A- . 4 a g .,r%ye ,__ r pp / p -'A m,up g g -e p + - 9 g. e + g .s ni wr y*+5thwe =-
g 9 y-_-' ween j ..Wg s. 43*
M - _-
.~
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. TABLE 5-1:'(Continued) l
- TABLE NOTATION
- a. Sample locations are indicated in the ODCM.
- b. Gamma isotopic analysis means the identification 'and quantification of-gamma-emitting' radionuclides that may be-attributable to the effluents from the facility.
- c. lThe purpose of this sample is to obtain background information. If it'is not practicalfto establish control locations in accordance with the distanceland wind direction' criteria, other sites which~ provide valid background-data may be substituted.
- d. Canisters for the collection'of radioiodine in air are subject to channeling. TThese devices should be carefully-checked before operation in the field or several:should be mounted in series to prevent-loss of iodine.
~
- e. Regulatory Guide 413 provides minimum acceptable performance criteria for thermoluminescence dosimetry (TLD):
systems used for environmental' monitoring. One or more instruments,Lsuch as a pressurized ion' chamber, for measuring-and recording dose rate continuously may be used. in place of,-or in addition to, integrating dosimeters. For the purpose of this table,L a thermoluminescent dosimeter may be considered to be one phosphor and two or more
~
~
phosphors in a packet may' be considered as .two or morr dosimeters. . - Film badgesishould not;be used for measuring direct radiation.
- f. Composite samples should be collected with equipment:(or equivalent) which is capable of collecting an aliquot at time intervals which are very short (e.g.,-hourly) relative'to the-compositing period (e.g., monthly)..
a O 1 Rev. 21-5-5 02-15-90 s. m._4u_-.-'__ __s.a..l_"-_muw A_ " O
'm,.r- y ^' ,'
7: jp ,
~~
' TABLE 5-2 REPORTING LEVELS FOR RADI0 ACTIVITY CONCENTRATIONS IN ENVIR0l#lENTAL SAMPLES-Reporting Leeds Airborne
' Particulate .
= Water or Gases Marine Animals local Crops 4 Analysis (pCi/1) (pCi/m*) (pCi/Kg, wet)- (p'C1/Kg, wet)
H-3 2 x 104 (a) Mn-54 1 x 10 8 3 x 10'
~
Fe-59 4 x 10 2 1 x 10' Co-58 1 x 10' 3xIb' Co-60 3 x 10 2 1 x-10 2 Zn-65 3 x 10 2l x ' 10' ' Zr-Nb-95 4-x 10 2 se
~
I-131 2 0.9 1 x'10'~ Cs-134- 30 10 '1 x 10 8 -
-1 x 10' Cs-137 :50 -20: ~2'x-10' - 2 x 10 ,
Ba-La-140 2 x.10' .
~
(a) For drinking water: samples. .This 'is.40 CFR Part: 141::value.
'5 - Rev. 21:
2-15-90 APPROVED- FEB 21 1990 : e g- _, , ,, l *A - d-q^ e p ,, ,
- m. g
~- - p -
TABLE 5-3
=
g - MAXIMUM VALUES FOR THE LOWER LIMITS OF DETECTION'(LLD)a.c.- Airborne Particulate Water or Gases Marine Animals- Local Crops Sediment-- '# Analysis (pCi/1) (pCi/m ) (pCi/Kg,' wet) (pCi/Kg, wet) -(pci/kg, dry) A gross beta 4 1 x 10 2 H-3 2000 130 g A Mn-54 15 Fe 30 -260 C0-53, 60 15 130 Zn-65 30 260 Zr 30 Nb-95 15
'27 lb 7 x 10
- 60 I-131 5 x 10 ' 130~ 60 150 Cs'134
- 15 6-x 10 ' 150- -80 180 Cs-137 18 Ba-140 '60-La-140 15
~
,s 5-7 APPROVED FEB 2-11990 Rev. 21 02-15-90 f .
em,_..i ,,, ,u_. ,y .g. , _ _ _ __ , , , ' _ _
*'.wh-'s--- mm._
-A'M-- L. .' ____ . _ _ , , _ _ _ _ _ _ , _
JTABLE 5-3' (Conti'nuedl TABLE NOTATION-
- s. .
- a. ?The LLD is the smallest concentration of radioactive material. in a sample !'
E that will be detected:with 95% probability with 5% probability of. falsely'. concluding that a . blank observation represents a "real" signal'. - l- . For a'particular measurement system (which mayLinclude radiochemical ~ separation):, ,
.4.66 s1 -i LLD -- b j'
L -E . V .-2.22 x 10? ._Y.1.iexp; (-Aat)
- Wh'ere: i ,
1- , t LL) is the "a priori" lower limit of detection as defined ab' ove:
-(as microcurie per. unit mass or volume),. -
_s ) is_ the standard deviation' of the background counting rate orJofo - tie counting rate of,a -blank' sample as appropriate.(as counts per , minute),;
~
E~is the counting efficiency.(as counts per. transformation)_, V is the< sample. size- (in units of mass or volume),, 2,22 x 10* is the number d transformations per mint microcurie, i 1 . Y is the fractional radiochemical; yield (when applicable), { t is the radioactive decay' constant for the particular-radionuclide,.and - at is the; elapsed time betweer midpoint'of sample collection and time of counting (for plant effi' tents',- not environmental samples). In calculating the LLD for a radionuclide determined by gamma-ray Spectrometry, the backgroundishalliinclude the typical contributions of-other radionuclides normally presentLin the samples -(e.g. . potassium-40 in
- milk samples). Typical values of E,V,Y _and at shall be:used in the '
! calculctions. 4 The value of sb used in the calc'ulation of _ the.LLD for a lparticular\ measurement system shall be based on the actual ~ observed variance of the background- counting rate or of the ' counting rate o_f the blank samples -(as appropriate) rather than on an. unverified theoretically predicted variance. ' In calculating the LLD for a radionuclide-determined by gamma' ray spectrometry, the. background should include the typical. contributions of '
-'other radionuclides normally present in the samples; Typical, values of E, -
V, Y and at should be used in the calculation, i j'. ,i b , kVPROVED FEB 211990 ; , 58 o x, Rev.,21> y
.y 4,,, ' 02-15f 90 5 -
e> . 4 - 0 ; , n!
-! \ - s t
_i 1!p s
,i -_ i_ :y t[ ,
.j ggi
' ~
'TABL'E 5-3~ (Continuedh .;
y TABLE NOTATION _ It should be recognized"that the LLD.is defined as:an a priori (before the . fact)-limit representing-the capability of.the. measurement system and~not as'
~
1 a oosteriori-(after the fact) limitt or fa particular measurement.* .,
- b. LLD.for drinking water.
r
- c. Other peaks which are measurable-and-identifiable, 'together with the, '
radionuclides in Table 5-3, shall be. identified and Lreported. t
*For a more complete. discussion of.the LLD,: and other detection limits, see
- the following: .
14 y (1). HASL Procidures Manual, HASL-300 (revised annual'ly). . (2) Currie, L. A.,n" Limits:for Qualitative Detection and Quantitative-
- Determination - Application to Radiochemistry" Anal . Chem.: 40,1586-93 l
~!
-(1968). '
(3) Hartwell,'J. K., " Detection Limits for Radioisotopic Counting . Techniques," Atlantic Richfield'Hanford Company Report'ARH-2537 (June.22,- ! 1972).. 4~; e - l
'(
i r. [. . ( i
*4 j
i : [, g 1 APPROVE 3 FEB 211990
- L b, !! , J.
, y.,_ 5 9' p .i Revdll , ,
, , m .f . ,
02-15k90/,lvl. p .:r + ;i, L ta bs, l f'a,: w d'. %* W % . m}{f ns- l
. .n ; x. . + , '1. g 3l ;a , _: T .' }3m 'ff j,V,j .dL ,39.,y
5'.2 -LAND'USE CENSUS.
-5.2.1 A land use census shall be conducted and shall identify'the location of the nearest milk animal, the nearest: residence and the nearest garden
- of greater than-500 square-feet-producing fresh leafy vegetables _ in each of the 16 meteorological sectors within a distance of five miles.
For elevated releases'as defined.~in Regulatory Guide 1.111', Revision 1,' July 1977, the land use census shall also
, identify the-locations of all. milk animals and _all gardens:
of greater than 500 square; feet producing. fresh leafy _ vegetables in each of-the 16 meteorological sectors within a distance of three miles. , 5.2.2 With a lan'd 'use census identifying a location (s) which yields 'a calculated dose or_' dose commitment greater. than
. the values currently being calculated in Technical Specification (V 2,3) 2.3.1, as appropriate, in lieu of any other report required by Technical.. Specification (s)
(U 2,3) 6.9.1,. prepare ~and submit to the Commission within'- 30 days,- pursuant to. Technical Specification (s)l-(U 2,3) 6.9.2, a Special Report which! identifies the new location (s). 5.2.3 With a land use census. identifying a location (s) which: yields a calculated dose or dose. commitment via_ the same _ exposure pathway 20 percent. greater'than at a locat. ion from which samples are-currently being obtained in accordance with Section 5.1 in lieu of any other report required by Technical-. Specification (s) (U' 2,3) 6.9.1~, prepare and ' submit to the Commission within 30~ days,: pursuant to
- Technical- Specification (s) .(U 2,3) 6.9.2, a ~Special Report -
which identifies the new location.- The.new location: shall be added to the radiological' environmental monitoring - program within:30 days, _ The sampling location," excluding the control station location,. having the lowest calculated does or dose commitment via'the;same exposure pathway may be deleted from this monitoring program after October 31 of the year-in which this land.use census was-conducted. 5.2.4 The land use census shall- be conducted at least -once per 12 months;between the dates.of_ June.1 and October 1 using that information which will provide _the best.results, such as by a door-to-door survey, aerial-survey, or by consulting local agriculture authorities. 5.2.5 'The requirements of Section S.2 are applicable at all times. 8 5.3 INTERLABORATORY COMPARISON PROGRAM 5.3.1 Analyses shall be performed on radioactive materials supplied as part of an Interlaboratory Comparison Program which has been approved by the Commission.
- Broad leaf vegetation sampling may be performed at the site boundary in the direction sector with the highest D/Q in lieu of the garden census.
5-10 Rev. 21 02-15 ( -
4 5.3.'INTERLABORATORY~ COMPARISON PROGRAM (Continued)) j 5.3.2 - With' analyses not being performed as required above,Jrecort: the corrective actions taken to prevent a recurrence to , the Commission in the- Annual Radiological Environmental
~
Operating Report. 5.3.3 A summary'of the results obtained as part of the above required Interlaboratory Comparison Program and .in . 3 accordance with Section 5.4.1: of this document shall be - I included-in the Annual Radiological Enviro.nmental Operating-Report (see Section 5.4). 5.3.4 The requirements of Section 5'.3 are applicable at all times. 5.4 ANNVAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT *- l The annual radiological environmental' operating ' reports . 5.4.1 . shall include suunaries, interpretations, and an analysis of trends of the -results of the ' radiological' environmental surveillance activities.for.the report period, including a comparison-with preoperational studies, _ operational , controls (as! appropriate), and previous environmental: surveillance reports and an assessment of the observed-impacts of_the plant operation on the environment." The:
- reports shall also include the results of: land use-censuses required-by Section 5.2. If harmful effects- or evidence of irreversible damage are detected by the' monitoring,/the- -
report shall, provide ' an analysis :of the problem andL a-planned course of: action to alleviate the problem. L The annual radiological . environmental operating Lreports-shall: include summarized and: tabulated results'in the format of Regulatory -Guide 4.8, . December '1975 of all' . i radiological environmental samples <taken:during the report period. in the event' that someL results are' noti available ' for inclusion with the report, the report shall be L submitted noting and explaining-the' reasons for-the missing. , I results. The missing data shall be submitted _as soon as-possible in a supplementary report. j The reports shall also include the following: a summary description of the radiological ' environmental monitoring. , program; a map of all1 samplingit ocations keyed to a table giving distances and directions from the mia-point of. reactor Units 2 and 3; and the results of licensee i participation-in the:Interlaboratory Comparison Program, required by Section 5.3. '
- A single submittal may-be made for a multiple unit station, combining'those
- sections that are common to all units at the station.
i
^
1 5-11 Rev. 21 -
'02-15-90 1 4
~
L . .i 5.5f SAMPLE L'OCATIONS'- . t , The Radiological- Environmental Monitoring' Sample Locations are identified in. Figure 5-1. -These sample locations are described in
~
i Tables 5-4 and 5-5 and indicates the distance in miles and the ' direction, determined from-degrees true north, from.the center of.the l Units 2.and 3 buiiding complex. Table 5-6 gives the sector and l direction designation for the. Radiological Environmental Monitoring
. Sample Location on Map, Figure 5-1.
I 5.6 BASES , MONITORING PROGRAM , l~ 5,6.1 The radiol'ogical-monitoring program required by-this specification provides measurements.of radiation and of: radioactive. materials in. those exposure pathways.and for. those radionuclides, which lead to the highest potential
- radiation exposures of. individuals resulting-from the station operation. This monitoring-program thereby supplements the radiological effluent monitoring program.by - ,
verifying-that the measurable concentrations of radioactive materials and levels of radiation are not higher than: expected on the basis of.the' effluent -measurements and modeling of the environmental. exposure pathways. The. I initially specified monitoring: program will be effective l for at least the 'first three' years-of commercial operation,
~
1 Following this period, program changes _may- be initiated . based on operational : experience. l The detection capabilities required by Table are stateJof-L . the-art for. routine environmental measurements in1 industrial ~ laboratories.. It should be recognized that. the l LLD is defined as an a oriori (beforeithe fact)LlimitL l representing the capability of a measurement system and not as a costeriori (after the fact) limit for.a particular -
- measurement. Analyses shall be performed lin such a manner that the stated LLDs will be achieved under routine-
- conditions. Occasionally background fluctuations,. '
unavoidably small, sample sizes, the-presence of interfering nuclides, or other uncontrollable circumstances-may render these LLDs'unachievable. In such cases,ithe: contributing-factors will be identified and described in the Annual Radiological Environmental. Operating Report. 1 L L L
- APPROVED FEB 211990 5-12 Rev. 21-02-15-90 7
y -, y n r n
5.6) BASES'(Continued) LAND USE CENSUS 5.6.2 This. specification' is provided to. ensure that changes in the use of unrestricted areas'are identified.and that modifications to.the monitoring programLare made if-required by the.results of this. census'.- The best' survey information from the -door' to-door, ' aerial: or consulting l ' with local' agricultural- authorities shall' be~ used. = This; census satisfies the requirements of 'Section IV.B.3'of Appendix I.to'10 CFR Part 50.- Restricting-the census to gardens of greater than 500 square-feet provides-assurancei that significant. exposure pathways via leafy vegetables will be identified-and monitored since a garden of this< ' size is the minimum required to produce the' quantity-(26~ kg/ year) of leafy vegetables assumed in Regulatory Guide 1.109 for consumption by a child.' .To determine this: ' minimum garden size, the following~ assumptions;were used, -
- 1) that 20% of the-garden was used for growing broad leaf-vegetation (i.e., similar to-lettuce.and cabbage),-and 2) a_
-vegetation yield of 2 kg/ square meter.
INTERLABORATORY COMPARISON PROGRAM' l 5.6"3 The requirement foY participation linlan_-Interlaboratory. Comparison Program'is.provided'to'. ensure that-independent.. , checks on the precision and accuracy of:the measurements:of radioactive material'in environmental sample matrices.are
. performed as partz of the quality. assurance program for environmental monitoringrin order to demonstrate that the results are reasonably valid. .
3 i i ( i i t APPROVED FEB 211990 5-13 Rev. 21
'02-15-90 :
,t
'Page 1 ofI6' TABLE 5-4 RADIOLOGICAL ENVIRONMENTAL MONITORING SAMPLE LOCATIONS DISTANCE
- TYPE OF SAMPLE AND SAMPLING LOCATION *** (miles) DIRECTION * '
{ ~~ Direct Radiation-l City of San Clemente (SDG&E Offices) - 5.6 NW 9
~
2 Camp San Mateo-(MCB, Camp Pendleton) 3.5 N- s 3' ' Camp San Onofre (MCB, Camp Pendleton) 2.6 NE 4 Camp Horno-(MCB,> Camp Pendleton) 4.5 E 5 Camp Las Pulgas (MCB, Camp Pendleton) 8.5- E. . l 6 Old Route :101' (East-Southeast) . 3.0 ESE-L 7 Old. Route 101 (East-Northeast) 0.5 ENE L i 8 Noncommissioned Officers Beach Club 1. 5 - , NW- l 9 Basilone Road /I-5-Freeway Offramp 2.0 NW' 10 Bluff (Adjacent to PIC #1) 0.7- WNW-I 11 Former Visitor's' Center 0.3** NW - 12 South Edge of Switchyard :0.2**- E 13 Southeast Site boundary (Bluff) 0.4**- SE J 14 Huntington Beach Generating Station 37.0 . NW 15 Southeast Site Boundary (Office Building) 0.2** SE l 16 East Southeast Site Boundary 0.4** ESE' 17 Transit Dose - - 18 Transit Dose - -- 19 San C1emente Highlands .5.0 .NNW 20 San Clemente Pier 5.3 NW 21 Concordia Elementary School - San Clemente 3.5 NW 22 Former Coast Guard Station - San Mateo Paint 2.7- WNW' 23 San Clemente General Hospital '8.2 NW 24 San Clemente High School 6.0- NW Distance (miles) and Direction (sector) are measured relative to Units 2 and 3 midpoint. Direction is determined from degrees,true north. Distances are within the Units 2 and 3 Site Boundary (0.4 mile in all sectors) and not required by Technical Specification. l
*** MCB - Marine Corps Base Plc - Pressurized Ion Chamber APPROVED FEB 211990 !
.5-14 Rev. 21 02-15-90 .
Page 2'of 6- # TABLE S-4 ; I RADIOLOGICAL ENVIRONMENTAL MONITORING SAMPLE LOCATIONS i s DISTANCE *
-TYPE OF SAMPLE AND SAMPLING LOCATION *** ' (miles) DIRECTION
- Direct Radiation (Continued) 25 Convalescent Home - San'Clemente- -8.0 NW-26- Dana Hills-High School 11.0 NW~ >
27 U.S. Post Office -- Dana Point - 10.6- NW 28 Doheny Fire-Station --Capistrano Beach- -9.5 NW. 29 San Juan Capistrano Fire Station 10.8 NW 30 Laguna Beach Fire Station 17.5 NW
.31 Aurora Park-Mission Viejo 18.7 NNW 32 Santa Ana Police' Department 32.0' NW }
33 Camp Talega (MCB, Camp Pendleton) - 5.7 N 34 San Onofre School- (MCB, Camp Pendleton) .1.9 NW-35 Range 312 (MCB, Camp-Pendleton) 4 ~. 7 NNE 36 Range 208C (MCB, Camp'Pendleton)_ 4.2 NE 37 Laguna Niguel Fire Station. .14.2 NW 38 San Onofre State-Beach Park 3.3 ;SE l 39 Basilone Road Trailer Park (MCB, Camp Pendleton) '1. 4 NNW 40 SCE Training Center'- Mesa-(Adjacent to PIC #3) 0.7 NNW 41 Old Route 101 - East 0.4 E 42 Horno Canyon (MCB, Camp Pendleton) 4,7 E 43 Edson Range (MCB, Camp Pendleton) 10.6' SE 44 Fallbrook Fire Station ' " $ 8.'0' E I l 45 Interstate 5 Weigh Station 2.0 ESE L 46 San Onofre State Beach Park .l'. 0 SE' , 47 Camp Las Flores'(MCB, Camp Pendleton) 8.6 SE L 48 Mainside (MCB, Camp Pendleton) 15.0 ' ESE Distance (miles) and Direction-(sector) are measured relative to Units'2 and. 3 midpoint. Direction'is determined from degrees true north. 'l I l l ** Distances are within the Units-2 and 3 Site Boundary (0.4 mile in all-sectors) and not required by Technical Specification. ! *** MCB - Marine Corps Base PIC - Pressurized Ion Chamber-l APPROVED FEB-211990 l 5-15 Rev.i21 ! 02-15-90
Page:3 of 6 - IABLE 5-4 l
-t RADIOLOGICAL ENVIRONMENTAL MONITORING SAMPLE LOCATIONS-DISTkNCE*
TYPE OF SAMPLE AND SAMPLING LOCATION *** (miles) DIRECTION
- Direct Radiation-(Continued) .
49_ Camp Chappo (MCB, Camp Pendleton) ' 12.8 - ESE ~
- 50 Oceans'ide Fire Station s 15'5
. SE- 1 51' - Carlsbad Fire Station - 18.6 SE .
52 Vista-Fire Station 21. 0 '. ESE
- 53 San Diego County Operations Center 45.0- SE 1 54- Escondido Fire Station 32.0 ESE 55- San Onofre State Beach (Unit 1, West Southwest). 0.2** WSW 56 . San Onofre. State: Beach (Unit 1, Southwest) 0.l** SW 57 San Onofre State Beach (Unit-2) 0.1** SSW-58 San Onofre State. Beach (Unit 3) 0.l** - S 59 SONGS Meteorological Tower 0.3** WNW 60 Transit Control Storage Area - --
61 : Mesa - East Boundary (Adjacent to PIC #4) 0.7 N 62 MCB - Camp Pendleton (Adjacent to PIC #5)-
- - 0.6 . NNE 63 MCB - Camp-Pendleton-(Adjacent to PIC #6) 0.6 NE-64 MCB - Camp Pendleton (Adjacent to PIC #7) .0. 5 ENE 65 MCB - Camp Pendleton (Adjacent to PIC #8) 0. 7- LE
]
-66 San Onofre State Beach (Adjacent to PIC~#9) 0.6 ESE Former SONGS Evaporation Pond (Adjacent to~PIC #2) 0.6 67 NW
}
68 Range 210C (MCB, Camp Pendleton) 4.3 ENE 99 Transit Dose - - i Distance (miles) and Direction'(sector)'are measured relative to Units'2 and 3 midpoint. Direction is determined from degrees true north.
** Distances are within the Units 2 and 3 Site Boundary (0.4 mile in all-sectors) and not required by Technical Specification. ~ *** MCB - Marine Corps Base PIC - Pressurized Ion Chamber APPR'0VED FEB 211990 5-16 Rev. 21 ,
02-15-90
~
Page_ 4: of L6.- -l TABLE 5 ; RADIOLOGICAL' ENVIRONMENTAL MONITORING SAMPLE LOCATIONS-I DISTANCE * .
~ TYPE OF SAMPLE AND SAMPLING LOCATION (miles) DIBI.CTION*
Airborne , 1- City of San Clemente (City Hall) 5. 5 ~- NW .
'2' Camp-San Onofre (Camp Pendleton) 1.8- NE~ !
3 Huntington. Beach Generating Station 37.0 NW. i 5 Units 2 and 3 Switchyard 0 13** NNE ; 6 SONGS' Meteorological Tower -- 0 . 3 ** WNW 9 . State Beach Park 0.6 ESE : 10' Bluff 0.7- WNW \
'll Mesa E0F~ 0.7 NNW' 12 Former SONGS Evaporation Pond 0.6- NW 13 Marine Corps Base'(Camp Pendleton East) 0.7 E .
1 Soil' Samples 1 Camp San Onofre~ 2' . 5 NE 2 0ld Route 101 - East Southeast 3.0 ESE
- 3. Basilone Road /I-5 Freeway Offramp 2.0 NW 4 Huntington Beach Generating Station 37.0 NW t 5 Former Visitor's Center 0.=2** NNW 7
Ocean Water ~ A Station Discharge Outfall - Unit 1- 0.5 SSW_ L B Outfall - Unit 2 0.7 SW-l C Outfall - Unit 3 0.7 SW D- -Newport Beach 30.0 NW s c Distance (miles) and Direction-(sector) are measured relative to Units 2 and 3 midpoint. Direction is determined from degrees true-north.
** Distances are within. the Units 2 and 3 Site boundary (0.4 mile in all.
sectors) and not required by Technical Specification. APPROVED FEB 211990 ; 5-17 Rev. 21' L 02H15-90 l
W y
-Page 5 of 6-TABLE 5-4 RADIOLOGICAL ENVIRONMENTAL MONITORING' SAMPLE LOCATIONS-DISTANCE *
~ l TYPE OF-SAMPLE AND SAMPLING LOCATION (miles) ~0IRECTION* Drinking Water
,l' Tri-Cities Municiphl Water District-Reservoir 8.7- ,NW "j
2' -San Clemente Golf Course ,Well'- -3.5' NNW 3- 'Huntington Beach. 37.0. -NW! Shoreline Sediment (Beach. Sand) l 1
~
San Onofre State Beach (0.6 mile Southeast) 0.6-. :SE. 2 San Onofre: Surfing Beach.- 0.9 NW 1 3 San Onofre State' Beach (3.1 miles. Southeast)- 3.1' .SE { 4 Newport' Beach (North End) -30.0 NW-Local crops ] 2.6
~
San Mateo Canyon (San Clemente Canyon) NW-1 22.0; SE-21 Southeast of Oceanside ,
'O San Clemente Resident with Garden 4.1 NW 1
i [ -l i ~ 1 l l l Distance (miles) and Direction (' sector)'are measured relative to Units'2 and 3 midpoint. Direction is determined from degrees true north. ' I
- Page 6 of 6 l APPROVED FEB 211990 l 5-18 Rev. 21
.t 02-15-90
TABLE 5 RADIOLOGICAL ENVIRONNENTAL MONITORING SAMPLE LOCATIONS l DISTANCE
- l' TYPE OF SAMPLE AND SAMPLING LOCATION (miles) DIRECTION *'
Non-Migratory Marine Animals f A - Unit l'Outfall 0.6 WSW ! B Units 2 and 3 Outfall 0.7 SSW C Newport Beach 30.0 NW J. - Kelp )' A San Onofre Kelp Bed 1.5 S-B San Mateo Kelp Bed 3.5 WNW- . C Barn Kelp Bed 6.6 !SSE. -l .D _ Newport' Beach 30.0 NW i Ocean Bottom Sediments A ' Unit 1 Outfall (0.5 mile West)~ 0.5 W-B Unit l'0utfall (0.6 mile West) 0.6 W-C' Unit 2 Outfall 0.8 -SSW' D Unit 3 Outfall 0;9 S-E Newport Beach 30.0 NW ;
}
.i I
i i Distance (miles) .and Direction (sector) are measured relativa to Units 2 and . 3 midpoint. Direction is determined from degrees true north. .i l APPROVED FEB 211990 5-19 Rev. 21 ;
^02-15-90 j
.u (TABLE 5-5I ,
PIC - RADIOLOGICAL ENVIRONNENTAL MONITORING l.0 CATIONS- . Theta DISTANCE
- PRESSURIZED ION CHAMBERS (Dearees)* Meters miles DIRECTION / SECTOR *'
S1' San Onofre Beach 298* 1070 .0.7 WNW P S2 . SONGS Former Evap. Pnd 313' 890- 0.6 NW _ Q1 S3- Japanese Mesa- 340' 11150 -- 0 . 7 NNW: :R S4 MCB.- Camp Pendleton 3 1120. 0.7 N _A-SS MCB - Camp Pendleton 19' 1050 i 0.6~ NNE: B S6 MCB Camp Pendleton 46' -940- 0.6~ NE 'C S7 MCB - Camp Pendleton 70* 870 0.5 ENE D '! S8. MCB - Camp Pendleton 98' 1120 0.7 E- 'E
$9 San Onofre State Beach 121' 940 ' O.6 ESE F l
.i Distance (meters / miles) and Direction (sector) are measured' relative to Units-2 and 3 midpoint. Theta direction is determined ~from degrees true north, i 1
o APPROVED FEB 2110o0 5-20 Rev. 21 02-15-90 i
. . , . . +
TABLE 5-6~ SECTOR AND DIRECTION DESIGNATION FOR RADIOLOGICAL ENVIRONNENTAL NONITORING SANPLE LOCATION MAP' ) DEGREES TRUE NORTH- ~ FROM ' SONGS 2 AkD- 3 MID-POINT NOMENCLATURE!
. Sector Center Sector 22.5'- ;
Limit Line Limit Sector
- Direction j 348.75 0 & 360 -11.25: A N' ]
11.25.- 22.5 =33.75- B NNE : 33.75- 45.0 56.25 C NE l 156.25 67.5 '78.75 D ENE-78.75 90.0 101.25 E- E-101.25- .112.0 123.75 .F ESE-123.75 135.0- 146.25 G SEL 146.25 157.0 168.75 H SSE, 168.75 180.0- 191.25 J S-191.25 202.5 213.75 K SSW' 213.75 225.0 236.25 , L SW- , 236.25 247.5 258.75 M WSW 258.75 270.0- 281.15 N W
- l. 281.25 292.5 303.75 P WNW- ;
I 303.75 315.0 326.25 Q .NW- f 326.25 137.5 348.75- R. :NNW- i Distance (miles) and Direction (sector) are measur'ed relative to Units 2 and_3 midpoint. Direction is determined from degrees true North'. , j i' 3103c. man i i APPROVED FEB 211990 I 5-21 Rev. 21 02-15290 [
4
'6.0'O ADMINISTRATIVE 6.I' DEFINITIONS )
The defined terms of this section appear-in capitalized type and are ; applicableLthrough these Specifications 1 ACTION ; J 6.1.1 ACTION shall be that part.of a~ specification which
- prescribes remedial. measures required under designated conditions.
-CHANNEL CALIBRATION 6.1.2 J A CHANNEL CALIBRATION- shall .be the adjustment', as -
necessary,Jof the~channelLoutput such that it responds with the necessary range and accuracy to known) values of the parameter which-the' channel monitors. The CHANNEL- . . _ j
. CALIBRATION shall~ encompass the entire channel, including ,
the sensor:and alarm and/or trip functions, and: shall i include the CHANNEL FUNCTIONAL TEST. -The CHANNEL-CALIBRATION may be. performed by any series 'of sequential, overlapping' or total channel steps such that1the entire ;
. channel is calibrated.
CHANNEL CHECK 6.1.3 A CHANNEL CHECK .shall' be the qualitative assessment of- e channel behavior during operation byLobservation. This - determination shall include,' where' possible, comparison of ' theLchannel indication and/or status'with-other indications-and/or-status derived =from independent instrument 7 channels measuring the same parameter, CHANNEL FUNCTIONAL TEST 6.1.4 A CHANNEL FUNCTIONAL TEST shall be: l_
- a. Analog channels - the injection of:aLsimulated signal' l
into channel as close to the sensor as practicable to- ! verify.0PERABILITY, including alarm and/or trip-functions. l- -b. Bistable channels - the. injection of a simulated- , signal into the = sensor to verify 0PERABILITY, [ including- alarm and/or trip. functions. i ' c. Digital computer channels. - the exercising of the ! digital computer hardware using diagnostic programs l
- and the injection of simulated process. data into-the l- channel to verify OPERABILITY.
APPR10VED FEB 211990 6-1 Rev. 21 , l 02-15-90 l . 4
~. _ , . _
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d 6.0 ADMINISTRATIVE (Continued) i 1 ( : DOSE E00lVALENT Iil31L l l .6.1.5 -DOSE EQUIVALENT l-131:shall be concentration of I-131 1 D (microcuries/ gram) which alone would produce the same . - , t thyroid dose'as the quantity-and isotopic mixture of.1-131, I-132, 1-133, 1-134,- and-I-135 actually-present.. The thyroid dose c'onversion factors used for this calculation . E shall be. those listed in Table III1of TID-14844, . . 1
" Calculation of Distance Factors for Power and Test Reactor '
-Sites." .
FRE0VENCY NOTATION 6.1. 6 - The FREQUENCY NOTATION-specified for~the performance of. . i
- Surveillance Requirements .shall correspond to the intervals defined in Table 6.2. .;
-GASEOUS RADWASTE TREATMENT ^ SYSTEM i
6.le7 .A; GASEOUS ~RADWASTE TREATMENT SYSTEM:is any. 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. 'i OPERABLE --OPERABillTY'
^
6.1.8l ~ A system, . subsystem, train,- componentvor device shall be OPERABLE or have OPERABILITY-when it-is' capable off performing its specified function (s),Jand when ally necessary. attendant instrumentation, controls, electrical-power, cooling or seal water, lubrication or other - auxiliary equipment that are required-for.the' system,- 1 subsystem,: train, component or device-to perform its-function (s) are _ also capable. of performing' their related support function (s).
~
PURGE - PURGING L 6.1.9 PURGE or PURGING isithe controlled process of oischarging air or gas from a confinement to maintain temperature, !
- pressure- humidity, concentration o'r other: operating condition, in such. a manner that -replacement . air or gas is 4 required to purify the confinement.- q VENTING t
6.1.10 VENTI.NG is the controlled process.of 4 :: charging air or gas-from a confinement to maintain temp W .ure, pressure, ' humidity, concentration or other operating condition, in such a manner that replacement air. or gas is not provided or required during VENTING. Vent, used, in system names, , [ does not imply a VENTING process, t L APPROVED FEB-211990 ; i L 6-2 Rev. 21 ' 02-15-90 11
, . , .5
> J6,0 ' ADMINISTRATIVE -(Continued)'
SOLIDIFICATION: 6.1.'11 -SOLIDIFICATION shall be the conversion of radioactive wastes from liquid systems to a homogeneous -(uniformly distributed), monolithic, -immobilized solid with definite ; volume and shape,: bounded'by a stable ~ surface of distinct
- outline on all sides-(free-standing).;
SOURCE' CHECK
- 6.1.~12 A SOURCE CHECK shall be the-qualitative assessment of . '
channel response'when the channel" sensor is exposed to.a radioactive source. .c THERMAL POWER
~ 6.1.13 - -THERMAL POWER shall be the total. reactor core heat transfer - '
rate to the reactor coolant. if b a
-1 a
APPROVED FEB 211990 6-3 Rev.-21 15-90 l p , n, ,- , p
e TABLE 601 OPERATIONAL MODES-. J REACTIVITY % 0F RATED AVERAGE COOLANT. 1 OPERATION MODE ~ CONDITION. K,77 THERMAL POWER * -TEMPERATURE
- 1. POWER OPERATION. 2 0.99 > 5%
1 350*F :
' 2. STARTUP 2 0.99 s.5% . 2 350*F.~ . 3.' HOT STANDBY < 0.99 0 2 350*F.
- 4. HOT SHUTDOWN :< 0.99 0 350*F> Tavg>200*F
- 5. COLD SHUTOOWN < 0.99 0 ;s 200*F. ,
L 6. REFUELING ** s'0.95'- 0 5.140*F , I l L i s
- Excluding decay heat.
** Fuel in the reactor vessel with the vessel head closure' bolts less than fully tensioned or with the: head removed.
7 s 1 APPROVED FEB 211990 6-4 .Rev. 21 < 02-15 : t . . . - . .
.> -TABLE 642
.FRE00ENCY-NOTATION NOTAT10N' FRE0VENCY
, S -At least once per 12. hours L r D - At least once per 24 hours , b ! W1 lAt' least once per 7 days-j M .At least o'nce per 31 days Q- At least once'.per 92 days, SA - At least once.-per 184' days : R At least once per:18 months-
'i
' S/U Prior to each' react'or'startup. i P. Completed prior:to each release'-
J;
-4 N; A'. :Not applicable:
Refueling Not :to exceed. 24' months Interval r
. j-l 4
i
- e a
[ t 4 i A APPROVED FEB 211990 6-5 Rev. 21 ! 02-15-90 ., j
_g,; . ..
'6.21 ADMINISTRATIVE CONTROLS' SEMIANNUAL'RADI0 ACTIVE EFFLUENT-RELEASE'REPORTO 1
.6.2.1- ' Routine radioactive effluent . release reports covering the~ ,
operation of_ the-unit during the previous 6 months of, _. operation shall .be. submitted lwithin 60 days after January 11 l and ' July 1 of ~each year. The' period of the first report
.shall- begin.with_ the date of= initial criticality..
6.2.2- The radioactive effluent release reports shall-include a ! summary of the quantities of radioactive: liquid and gaseous F effluents and. solid waste 1 released from the unit as J outlined in Regulatory Guide 1.21, " Measuring,. Evaluating, J
.and Reporting Radioactivity in Sol,id Wastes and Releases of
-Radioactive Materials in Liquid.and Gaseous Effluents'from Light-Water-Cooled Nuclear Power P1 ants, " Revision:1, June ,
'1974; with data summarized on a quarterly basis following .
the format of/ Appendix'.B thereof. The' radioactive' effluent release . report to be submitted 60
. days afterTJanuary 1'each year shall7 include an annual-isummary of hourly meteorological data collected over; the- ..
previous. year. This. annual summary may .be:either in the- !
- form of an hour-by-hour listing of wind speed,' wind . _
direction,>and' atmospheric' stability, and precipitation 1(if-measured) on~ magnetic tape, or.'in the form'ofistability. 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 dur_ing< the
. previous calendar year; :This;same report shall also include an. assessment of-the. radiation doses from ,
! radioactive liquid and ga'seou's effluentsito members of the public due to.their activities -inside the site boundary- l (Figure:1-2:and 2-2).during.the report period. All-assumptions used~in making these--assessments (i.e.,
specific activity, exposure, time: and' location) shallL be ' included:in:.these: reports 1The meteorological conditions concurrent with the time--of release ofcradioactive:
~
q materials in gaseous: effluents (as determined by" sampling frequency and measurement).shall be used_for determining the; gaseous: pathway doses.~ The assessment.of radiation <
' doses shall be performed ^ in accordance'with the10FFSITE DOSE CALCULATION MANUAL-(0DCM). j l4 APPROVED FEB 2-11990 6-6 -Rev. 21 02-15-90 d s - ,. . - -
, ~ 6. 2 ADMINISTRATIVE CONTROLS -(Continued)-
The radioactive: effluent release report to be submitted 60 days after January 1 of each year shall-also include an- u assessment 1of radiation doses to.the.likely most exposed ! member of the- public,from reactor releases;and other nearby 1 uranium fuel cycle sources:(including doses from primary effluent pathways and direct radiation) for the previous 12 ; consecutive months-to show conformance-withc40;CFR 190, Environmental Radiation Protection Standards'for Nuclear - Power Operation. . Acceptable < methods: for calculating the dose icontribution from:1iquid and -gaseous effluents.are given in regulatory Guide 1.109,LR ev. 1. ! Th'e radioactive effluents release shall include the. following 'information for each type of solid waste shipped
.offsite during the report period:-
. a. Cont'iner a volume,
- b. . Total curie quantity-(specify whether determined' (
by measurement.or: estimate),
- c. Principal radionuclides .(specify-whether determined by measurement'or estimate), #
- d. -Type lof waste (e.g., spent resin,fcompacted dry waste,evaporatorbottoms),-
-e. Type of container (e.g., LSA,' Type A, Type-B, !
LargeQuantity), and V i
- f. Sc11dification ~ (e.g. , ce:nent,1: urea; formaldehyde) . ,
The radioactive effluent release reports: shall> includo unplanned releases from the ' site- to unrestricted areas:of: L radioactive materials in gaseous and liquidfeffluents on a quarterly' basi s. I The radioactive effluent release reports shall- include-any changes-to the PROCESS CONTROL PROGRAM (PCP)'made during. .i the reporting period. l
)
L* A single submittaT may be made for a multiple unit station. The submittal l should' combine those sections that are common to all! units at-the Station;-
- however, for units with separate radwaste systems, the submittal shall specify l the releases of rauioactive material from each unit. "
i p APPROVED FEB 211990 l 6-7 Rev. 21 ! ! 02-15s90 b ,
. , , e . .
T
'6.3 . MAJOR CHANGES TO'RADI0 ACTIVE WASTE TREATMENT SYSTEMS (Liquid, & Gaseous)
Licensee: initiated major changes to-the radioactive waste systems (liquid =& l
? gaseous):- .
1
~
- 1. Shall be . reported to the Commission;in the Monthly.0perating Report _for '
the period in which the-evaluation was performed pursuant to-6.5.2. The discussion of each change shall contain:
- a. A summary of the evaluation that led to .the determination that the ;
change could be made,in accordance with:10 CFR 50.59; 4 .b. . Sufficient detailed information to' totally support =the1 reason for the change without benefit.of ' additional or' supplemental 1 information;
'4
- c. A detailed description of-the equipment, components'and processes involved and the interfaces-with other plant systems:-
1
.d. An evaluation of_the change which shows the predicted releases-of radioactive' materials :in ~ liquid and gaseous effluents that differ from those previously predicted in the. license application and.
~
amendments thereto:- . e.. An-evaluation of the change which.shows the. expected maximum i exposures. to individual in- the. unrestricted area and- to the- 4 generalspopulation that differ from'thoselpreviously estimated in the license application and: amendments thereto;_
- f. A comparison oof the predicted releases off radioactive. materials,.
in sliquid and -gaseous; effluents to. the actual release for the- ' period prior to when thefchanges are to.be made;, t-
- g. An estimate of-'the exposure to plant operatingipersonnel as a '
result of. the change;- and
- h. Documentation of the fact that the change was reviewed and found acceptable: pursuant to 6.5.2.
1 2. Shall become effective upon review and acceptance pursuant to _6.5.2. , a i s t i APPROVED FEB 311990 4 6-8 Rev. 21 > 15-90 s
- w w
e- ..
.6.4: BASES LIOUID EFFLUENTS CONCENTRATION (1.1)
- 6. 4 .1 - This specification is provided to ensure that the .
concentration of radioactive materials released in liquid waste effluents-from the site will be less than-the concentration -levels specified in110.CFR'Part 20, Appendix B,: Table II, Column: 2. This'1 imitation provides additional assurance that the, levels-of radioactive materials in- , bodies of- water outside the site will! result iniexposures within (1)-the Section II.A design objectives of Appendix-I,:.10 CFR 50, to an individual,= and (2). theylimits of 10 CFR 20.106(e) to the; population.- The concentration limiti for dissolved or entrained . noble l gases is based upon?the . assumption that Xe-135 is the controlling radioisotope-and L
. itiMPC-in: air ~(submersion) was converted to an equivalent: 1 concentration in' water using-the methods-described in:
j International Commission on Radiological;Protectionf(ICRP) Publication 2. J DQS1 (1.2) 'j 6.4.2 This specification;is provided to implement- the require - :i ments of Section:II.A,1111.A and IV.A~of Appendix I, 10 CFR >
, Part 50. The Limiting Condition for-0peration implements j the guides' set forth in Section II.A of1 Appendix I.- The- j ACTION: statements provide the required-. operating:flexi ' j bility and at the same time _ implement.the guides set'forth H in:Section IV.A ofcAppendix11 to assure-that.the releases 9 of radioactive material in liquid effluents will be kept j "as-low as is reasonably achievable." -The dose calcu-1 lations:in the ODCM _ implement the requirements in Section' i III.A of Appendix'I that conformance with the guides of<
Appendix I be shown by calculational procedures based on j ' models and data,- such _that the ~ actual- exposure of an-individual through. appropriate pathways'.is unlikely to be substantially underestimated.- The equations specified in the ODCM for calculating the' doses due to the actual release rates of radioactive materials:in liquid effluents 1 are consistent with the methodology: provided in Regulatory A Guide 1.109, " Calculation of Annual Doses! to- Man from Routine Releases- of Reactor Effluents' for<the Purpose of Evaluating Compliance with 10 CFR Part 50; Appendix:1,- ,
-Revision 1, October 1977 and Regulatory Guide 1.113, ;
" Estimating Aquatic Dispersion of Effluents from Accidental and Routine Reactor Releases for the-' Purpose of i Implementing Appendix I," _ April' 1977. ,
This specification applies to the release of 1iquid effluents from each reactor at the site. For units with , shared radwaste treatment systems, the~ liquid effluents from the shared system are proportioned among the units sharing that system. APPROVED FEB 211990 - j , 6-9 Rev. 21 h 02-15-90 ! 1
~- - .
.6;4L BASES C(Continued)L j k LIOUID WASTE TREATMENT (1.3) 6.4.3 .The_ OPERABILITY of the liquid radwaste. treatment system
~
j
' ensures that this system will be available for use whenever
~
l xliquid effluents. require treatment prior to release to the H
, . environment. The requirement.that'the' appropriate portions ,,
of this system be used when1 specified provides assurance that the releases of radioactive materials in' liquid ; effluents will be kept "asilow as 1s reasonably: achievable."' ~ This specification . implements the requirements of 10 CFR Part 50.36a, General, Design '. T l Criterion 60'of Appendix'A to 10!CFR:Part 50 and,the-design : objective given in Section:II.0-of Appendix l' to 10 CFR ' , Part 50. The specified limits governing the use of appropriate portions of the liquid-radwaste treatment' system were specified as a suitable- fraction of ~the. dose' -- design objectives set forth in' Section II. A of Appendix. I, 10 CFR Part 50, for. liquid effluents. l GASE0US EFFLUENTS. DOSE RATE _(2.1) - 6.4.4 This specification is,provided:to ensure'thatLthe dose at; any time at the site boundary from gaseous effluents from all units on the site'will be within the annual dose limits of 10 CFR Part 20 for' unrestricted: areas. The annual--dose limits are~the doses associated with=the concentrations of-10_ CFR Part 20,, ' Appendix: B, Table :11, , Column 1. - L These limits provide reasonable assurance that _ radioactive material discharged in gaseous effluents ~will not result in- 1 the exposure 'of an individual in an unrestricted area, either within or outside the site boundary,.to. annual r average-concentrations exceedingtthe 1imits specified in Appendix B,. Table II of 10 CFR Part 20 (10 CFR-Part 20.106(b)). For individuals who may:at-times.be within'the site boundary, the' occupancy of.the individual?will be- : sufficiently low to compensate for any. increase in the: atmospheric diffusion' factor above that-for the. site boundary. The_specified release rate limits restrict,nat
~
all times, the corresponding gamma and beta dose rates above- background to an individual at or beyond the site .; boundary to-less than or equal ~ to 500 -mrem / year to the total body or to less' than or equal. to 3000 mrem / year. to the skin. These-release rate limits also restrict, at all times,'the corresponding thyroid dose raterabove background to a child via the inhalation pathway to less than or equal
!~
to 1500 mrem / year. This specification applies to the release of' gaseous y effluents from all reactors at the site. For. units with-shared radwaste treatment systems, the gaseous effluents - from the shared system are proportioned among the units sharing that system. APPROVED FEB 211990 : 6-10 Rev. 21 15-90 !
4 6.4 BASES (Continued)l DOSE - NOBLE GASES (2.2)
-6.4.5- This specification 'is provided to implement.the requirements of Sections II.B. III.A and IV.A of ,
Appendix I,-10'CFR Part'50. The. Limiting Condition for .
' Operation-implements the guides set forth in Section II.B
-of-Appendix.I. The ACTION statements provide the' required operating flexibility and.at the same time implement the guides ~' set forth' in' Section IV. A of. Appendix _ I to assure ithat the releases lof_ radioactive. material ;in gaseous' l
L effl9ents will-be kept."as low as is. reasonably .. - 1
-achievable."- The Surveillance Requiroments implement the requirements in Section III.A'of~ Appendix I_that_ g
- e conformance with the guides of. Appendix.I be shown~by _
1 calculational procedures based on models.and data such thatl ' the actual exposure'of_an individual through appropriate pathways is unlikely to be substantially underestimated. The dose calculations: established in the' 00CM for. calculating the~ doses due:to-the actual release rates of- . _ 4 radioactive noble gases in gaseous effluents ~ are consistent , with -the methodology provided in Regulatory Guide 1.'109, !
. " Calculation of Annual Doses to Man from Routine Releases- !
of Reactor Effluents for the Purpose of Evaluating _ . Compliance with 10 CFR Part'50, Appendix I,"' Revision 1, October'1977-and Regulatory Guide _.1.111,' " Methods form - Estimating Atmospheric Transport'and Dispersion.of Gaseous . Effluents in Routine Releases -from Light-Water. Cooled. Reactors," Revision 1,; July 1977. The 00CM equations a
'provided for' determining: the airj doses at the site, boundary
.are' based upon the historical.' average atmospht.ric '
j conditions. -i . DOSE - RADIOI0 DINES. RADI0 ACTIVE MATERIALS IN PARTICULATE FORM'AND. TRITIUM (2.3)' -. 6.4.6 This specification is provided to implement. the _. requirements of Sections.II.C, III.A and1IV.A of. Appendix 1, 10--CFR Part 50.. The Limiting Condi-tions for Operation . are the guides; set forth in Section II.C:of-AppendixL1.
- The ACTION state'ments provide =the required operating' .
-i' flexibility and at the same time implement the guides set forth in Section IV.A of Appendix I to assure-that the
- A releases of radioactive materials in gaseous effluents 'will i be kept "as low as is reasonably achievable." - The 00CM calculational methods specified in the Surveillance i
Require-ments implement the requirements in~Section III.A , i 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 . exposure.of an . individual through appropriate pathways ~is unlikely-to be substantially underestimated. .The ODCM calculational methods j APPROVED FEB 211990
-i 6-11 Rev. 21 1 H
02-15-90 , w y , , -- - - y . . . ,,.9 y v
r 6.4 M KS -(Continued) for calculating the doses due to the actual release rates of the subject materials are consistent with the methodology provided in Regulatory Guide 1.109,
" Calculation of Annual Doses to Man from Routine Releases I of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix 1," Revision 1, ;
, October 1977 and Regulatory-Guide 1 1.111, " Methods for i Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light Water-Cooled ,
Reactors," Revision 1 July 1977. These equations also
?rovide for determining the actual doses based upon the i 11storical average atmospheric conditions. .The release:
rate specifications for radioiodines, radioactive ' materials in particulate. form and tritium are dependent on the existing radionuclide pathways to man, in_the unrestricted area. The 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 ; consumption by man, 3) deposition onto grassy areas where milk animals and meat producing animals graze with consumption of the milk and meat by man, and 4) deposition on the ground with subsequent exposure of man. ; GASEOUSRADWASTETREATMENT.(2.4)- 6.4.7 The OPERABILITY of the GASEOUS RADWASTE TREATMENT SYSTEM and the VENTILATION EXHAUST TREATMENT SYSTEM ensures that the systems will be available for use whenever-gaseous effluents require , treatment prior to release to the environment. ; The requirement that the appropriate portions of : ( these systems be used, when specified,_provides L 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-objer"es given in.Section 11.0 of Appendix 1 to 10 Ci?. art 50. The_specified limits governing the use of appropriate portions of the systems 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 Part 50, for gaseous ; effluents. APPROVED FEB 211990 6-12 Rev. 21 ; 02 15690 ; 1
. . . . l. - . . -
6.i MSIS (Continued) l TOTAL DOSE (2.5) 6.4.8 This specification is provided to meet the dose limitations of 40 CFR 190. The specification requires the preparation and submittal of a Special Report whenever the' calculated doses from plant: radioactive effluents exceed twice the design objective doses of Appendix 1. For' sites containing up to 4 reactors, it is highly
- unlikely that the resultant dose to a member of the public will exceed the dose limits of 40 CFR 190 if the individual reactors remain within the reporting requirement level. The Special Report will describe a course of action which should result in the limitation of dose to a member of the public for 12 consecutive-months to within the 40 CFR 190 limits. For the pur>oses of the Special Report, it may be assumed t1at the dose commitment to the member of the public from other uranium fuel cycle sources is negligible, with the exception that dose contributions from other nuclear fuel cycle facilities at the same site or within a radius of 5 miles must be considered.
If the dose to any member of the public is estimated to exceed the requirements of 40 CFR 190, the Special Report with a, request for a variance in accordance with the provisions of 40 CFR 190.11. is considered to be a timely request and fulfills the requirements of 40 CFR 190 until NRC staff action is completed provided the release conditions reseting in violation of 40 CFR 190 have not already been corrected. An-individual is not considered a member of the public during any period in which he/she is engaged in carrying out any. operation which is part of the nuclear fuel cycle.< RADIOACTIVE LIOUID EFFLUENT INSTRUMENTATION (4.1) 6.4.9 The radioactive liquid effluent instrumentation is provided to monitor and control, as applicable, the releases of radioactive materials in liquid effluents during actual or potential releases of liquid effluents. The alarm / trip setpoints for these instruments shall be , ! calculated 'in accordance with the procedures in the ODCM to ensure that the alarm / trip will occur prior to exceeding the 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 Part 50. APPROVED FEB 211990 6-13 e . 21 02 15-90
g l 6.4 BASES (Continued) RADI0 ACTIVE GASEOUS EFFLUENT INSTRUMENTATION (4.2) , 6.4.10 The radioactive gaseous efftuent instrumentation ! is provided to monitor and control, as applicable, the releases of radioactive materials i in gaseous effluents during actual or potential l releases of gaseous effluents. The alarm / trip t setpoints for these instruments shall be calculated in accordance with the procedures in the ODCM to ensure that the alarm / trip will occur- j prior to exceeding the limits of 10 CFR Part 20. 4 This instrumentation also includes provisions for. , monitoring and controlling the concentrations of ' potentially explosive gas mixtures in the waste . gas holdup system. The OPERABILITY and use of- i this instrumentation is, consistent with the ' requirements of General Design Criteria 60, 63 -
-and 64 of Appendix A to 10 CFR Part 50.1 ,
i I i I L ! ._ L l L - APPROVED FFB 211990 6-14 Rev. 21 02-15-90 _ n . . . _ .}}