ML20090A832
| ML20090A832 | |
| Person / Time | |
|---|---|
| Site: | Shoreham File:Long Island Lighting Company icon.png |
| Issue date: | 08/07/1991 |
| From: | LONG ISLAND LIGHTING CO. |
| To: | |
| Shared Package | |
| ML20090A776 | List: |
| References | |
| 4170002, NUDOCS 9203030115 | |
| Download: ML20090A832 (205) | |
Text
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OFFSITE DOSE CALCULATION MANUAL' List of Effective Pages Page. Table (T), Revision ; or Figure (F) Number EP 18 EP-2 18 EP-3 18 i thru 11 16 iii thru v 17 vi 16 vii thru viii 17 1.1-0 17 1,2-0 16 I.2-1 thru I.2-5 18 1,2-6 17 1.2-7 thru I.2-8 18 I.3-0 16 I. -1 17 1.3-2 16 1.3-3 thru I.3-5 18 I-3.6 thru 1.3-8 17 1.3-9 16 1.3-10 18 I.3-11 thru I.3-16 17 I.3-17 16 1.3-18 17 1.3-19 thru I.3-20 18-I.3-21 16 1.3-22 thru I.3 17 1.3-24 16 I.3-25 17 1.3-26 thru I.3-27 18 I,3-28 thru I.3-29 17 I.3-30 16 1.3-31 thru I.3-33 17 I.3-34 18 I.3-35 16 I.3-36 18 I.3-37 thru I.3-39 17 I,3-40 16 I.3-41.thru I.3-45 17 I.3-46 thru I.3-47 18 I.4-0 thru I.4-1 16 1.4-2 17 I.4-3 thru-I.4-5 - 16 1.4-6 thru I.4-7 17 1.4-8 17 1.4-9 16 EP-1 Revision 18 - May 1991 > s - n a
0FFSITE DOSE CALCVLR'10N MANUAL- j List _of Effective Pages (Cont'd.) Page. Table (T), Revision , ior Figure (F) Number .,
-1.5-0 thru 1.5-4 16 I.6-0 .
16 - 1.6-1 thru 1.6-3 18 1.6-4 16-11.1-1 16 11.2.1-1 thru 11.2.1-2 17 11.2.1-3 thru 11.2.1-5 8 11.2.1-6 16 11.2.1-7 13 F2.1-1 thru F2.1-2 14 11.2.2-1 thru 11.2.2-4 17 11.2.2-5 thru 11.2.2-8 17 Deleted T2.2-1, pp. 1/2 thru 2/2 10 F.2.2-1 3 F.2.2-2 thru F.2.2-2 1 F.2.2-3 thru F.2.2-6 17 Deleted 11.3.0-1 17 11.3.1-1 17 11.3.1-2 thru 11.3.1-5 8 11.3.1-6 16 , T 3.1-1 3
-T.3.1-2, pp. 1/3 thru 3/3 3 F.3.1-1 17 F.3.1-2 17 Deleted 11.3.2-1 16 11.3.3-1 16 11.3.3-2 thru 11.3.3-4 3 11.3.3-5 thru 11.3.3-8. 17 F.3.3-1 17 11.3.4-1 16 11.3.4-2 3 -
11.3.4-3 thru 11.3.4-5 17 T.3,4-1 1
--I I . 3. 5 .1 17 11.3.5-2~ 10 11.3.5-3 thru_II.3.5-6 3 11.3;5-7 13 II.3.5-8 10 11.3.5-9 inru 11.3.5-10 13 11.3.5-11 thru 11.3.5-13 17 T.3.5-1, p. 1/3 10 T.3.5-1, pp. 2/3 thru 3/3 1 T.3.5-2, pp.-1/3 thru 3/3 1 EP-2 Revision 18 - May 1991 t
0FFSITE DOSE CALCULATION MANUAL List of Effective Pages (Cont'd.) Page Table (T), Revision or Figure (F) Numbe r_, T.3.5-3, pp. 1/3 thru 3/3 1 T.3.5-4, pp. 1/3 thru 3/3 1 T.3.5-5, pp. 1/2 thru 2/2 3 T.3.5-6, p. 1/1 1 , T 3.5-7 p. 1/1 1 T.3.5-8, p. 1/1 15
-T.3.5-9, pp. 1/3 thru 3/3 3 T 3.5-10, pp. 1/3 thru 3/3 3 T.3.5-11, pp.1/3 thru 3/3 3 T.3.5-12, pp. 1/3 thru 3/3 3 T.3.5-13, pp. 1/3-thru-3/3 3 T.3.5-14, po. 1/3 thru 3/3 3
-T.3.5-15, p. 1/1 15-T.3.5-16, p. 1/1 3 T.3.5-17, p. 1/1 14
-11.3.6-1 17 F.3.6-1 17 Deleted 11.3.7-1 16 11.4-1 thru 11.4-2 18 11.4-3~ 4 T.4-1 17 T.4-2 18 11.5 17 T.5-1, ( Rev. O thru 16 Deleted ) 17 T.5-2 thru T 5-5 renumbered 17 F.5-1 thru F.5-2 17 11.6-1 3 A-1 15
-B-1 3 EP-3 Revision 18 - May 1991 l
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LONG ISLAND LIGHTING COMPANY OFFSITE DOSE CALCULATION MANUAL EFFECTIVE DATE - AUGUST 7. 1991 P Revision 18 l
SNPS-1 ODCM PLEASE NOTE Revision 1 - August '983 of the LILCO, SNPS-1, Offsite Dose Calc:h tion Manual has been totally revised from the Original - March 1983 Submittal - Therefore, Revision 1 - August 1983 has no change bars. CHANGE BARS have been used in subsequent revisions to locate a change (additions, deletions, and/or modifi-cations)inengineering, design, methodology,etc. CHANGE BARS are not used for Errata (i.e., typos, format changes). CHANGE BARS are not used in Part I Revision 16 since this material is entirely new to the ODCM. They are also not used to indicate changed page numbers in Part 11 Revision 16 since all page numbers have had a II, appended to them. In addition, Part 11 changes are not labelled Revision 16 at the page bottom if the only change is a page number appendage. 00 NOT REMOVE - KEEP IN YOUR ODCM BN1-11600.02-92 i Revision 16 - July 1990
SNPS-1-ODCM
'PART I_ THE RADIOLOGICAL-EFFLUENT CONTROLS (REC)
TABLE OF CONTENTS 00CM- , REC
- SECTION SECTION SUBJECT PAGE 1 - > INTRODUCTION !.1-0 2 1.0 DEFINITIONS 1.2-0 3 3.0 and 4.0 CONTROLS AND SUREVE1LLANCE 1.3-0 REQUIREMENTS 4: 3.0 and 4.0 BASES BASES FOR SECTIONS 3.0 and 4.0 1.4-0 5.0 DESIGN FEATURES I.5 6 6.0 ADMINISTRATIVE CONTROLS 1.6-0 <
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b BN1-11600.02-92 11 Revision 16 -' July 1990
l l SNPS-1 ODCM PART !! CALCULATIONAL METHODOLOGY AND PARAMETERS FOR l l COMPLIANCE WITH THE RADIOLOGICAL EFFLUENT CONTROLS TABLE OF CONTENTS Radiological 1 Effluent i Cor.trols ' Section Subject __Section Paz 1 INTRODUCTION !!.1 1 2 SET POINTS !!.2.1-1 2.1 LIQUID EFFLUENT MONITOR SET POINTS 3.11.1.1 11.2.1-1 ; 2.1.1 Radiation Effluent Monitor (RE-13) High/ Trip Alarm Set Point for Discharge Waste Sample Tanks, Recovery Sample Tanks, or Yard Piping Drain Sump 11.2.1-4 2.1.2 RadiationEffluentMonitor(RE79)HighAlarm Set Point for Reactor Building Salt Water Drain Tank !!.2.1-0 2.1.3 Residual Heat Removal Heat Exchanger Service Water Outlet Monitors (RE-23A,RE-238) High Alarm Set Points 11.2.1-7 2.2 GASE0US EFFLUENT MONITOR SET POINTS 3.11.2.1 11.2.2 1 2.2.1 Gaseous Effluent Monitor High Alarm Set Point forStationVentilationExhaustMonitor(RE-42) I I . 2. 2-t' 2.2.1.1 Gaseous Effluent Monitor High A!:rm Set Point for Station Ventilation Exhaust Monitor (RE-42)BasedonNobleGasesTotal t Body Dose Rate 11.2.2-2 2.2.1.2 Gaseous Effluent Monitor High Alann . Set Point for Station ventilation Exhaust Monitor (RE-42) Based on Noble Gases Skin Dose Rate 11.2.2-3 ( BN1-116DO.02-92 iii Revision 17 - May 1991
i l SNPS-1 ODCH TABLE Or CONTENTS (CONT'D) 3 DOSE CALCULATION HETHODS 11.3.0-1 3.1 LtQUID EFTLUENT, DOSE CALCULATION 3.11.1.2 11.3.1-1 1 3.1.1 Hethod 1: (Computerized Hethod) 11.3.1-1 3.1.2 Method 2: (Backup Hethod) 11.3.1-5 3.2 OPERATION OF LIQUID WASTE TREATHINT i SUBSYSTEMS 3.11.1.3 11.3.2-1 3.3 DOSE RATE DUE TO GASEOUS EFFLUENTS 11.3.3-1 3.3.1 Hethod 1: (Computerized Method) 11.3.3-1 3.3.1.1 Release Rete Estimation 3.11.2.1 11.3.3-1 3.3.1.2 Total body Dose Rate 3.11.2.1 11.3.3-2 3.3.1.3 Skin Dose Rate 3.11.2.1 11.3.3-3 3.3.1.4 Organ Dose Rate (1-131, 1-133 Tritium and Particulate Releases) 3.11.2.1 11.3.3-4 3.3.2 Hethod 2: (Backup Hethod) 11.3.3-5 3.3.2.1 Noble Gas Total Body Dose Rate 3.11.2.4 11.3.3-5 3.3.2.2 Noble Gas Skin Dose Rate 3.11.2.1 11.3.3-6 3.3.2.3 Organ Dose Rate (Particulate Releases) 3.11.2.1 11.3.3-7 3.4 GASEOUS EFTLUENTS NOBLE GAS AIR DOSE 3.11.2.2 11.3.4-1
- 3.4.1 . Hethod it (Computerieed Method) 11.3.4-1 '
3.4.1.1 Release Estimation 3. '.1. 2. 2 11.3.4-1 3.4.1.2 Noble Gas Gamma Air Dose 3.11.2.2 11.3.4-2 3.4.1.3 Noble Gas Beta Air Dose 3.11.2.2 11.3.4-2 3.4.2 Method 2: (Backup Hethod) 11.3.4-3 3.4.2.1 Noble Gas Gamma Air Dose 3.11.2.2 11.3.4-3 3.4.2.2 Noble Gas Beta Air Dose 3.11.2.2 11.3.4-4 3.5 GASEOUS EFFLUENTS, DOSE DUE TO RADICACTIVE MATERIALS IN PARTICULATE TOPH AND RADIONUCLIDES WITH HALT-LIVES GREATER THAN 8 DAYS 3.11.2.3 11.3.5-1 3.5.1 Method la (Computerized Method) 11.3.5-1 3.5.1.1 Reitase Estimation 3.11.2.3 11.3.5-1 3.5.1.2 Total Body Dose 3.11.2.3 11.3.5-2 hN1-11600.02-92 iv Revision 17 - May 1991
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SNPS-1 ODCH TABLE OF CONTENTS (CONT'D) 3.5.1.3 Skin Dose 3.11.2.3 11.3.5-3 3.5.1.4 Organ Doses Due to Inhalation 3.11.2.3 11.3.5-5 3.5.1.5 Organ Doses Due to Ingestion of i Leafy Vegetables 3.11.2.3 11.3.5-5 l 3.5.1.6 Infant Thyroid Dose Due to Inhalation and Ingestion of Goat Hilk 3.11.2.3 11.3.5-7 3.5.2 Method 21 (backup Hethod) 11.3.5-11 3.5.2.1 Organ Doses 3.11.2.3 11.3.5-11 3.6 (No Longer in Use) 11.3.6-1 l 3.7 TOTAL DOSE FOR THE URANILH FUEL CYCLE 3.11.4 11.3.7-1
-3.7.1 Sources of Radiation and Radioactivity 11.3.7-1 3.7.2 Radiological Impact of Generation of Electricity 11.3.7-1 4 HETEOROLOGICAL AND HYDROLOGICAL PARAMETERS UTILIZED IN THE CALCULATION OF DOSES 11.4-1
4.1 INTRODUCTION
11.4-1 4.2 PARAMETERS AND METHODOLOGY USED Ih THE C0KPUTERIZED METHOD 11.4-1 4.2.1 Meteorological Data 11.4-1 4.2.2 Long-Term X/Q and D/Q Values 11.4 1 4.3 PARAMETERS AND METHODOLOGY USED IN THE BACKUP METHOD 11.4-3 ,, 5 RADIOLOGICAL ENVIRONMENTAL HONITORING PROGRAM SAMPLING 2DCATIONS 11.5-1 6 INTERLABORATORY COMPARISON PROGRAM 11.6-1 Appendix A DERIVATION OF A A-1 Appendix B DERIVATION OF P,g) B-1 BN1-Il600.02-92 v Revision 17 - May 1991
SNPS 1 ODCM l LIST OF TABLES Table Title 2.2-1 Dose Factors for Exposure to a Semi-Infinite Cloud of Noble Gases , ; 3.1-1 Decay Constants ; 3.1-2 Adult Dose Rate Conversion Factors A for (Fish and Invertebrate) Ingestion Pathway i 3, La Noble O s Dose factors 3.5-1 Inhalation Dose Factors for Adults 3.5 2 Inhalation Dose Factors for Teenager , 3.5 3 Inhalation Dose Factors for Child 3.5-4 Inhalation Dose Factors for Infant
- 3.5-5 Recommended Values for V to be used for the Paximum ExposedIndividualinLIEuofSite-SpecificData ;
3.5-6 Stable Element Transfer Data 3.5-7 Humidity Parameters at Receptors 3.5-8 Location of Nearest Residence, Vegetable Garden, and Site Boundary by Sector Contaminated Ground, in estion of Leafy and Stored 3.5-9 P idhe, tables Dose Rate Convers on Factors for child 3.5-10 P Child Ingestion of Cow's-Milk Dose Rate 88$v,ersionFactors 3.5-11 P Child Ingestion of Goat's Milk Dose Rate 8ddv,ersionFactors , 3.5-12 P , Child Ingestion of Meat Dose Rate Conversi:n fddtors 3.5-13 P , Infant Inges tion of Cow's Mill Dose Conversion PAdtors BN1-11600.02-92 vi Revision 16 - July 1990 - ._,m.,w_.,,,,, , , , , - , , ,,.m. ,,,_,--...em--%w-,,--c,,,, _,mw_,._w,-mym.m,,e,..y ,3-.--p.--..myvy*, -*-w-,w-- . + -
SNPS-1 ODCM LISTOFTABLES(CONT'D) Table Title ; 3.5-14 P , infant inv stion e of Goat's Milk Dose Conversion l E$dtors 3.5-15 P Child Inhalation and Ingestion of Leafy and Stored V8he,tablesDoseRateConversionFactors 3.5-16 P}dtors. F Child Ingestion of Goat's Milk Dose Rate Conversion 3.5-17 P , Infant Ingestion of Goat's Milk Dose Rate Conversion Fddtors 4-1 Critical Receptor Locations for Gaseous Erfluent Catulations 4-2 General Site - Specific Data 5-1 Radiological Environmental-Monitoring Program - Direct Radiation Monitoring Stations 1 5-2 -Radiological Environmental Monitoring Program - Airborne Monitoring Stations 53 Radiological Environmental Monitoring Program - Waterborne Monitoring Stations 5-4 Radiological Environmental Monitoring Program - Ingestion Monitoring Stations BN1-11600-92 vii Revision 17 - May 1991 -!
$NPS-1 ODCM LIST OF FIGURES Fioure Title 2.1-1 Detector RE-13. Response vs. Gama Energy [
2.1-2 Detectors RE-23A RE-23B and RE.79, Response vs. Gama Energy < 2.2-1 Detector RE-42, Efficiency vs. Average Beta Energy 2.2-2 Linearity Response Curve for Detector RE-42 3.1-1 Liquid Radweste System Model 3.3-1 Gaseous Effluent Model 5-1 Onsite Sampling Locations - Radiological
- Environmental Monitoring Program 52 Offsite Sampling Locations - Radiological Environmental Monitoring Program l
I I l-l l BN1-11600.02-92 viii Revision 17 - May 1991 1
SNPS-1 ODCH PART 1 SECTION 1 INTRODUCTION a Procedural details of the Radiological Effluent Technical Specifications not as.ociated with solid radioactive vastes which were previously located in the s Station Technical Specifications (TS) have been relocated to the OJCM. ' Portions of the Definitions and Administrative Controla Section of the TS are also being relocated to the ODCH, and some changes to the words of these sections of TS are being made. All the changes are made t ernformance with the requirements of Generic Letter 89-01 {gyrovide ' r Additional changen to the Radiological Effluent Controls (Part 1, Section 3) of the ODCH have been made to reflect the isotopic inventory and the [ radiological effluent monitoring requirements appropriate to a defueled operating condition with fuel stored in the Spent Fuel Pool. The Plant may not be returned to an oper tional state or f uel moved back into the reactor vessel without modifying thia ODCM. Additional changes to this doLument may be required for decommissioning activities. (1) NRC Generic Letter 89-01, "Impicmentation of Programmatic Controls for ', Radiological Effluent Technical Specifications in the Adminirtrative-Controls Section of the Technical Specification and the Relocation of Procedural Details of the RETS to the Offsite Dose Calculation Manual or to the Process Control Program", January 31, 1989. 1.1-0 Revision 17 - May 1991 ,
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SNPS-1 ODCM PART I SECTION 2 RADIOLOGICAL EFFLUENT CONTROLS SE" TION 1.0 DEFINITIONS . 1,2-0 Revision 16 - July 1990 i t
INDEX der!NITIONS i i i 1 l SECTION i 1.0 DEFINIT!0,NS PAGE 1.1 ACT10N........................................................ 1.2 3 1.2 CHANNEL CAllBRAT10N........................................... 1.2 3 1.3 CHANNEL CHECK................................................. 1.2-3 l 1.4 CHANNEL FUNCTIONAL TEST....................................... 1.2 3 1.5 DEFUELED M0DE................................................. 1.2 3 1.6 FREQUENCY NOTAT10N............................................ _!.2 4 ; 1.7 FUEL HANDLING OPERAT10NS...................................... 1.2-4 1.8 MEMBER (S)0FTHEPUBLIC....................................... 1,2-4 1.9 0FFSITEDOSECALCULATIONMANUAL(0DCM)........................ 1.2 4 1.10 OPERABLE OPERABILITY........................................ 1.2 4 1.11 REPORTABLE EVENT.............................................. 1.2-5 l 1.12 51TE B0VNDARY................................................. 1.2 5 1.13 SOURCE CHECK.................................................. 1.2-5 1.14 UhRESTRICTED AREA............................................. 1.2-5
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s SHOREHAM - UNIT 1 1.2-1 Revision 18 - May 1991 i.
INDEX LIST OF TABLES TABLE PAGE 1.1 SURVEILLANCE FREQUENCY NOTAT10N............... . 1.2 7 J i I 1 I I P i SHOREHAM - UNIT 1 1.2-2 Revision 18 - May 1991 V
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J.0 DEFINITIONS The defined terms appear in capitalized type and shall be applicable throughout these Controls.-- ACTION 1.1 ACTION shall be that part of a Control which prescribes remedial measures to be taken under designated conditions.
, CHANNEL CALIBRATION 1.2 A CHANNEL CAllBRAT10N shall be the adjustment, as ne:essary, of the channel output such that it responds with the necessary range and accuracy to known values of the parameter which the channel monitors. The CHANNEL CAllBRAT10N shall encompass the entire channel including the sensor and alarm and/or trip functions, and shall include CHANNEL FUNC110NAL TEST. The CHANNEL CAllBRATION may be performed by any series of sequential, overlapping or total channel steps such that the entire channel is calibrated.
CHANNEL CHECK 1.3 A CHANNEL CHECKi tall be the qualitative assessment of channel behavior during operation by observation. This determination shall include, where possible, comparison of the channel indication and/or status with other indications and/or statue derived from-independent instrument channels measuring the same parameter. CHANNEL FUNCTIONAL TEST 1.4 A CHANNEL FUNCTIONAL TEST shall be:
- a. Analog channels - the injection of a simulated signal into the channel as close to the sensor as practicable to verify OPERABILITY including alarm and/or trip functions and channel failure trips.
- b. Bistable channels - the injection of a simulated signal into the sensor to verify OPERABIL11Y including alarm and/or trip functions.
The CHANNEL FUNCTIONAL TEST may be performed by any series of sequential, overlapping or total-channel steps such that the entire channel is tested. CEFUELED MODE 1.5 The plant is in the DEFUELED MODE when all fuel has been removed from the reactor vessel and there is fuel in the spent fuel storage pool or in the new fuel storage vault. SHOREHAM - UNIT 1 1 ?-3 Revision 18 - May 1991
DErlN1T10NS , FREQUENCY NOTATION 1.6 The FREQUENCY NOTATION specified for the performar.ce of Surveillance l Requirements shall correspond to the intervals defined in Table 1.1. FUEL HANDLING OPERATIONS 1.7 FUEL HANDLING OPERATIONS shall be the movement of fuel over or within the Spent Fuel Pool. Suspension of FUEL HANDLING OPERATIONS shall not preclude completion of the movement of fuel to a safe conservative position. MEMBER (S) 0F THE PUBLIC 1.8 MEMBER (5) 0F THE PUBLIC shall include all persons who are not occupationally . associated with the plant. This category does not include employees of the utility, its contractors or vendors. Also excluded f rom this category are persons who enter the site to service equipment or to make deliveries. This category does include persons who use portions of the site for recreational, Occupational or other purposes not associated with the plant. OFFSITE DOSE CALCULATION MANUAL (ODCM) 1.9 TheOFFSITEDOSECALCULATIONKANUAL(0DCM)shallcontainthemethodologyand parameters used in the calculation of offsite doses resulting from radioactive gaseous and liquid effluents, in the calculation of gaseous and liquid effluent monitoring Alarm / Trip Setpoints, and in the conduct of the Environmental Radiological Monitoring Program. The 0DCM shall also contain (1) the Radioactive Effluent Controls and Radiological Environmental Monitoring Programs required by Technical Specification Section 6.0 and (2) descriptions of the information that should be included in the Annual Radiological Environmental Operating and Semiannual Radioactive Effluent Release Reports required by Technical Specification Section 6.0. OPERABLE - OPERABILITY 1.10 A system, subsystem, train, component or device shall be OPERABLE or have l i OPERABILITY when it is capable of performing its specified function (s) and when all necessary attendant instrumentation, controls, electrical power, cooling or seal water, lubrication or other auxiliary equipment-that are required for the system, subsystem, train, component or device to perfonn its function (s) are alsocapableofperformingtheirrelatedsupportfunction(s). i SHOREHAM - UNIT 1 1.2-4 Revision 18 - May 1991 w -e - - - - - - . - - - , , - , e,----n,--w- ,-mn- e == w ~' e ww*-~n"-'-=v-w-wr-a-c-*'r's-~ w*= s- - w w* w o -=m-m-~-w-wr~r~-,---n~-www-ww1- '*~---w*'<"*+,-ww~en w'*-*
1 DIFINITIONS P REPORTABLE EVENT l 1.11 A REPORTABLE EVENT shall be any of those conditions specified in Section 50.73 to-10 CFR Part 50. . SITE BOUNDARY 1.12 The SITE BOUNDARY shall be that line beyond which the land is neither owned, nor 1 leased, nor otherwise controlled by the licensee. { SOURCE CHECK 1.13 A SOURCE CHECK shall be the qualitative assessment of channel response when the ! channel sensor is exposed to a radioactive source. - UNRESTRICTED AREA-1.14 An UNRESTRICTED AREA shall be any area at or beyond the SITE BOUNDARY-access to which is not controlled by the licensee for purposes of protection of individuals from exposure to radiation and radioactive materials, or any area within the 511E BOUNDARY used for residential quarters or for industrial, commercial, institutional, and/or-recreational purposes. SH09EHAM - UNIT 1 1.2-5 Revision 18 - May 1991
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DETINITIONS T!!IS PAGE LEl'T BLANK 5110REHAM - UNIT 1 1.2-6 Revision I/ - May 1991 l i l l
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j DEFINITIONS _ l l TABLE 1.1 _SURVElLLANCE FREQUENCY NOTATION NOTATION FREQUENCY S At least once per 12 hours. D At least once per 24 hours. W At least once per 7 days. M At least once per 31 days. Q At least once per 92 days. SA At least once per 184 days. : A At least once per 366 days. R Atleastonceper18 months (550 days). ' N/A Not applicable. P Completed prior to each release. , t P
.SHOREHAM - UNIT 1 1.2-7 Revision 18 - May 1991
Dl.flNITIONS _ , _ Tills FAGE LEFT BLANK SHOREHAM - UNIT 1 1,2-8 Revision 18 - May 1991 I
SNPS-1 ODCM PART 1 SEC110N 3 , t RADIOLOGICAL EFFLUENT ! CONTROLS SECTIONS 3.0 and 4.0 CONTROLS p . SURVEILLANCt. REQUIREMENTS I t 1.3-0 Revision 16 - July 1990
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l INDEX CONTROLS AND SURVEIL 1EICT REQUIRDfENTS SECTION PAGE 3/4.0 APPL 1CABILITT......................................... I.3-3 3/4.3 INSTRUMENTATION....................................... Radioactive Liquid Effluent Monitering Instrumentation.................................. 1.3-5 l Radioactive Caseous Effluent Monitoring Instrumentation.................................. 1.3-10 3/4.11 RADIDACTIVE ETTLUENTS l 3/4.11.1 LIQUID ETTLUENTS i Concentration.................................... 1.3-1$ Dose............................................. 1.3-19 Liquid Radwaste Treatment System................. I.3-20 3/4.11.2 GASE0US EFFLUENTS Dose Rate........................................ I.3-22 Dose - Noble Cases............................... I.3-26 Dose - Tritium, and Radionuclides in
. Particulate Form............................ I.3-27 3/4.11.4 TOTAL D0SE............................................ 1.3-34 3/4.12 RADIOLOGICAL ENV1dONMENTAL MONITORING 3/4.12.1 MONITORING PR0 GRAM.................................... I.3-35 3/4.12.2 LAND USE CENSUS....................................... 1,3-46 3/4.12.3 INTERLABORATORY C0KPARISON PROGRAM.................... I.3-47 I.3-1 Revision 17 - May 1991
JNDEX : LIST OF TABLES TABLE PAGE , 3.3.7.10 1 RAD 10ACT!YE L10010 EFFLUENT MONITORING INSTRUMENTATION................................... 1,3 6 ; 4.3.7.10-1 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS......... 1,3-8 3.3.7.11-1 RADIOACTIVE GASEOUS EFFLUF.NT MON 110 RING , INSTRUMENTATION................................... 1.3-11 4.3.7.11-1 RADI0 ACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS......... I.3-13 ; 4.11.1.1.1-1 RADI0 ACTIVE LlQUID WASTE SAMPLING AND ANALYSIS PR0 GRAM........................................... 1.3-16 4.11.2.1.2 1 RADIOACTIVE GASEOUS WASTE MONITORING, SAMPLING, AND ANALYSIS PR0 GRAM.............................. 1.3-23 3.12.1-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM..... 1.3-37 3.12.1-2 REPORTING LEVELS FOR RADIDACTIVITY CONCENTRATIONS IN ENVIRONMENTAL SAMPLES.......................... 1.3-42 4.12.1 1 DETECTION CAPABILillES FOR ENVIRONMENTAL SAMPLE ANALYSIS.......................................... 1.3-43 i l 1.3-2 Revision 16 - July 1990 l
3/4.0 APPLICABILITY C0k'T ROL S 3.0.1 Compliance with the Controls contained in the succeeding Controls.is required during the DEFUELED MODE specified thereint except that upon failure to meet the Controls the associated ACTION requirements shall be met. , 3.0.2 Noncompliance with a Control shall exist when the requirements of the Control and associated ACTION requirements are not met within the specified time intervals. If the Control is restcred prior to expiration of the specified tone intervals, completion of the ACTION requirements is not required. 3.0.3 Commencement or continuation of FUEL HANDLING OPERATIONS shall not be made when the conditions for the Controls are not met and the associated - ACTION requires suspension of FUEL HANDLING OPERATIONS if they are not met within a specified time interval. FUEL HANDLlHG OPERATIONS may be made in accordance with the ACTION requirements when conformance to them:
- 1. Permits continued FUEL HANDLING OPERATIONS for an unlimited period of time or,
- 2. Permits fuel to be moved to a safe, conservative position.
SHOREHAM - UNIT 1 1.3-3 Revision 18 - May 19!1
i APPLICABILITY j SURVEILLANCE REDUIREMENTS-4.0.1 Surveillance Requirements shall be met during the DEFUELED MODE or other APPLICABILITY conditions specified for individual Controls. 4.0.2 Each Surveillance Requirement shall be performed within the specified surveillance interval with a maximum allowable extension not to exceed 25% of the specified surveillance interval. 4.0.3 Failure to perform a Surveillance Requirement within the allowed surveillance intetisl, defined by Specification 4.0.2 shall constitute noncompliance with the OPERABILITY requirements for a Control. The time limits of the ACTION recuirements are applicable at the time it is identified- < that a Surveillance Requirement has not been performed. Surveillance Requirements do no have to be performed on inoperable equipment. 4.0.4 FUEL HANDLING OPERATIONS shall not occur or continue unless all Surveillance Requirement (s) associated with the Control have been performed within the applicable surveillance interval. This provision shall not prevent passage through or to conditions as required to comply with ACTION requirements. [ [ i SHOREHAM - UNIT 1 1.3-4 Revision 18 - May 1991 I r . r- me---w-- --------m--v ~- y w--r e-- **wi+w* e--+--e-- -- + , - -n+-cr---yv --e -nww+- -,- -- e - w, -
l n 1NSTRUMENTAT10N RADICACTIVE L10010 EFFLUENT MONITORING INSTRUMENTATION i CONTROLS 5 3.3.7.10 The radioactive liquid effluent monitoring instrumentation channels shown in Table 3.3.7.10-1 shall be OPERABLE with their alarm / trip setpoints set to ensure that the limits of Control 3.11.1.1 are not exceeded. The alarm / trip setpoints of these channels shall be determined in accordance with - the Offsite Dose Calculation Manual (0DCM). APPLICABlllTY: At all times. ACTION:
- a. With a radioactive liquid effluent monitoring instrumentation channel alarm / trip setpoint less conservative than required by the above control, immediately suspend the release of radioactive liquid effluents monitored by the affected channel or declare the channel ,
inoperable or change the setpoint so it is acceptably conservative.
- b. With the number of channels OPERABLE less than the Minimum Channels OPERABLE requirement of Table 3.3.7.10-1, take the ACTION shown in '
Table 3.3.7.10 1. Restore the instruments to OPERABLE status within 30 days and if unsuccessful explain in the next Semiannual ! Radiological Effluent Release Report why the inoperability was not corrected in a timely manner,
- c. The provisions of Control 3.0.3 are not applicable. l
$URVEILLANCE REOUIREMENTS 4.3.7.10.1 Each radioactive liquid effluent monitoring instrumentation channel shall be demonstrated OPERABLE by performance of the CHANNEL CHECK, SOURCE CHECK, CHAhNEL CALIBRATION, and CHANNEL FUNCTIONAL TEST operations at the frequencies-shown in Table 4.3.7.10-1.
4.3.7.10.2 At least once per 4 hours at least one circulating or service water pump shall be determined to be operating _and providing dilution to the disp Se strvcit:re whenever dilut'on is required to meet the site radioactive
'; N conevntration limits of Control 3.11.1.1.
SHOPEmp - 1 1.3-5 Revision 28 - May 1991 __ ._._._.,_.u..._.__.._._ _ . _ . _ . _ . _ _ _ _ . _ _ _ _ . _ _ _ _ . - . _ _ _ _ . _ . _ . , . _
E o N
- c
$ TABLE 3.3.7.10-1 h
s RADIOACTIVE LIQUID EFFLUENT MGiitTORING INSTRLMENTATION w MINIMDi CHANNELS INSTRUMENT OPERABLE ACTION
- 1. GPOSS RADICACTIVITT MONITORS PROVIDING ALARM AND AUTOMATIC i TERMINATION OF RELEASE
- a. Liquid Radvaste Effluent Line, RE-13 1 110 y 2. GROSS RADI0 ACTIVITY MONITCRS PROVIDING ALARM BUT NOT w PROVIDING AUTOMATIC TERMINATION OF RELEASE a .
- a. RER Heat Exchanger Service Water Outlet, RE-23A, RE-23B 1 111
) b. Reactor Building Salt Water Drain Tank Outlet, RE-79 1 112
- 3. FLOW RATE MEASUREMENT DEVICE
- a. Liquid Radwaste Effluent Line 1 113
?
1 a 4 g The detector associated with the operating RER subsystem shall be OPERABLE when service water is flowing through _ the respective RER heat exchanger and the associated RRR subrfstem is filled with water f I x b
h TABLE 3.3.7.10-1 (Continued) i ACTION STAT!MENTS . ACTION 110 - With the uumber of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue provided that prior to initiating a l l release: ,
- a. At least two independent samples are analyzed in accordance with Controls 4.11.1.1.1 and 4.11.1.1.2, and
- b. At least two technically qualified members of the Station ,
Staff independently verify the release rate calculations ' and discharge line valvingt , Othervise, suspend release of radioactive effluents via this pathway. ACTION 111 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirertent, for the detector (s) associated with operating RER loop (s) effluent releases via the(se) pathway (s) may continue provided that, at least once per 12 hours, grab samples are collected and analyr.ed for ,7 radioactivity at a lower limit of detection of at least 5x10 l microcurie /st. 1 ACTION 112 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue provided that, at least once per 12 hours,grabsamplesarecollectedandanalyzed{orradioactivity at a lower limit of detection of at least 5x10~ microcurie /mL. l ACTION 113 - With the number of channels OPERABLE less than required by the Hinimum Channels OPERABLE requirettent, ef fluent releases via this pathway may continue provided that, flow rate is estimated l at least once per 4 hours during actual releases. Pump performance curves generated in place may be used to estimate flov. SHOREHAM - UNIT 1 1.3-7 Revision 17 - May 1991 l
~
4 TABLE 4.3.7.10-1 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENATATION SUREVEILLANCE REQUIREMENTS 1
/
3-CPJ3NEL CHANNEL SOURCE CHA.NTEL FUNCTIONAL I INSTRUMENT CHECK CHECK CALIBRATION TEST _
- 1. GROSS RADIDACTIVITT MONITORS PROVIDING ALARM AND AUTOMATIC TERMINATION OF RELEASE
- a. Liquid Radvaste Effluent Line, RE-13 D(4) P R(3) Q(1) 4 Ia 2. GROSS RADIOACTIVITY MONITORS Eo PROVIDING ALARM BUT NOT PROVIDING AUTOMATIC TERMINATION OR RELEASE
- a. RHR Heat Exchanger Service Water Outlet, RE-23A, RE-23B D* M R(3) Q(2) i
- b. Reactor Building Salt Water Drain Tank Outlet, RE-79 D M R(3) Q(2)
- 3. FLOW RATE MEASUR MENT DEVICE 4 a. Liquid Radvaste Effluent Line D(4) N.A. R Q
^ 8
- c Only when service water is flowing through the respective RER heat exchanger and the associated RHR subsysten is 4 filled with water. ,
5 2 i_ ~
i ThBLE4.3.7.10-1(Continued) TABLE NOTATIONS (1) The CHANNEL FUNCTIONAL TEST shall also demonstrate that automatic ! isolation of this pathway and control room alarm annunciation and/or indication occur if any of the following conditions exists:
- 1. Instrument indicates measured levels above the alars/ trip setpoint.
- 2. Circuit failure.
3.- Instrument indicates a downscale failure.
- 4. Instrument controls not set in operate mode.
(2) The CHANNEL FUNCTIONAL TEST shall also demonstrate that control room alarm annunciation and/or indication occurs if any of the following conditions exists: 1._ Instrument-indicates measured levels above the alarm / trip setpoint.
- 2. Circuit failure.
- 3. Instrument indicates a downscale failure.
- 4. Instrument controls not set in operate mode.
(3) The initial CHANNEL CAllBRATION shall be performed using one or more of the reference standards certified by the National Bureau of Standards (NBS) or using standards that have been obtained from suppliers that participate in measurement assurance activities with NBS. These standards shall permit calibrating the system over its intended range of energy and measurement range. For subsequent CHANNEL CALIBRATION, sources that have been related to the initial calibration shall be used. (4) CHANNEL CHECK shall consist of verifying indh.ation during periods of release. CHANNEL CHECK shall be made at least once per 24 hours on days when bat:h releases are made. SHOREHAM - UNIT 1 1.3 9 Revision 16 - July 1990 -rw. -%.,_ - . , - , , .,e -,, -,,$ ----.s ,,c.,, - _ . , - - . - _ . , - . .-.-,y , -.m-.. . v- .,c - ,- .
,m.,
INSTRUMENTATION RADjAC11vf _ GASEOUS EFFLUENT _ MONITORING INSTRUMENTATION CONTROLS
~
.),
1 3.3.7.11 The radioactive go tous effluent monitoring instrumentation channels ! shown in Table 3.3.7.11 1 shall be OPERABLE with their alarm / trip setpoints set to ensure that the limits of Control 3.11.2.1 are not exceeded. The alarm / trip setpoints of these channels shall be determined in accordance with the ODCH. I APPLICABILITY: At all times. ACTION:
- a. With a radioective gaseous effluent monitoring instrumentation channel alarm / trip setpoint less conservative than required by the above Control, immediately suspend the release of radioactive
-gaseous effluents monitored by the affected channel or declare the channel inoperable, or change the setpoint so it is acceptably '
conservative.
- b. With the number of channels OPERABLE less th6n the Minimum Channels OPERABLE requirement of Table 3.3.7.11-1, take the ACTION shown in Table 3.3.7.11-1. Restore the instrument to OPERABLE status within 30 days and, if unsuccessful, explain in the next Semiannual Radiological Effluent Release Report why the inoperability was not corrected in a timely manner.
- c. The provisions of Controls 3.0.3 are not applicable.
SURVEILLECE REQUIREMENTS 4.3.7.11 Each radioactive gaseous 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 4.3.7.11-1.
$HOREHAM - UNIT 1 1,3-10 Revision 18 - May 1991
-- .. - . - - - - ~ - . . , - , , - . - . - . .- .-. -- - . - . , , .
TABLE 7.11-1
'E RADIDACTIVE CASEOUS EFFLUENT MONITURING INSTRUMENTATION n
f MINIMUM CHAFNELS e ACTION OPERABLE 3
-4 INSTRUMENT
~
- 1. [No Longer in Use}
- 2. [No Longer in Use]
- 3. STATION VEh71LAT10N EIRAUST MONITORING SYSTLM Noble Gas Activity Monitor, RE-42 I 120 a.
. b. [No Longer in Use]
Particulate Sampler 1 122 c.
~ 123
- d. Effluent Systen Flow Rate Monitor 1 123
- e. Sampler Flow Rate Monitor 1
- 4. [No Longer in Use]
?
1 1 8 0 i x 3
TABLE 3.3.7.11-1 (Continued) TABLE NOTATIONS i ACTION STATEMENTS ACTION 120 - With the number of channels OPERABLE less thaa required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway m;y continue provided grab samples are taken at least once per 12 hours and there sa ples are analyzed for radioactivity within 24 hours. ACTIDX 121 [NoLongerinUse) ACTION 122 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue provided samples are continuously collected starting within 8 hours of diccovery, with auxiliary sampling equipment as required in Table 4.11.2.1.2-1. ACTION 123 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue provided the flow rate is estimated at least once per 12 hours. ACTION 124 - [No Longer in Ose] l SHORERAM - UNIT 1 1.3-12 Revision 17 - May 1991 l l
TABLE .7.11d YL y RADIOACTIVE CASEOUS EFFLUENT _MC**'i' RING IF3TRUMENTATION SURVEILLANCE REQUIREMENTS a CHANNEL H CHANNEL SOURCE CHANNEL FUNCTIONAL'
~ CHECK CHECK CALIBRATIOK TEST INSTRUMENT
- 1. [No Longer in Use]
- 2. [No Longer in Use)
- 3. STATION '<ENTILATION EXHAUST MONITORING SYSTEM
- a. Noble Gas Activity Monitor, D M R(2) Q(1)
.H y RE-42 O
- b. [No Longer in Use]
- c. Particulate Sampler W N/A N/A N/A Effluent System Flow Rate D N/A Q N/A d.
Monitor
- e. Sampler Flow Rate Monitor D N/A Q N/A 5
h- 4. [No Longer in Use] E u i, I w b 8
, TABLE 4.3.7.11-1 (Continued)
TABLE NOTATIONS (1)- The CHANNEL FUNCTIONAL TEST shall also demonstrate that control room , alarm annunciation and/or indication occurs if any of the following conditions exists: -
- 1. Instrument indicates measured levels above the alarm setpoint.
- 2. C1rcuit failure.
- 3. Instrument indicates a downscale failure.
- 4. Instrument controls not set in operate mode.
(2) The initial CHANNEL CALIBRATION shall be performed using one or more of the reference standards certified by the National Bureau of Standards (WBS) or using standards that have been obtained from suppliers that participate in measurement assurance activities with NBS. These standards shall permit calibrating the system over its intended range of energy and measurement range. For subsequent CHANNEL CALIBRATION, sources that have been related to the initial calibration shall be used. (3)- [No Longer in Use] l l .. i l l SHOREHAM - UNIT 1 I.3-14 Revision 17 - May 1991 l I
3/4.11 RADI0 ACTIVE EFFLUENTS 3/4.11.1 LIQUID EFFLUEhy CONCENTRATION CONTROLS 3.11.1.1 The concentration of radioactive material released in liquid effluents to UNRESTRICTED AREAS (see Figure 5.t.3) shall be limited to the l concentrations specified in 10 CFR Part 20 Appendix B. Table II, Column 2 for radionuclides other than dissolved or entrained noble gases. For dissolvgd or entrained noble gases, the concentration shall be limited to 2 x 10 microcurie /mL total activity. APPLICABILITY: At all times. ACTION: With the concentration of radioactive material released in liquid etfluents to UNRESTRICTED AREAS exceeding the above limits, immediately restore the concentration to within the above limits. SURVET' LANCE REQUIREMENTS
- 4. 11.1.1.1 Radioactive liquid wastes shall be sampled and analyzed accord'ag to the sampling and analysis program of Table 4.11.1.1.1-1, 4.11.1.1.2 The results of the radioactivity analyses shall be used in accordance with the methodology and parameters in the ODCM to acsure that the concentrations at the point of release are maintained within the limits of Control 3.11.1.1.
i l S110RDIAM - UNIT 1 I.3-15 Revision 17 - May 1991 l L ._.
TABLE 4.11.1.1.1-1 ) RADIDACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAM Lower Limit Minimum Type of of Detection Liquid Release Sampling Analysis Activity (LLD) Type Frequency Frequency Analysis (uCi/mL)"
~7 A. Batch Waste P P Principal,Gama 5x10 ReleaseTgnks Each Batch Each Batch Emitters and Sumps
- 1. Discharge Waste Sample ~
Tanks P* M* Dissolved and lx10 One Batch /M Entrained Gases
- 2. Recovery (Gat:ma Emitters)
Sample 1x10 Tanks Eac$* Batch Composite d H-3 Gross Alpha 1x10
- 3. Yard Pip-
-8 ind Drain P* Q** d Sr-89, Sr-90 5x10 Sump Each Batch Composite -6 Fe-55 1x10
~7 B. Continuous M# M# 5x10 Releases
- Grab Sample Grab Sample' Emitters" Principal Cama
- 1. RER Heat Exchanger Service Water Dissolved and lx10 Outlet Entrained Cases (Gamma Emitters)
- 2. Reactor Building -5 Salt Water H-3 1x10
~
Gross Alpha 1x10
-8 Q## Q## Sr-89, Sr-90 5x10 f f Grab Sample Grab Sample -6 Fe-55 1x10
- If batch is released during the month.
- If batch is released during the quarter, f If flow is released during the month.
## If flow is released during the quarter.
SHOREHAM - UNIT 1 I.3-16 Revision 17 - May 1991 [
TABLE 4.11.1.1.1-1 (Continued) TABLE NOTATION a The LLD is defined, for purposes of the Controls, as the smallest concentration of radioactive material in a sample that will yield a net count, above system background, that will be detected with 95% probability with only 5% probability of-falsely concluding that a blank observation represents a "real" signal. For o articular measurement system, which may include radiochemical separ. 'n: LLD = 4.66 sb 6 E . V . 2.22 x 10 . Y , exp (-AAt ) k'here: LLD is the "a priori" lower limit of detection as defined above, as microcuries per unit mass or volume, s h is the standard deviation of the background counting rate or of tne counting rate of a blank sample as appropriate, as counts per minute, E is the counting-efficiency, as counts per disintegration, V is the sairple size in units of mass or volume, 2.22 x 100 is the number of disintegrations per minute per microcurie, Y is the fractional radiochemical yield, when applicable, A is the radioactive decay constant for the particular radionuclide, and At for plant effluents is the elapsed time between the midpoint of sample collection and the time of counting. 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 priori (before the fact) limit. representing the capability of the measurement system and not as a posteriori (after the fact) limit for a particular measurement. b 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 ODCM to assure representative sampling. SHOREHAM - UNIT 1 1.3-17 Revision 16 - July 1990
TABLE 4.11.1.1-1 (Continued) TABLE NOTATIONS (Continued)
"The principal gamma emitters for which the LLD specification applies include the following radionuclides: Cs-134 and Cs-137. Ce-144 shall also be measured, but with Ma-54 Co-60, an LLD 2n-6g,Ci/mL.
of 5x10
~
u This list does not mean that only these nuclides are to be considered. Other gamma peaks that are identifiable, together with those of the above nuclides, shall also be analyzed and reported in the Semiannual Radioactive Effluent Release Report pursuant to Control 6.9.1.7. d A composite sample is one in which the quantity of liquid sampled is proportional to the quantity of liquid vaste discharged and in which the method of sampling employed results in a specimen that is representative of the liquids released.
'A continous release is the discharge of liquid vastes of a nondiscrete volume, e.g., from a volume of a system that has an input flow during the continuous release.
I If the alarm setpoint of the effluent monitor, as determined by the method presented in the ODCM, is exceeded, the frequency of sampling shall be increased to daily until the alarm condition no longer exists. Frequency of analysis shall be increased to daily for principal gamma emitters and on incident composite for 11-3, gross alpha, Sr-89, Sr-90 and Fe-55 prepared and analyzed. i SHOREMAM - UNIT 1 1.3-18 Revision 17 - May 1991
RADIOACTIVE EFFLUENTS DOSE
-CONTROL.
3.11.1.2 The dose or dose commitment to a MEMBER OF THE PUBLIC from radioactive materials in liquid effluents released, from each reactor unit, to UNRESTRICTED AREAS (see Figure 5.1.3) shall be limited:
- a. During any calendar quarter to less than or equal to 1.5 mrems to the total body and to less than or equal to 5 mrems to any organ, and
- b. During any calendar year to less than or equal to 3 mrems to the total body and to less than or equal to 10 mrems to any organ.
APPLICABILITY: At all times. ACTION: a.- With the calculated dose from the release of radioactive materials in liquid effluents exceeding any of the above limits, prepare and submit to the Commission within 30 days, pursuant to Technical Specification Section 6.0, a Special Report that identifies the cause(s) for exceeding the limit (s) and defines the corrective actions that have been taken to reduce the releases and the proposed corrective actions to be taken to assure that subsequent releases will be in compliance with the above limits.
- b. The provisions of Control 3.0.3 are not applicable.
SURVE1LLANCE REQUIREMENTS _ 4~.11.1,2 Cumulative dose contributions from liquid effluents for the current calendar quarter and =the current calendar year shall be determined in accordance with the methodology and parameters in the ODCM at least once per 31 days. SHOREHAM - UNIT 1 1.3-19 Revision 18 - May 1991
.. - - .. . - . ~ - - - - - - .. - - .-. - - - .... _ .- - _ - -.- RADI0 ACTIVE EFFLUENTS . LIQUID RADWASTE TREATMENT SYSTEM CONTROLS 3.11.1.3 The liquid radwaste treatment system shall be OPERABLE and appropriate portions of the system shall be used to reduce releases of radioactivity when the projected doses due to the liquid effluent, from each reactor unit to UNRESTRICTED AREAS (see Figure 5.1.3) would exceed 0.06 mrem to the total body or 0.2 mrem to any organs in a 31-day period. APPLICABILITY: At all times. , ACTION:
- a. With radioactive liquid waste being discharged without treatment and in excess of the above limits and any portion of the liquid radwaste treatment system not in operation, prepare and submit to ,
the Conmission within 30 days pursuant to Technical Specification Section 6.0, a Special Report that includes the following information:
- 1. Explanation of why liquid radwaste was being discharged without treatment, identification of any inoperable equipment or subsystems, and the reason for the 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,
- b. The provisions of Control 3.0.3 are not applicable. --
SURVEILLANCE REQUIREMENTS 4.11.1.3.1 Doses due to liquid releases to UNRESTRICTED AREAS shall be projected at least once per 31 days, in accordance with the methodology and parameters in the ODCM, 4.11.1.3.2 The installed liquid radwaste treatment system shall be demonstrated OPERABLE by meeting Controls 3.11.1.1 and 3.11.1.2. SHOREHAM - UN2i i 1.3-20 Revision 18 - May 1991
- . . . . . _ . . - - - - . . . . - - . - . . ~ . _ . . . _ _ . - .
RADI0 ACTIVE EFFLUENTS 3.11.1.4 (NotUsed) 1 SHOREHAM - UNIT 1= I.3-21 Revision 16 - July 1990
RADIDACTIVE EFTLUENTS 3/4- 11.2 GASEOUS EFFLUENTS DOSE RATE CONTROLS 3.11.2.1 The dose rate to areas at and beyond the SITE BOUNDARY due to radioactive materials released in gaseous effluents from the site (see Figure 5.1.3) shall be limited to the following (
- a. For noble gases: Less than or equal to 500 mrems/yr to the total body and less than or equal to 3000 mrems/yr to the skin, and
- b. For tritium and for all radionuclides in particulate form with l half-lives greater than 8 days: Less than or equal to 1500 mrems/yr to any organ.
APPLICABILITY: At all times. AC* LION: With the dose rate (s) exceeding the above limits, immediately restore the release race to within the above limit (s).
-SURVEILLANCE REQUIREMENTS 4.11.2.1.1 The dose rate due to noble gases in gaseous effluents shall be determined to be within the above limits in accordance with the methodology and parameters in the ODCM.
4.11.2.1.2 The dose rate due to tritium and all radionuclides in particulate form with half-lives greater than 8 days in gaseous ef fluents shall be determined to be within the above limits in accordance with the methodology and parameters in the ODCM by obtaining representative samples and performing analyses in accordance with the sampling and analysis program specified in Table 4.11.2.1.2-1. SHORERAM - UNIT 1 1.3-22 Revision 17 - May 1991 I
_ .. ._ . _- . - . . _ _ __-. .. - - _ . _-- _ _ . . _ ._ m -- _ , . _ . _ . _ . - TABLE 4.11.2.1.2-1 RADIOACTIVE GASEOUS WASTE MONITORING, SAMPLING AND ANALYSIS PROGRAM Lower Limit Minimum Type of of Detection Gaseous Release Sampling Analysis Activity (LLD) Type Frequency Frequency Analysis (uCi/mt)* A. Station Continuous" M Principal Gamma 1 x 10~II Ventilation Particulate b Exhaust Sample Emitters Continuous
- M Gross Alpha 1 x 10'II Particulate Sample Continuous' Q Sr-89, St-90 1 x 10'II Composite Particulate Sample Continous* Noble Gas Noble Cases 1 x 10 -6 Monitor Gross Beta or Gamma M M Principal Gamma 1 x 10
Grab Sample b M d M H-3 1 x 10 -6 Grab Sample B. [No Longer in Use] SHOREHAM - UNIT 1 I.3-23 Revision 17 - May 1991 l _ _ . _ _I
TABLE 4.11.2.1.2-l'(Continued) TABLE NOTATION a ihe LLD is' defined. for purposes of these Controls as the smallest concentration of radioactive material in a sample that will yield a net count, above system background, that will be detected with 95% probability with only 5% probability of-falsely concluding that a blank observation represents a "real" signal. For a particular measurement system, which may include radiochemical separation: 4.66 sb LLD = E . V. 2 22'x 106 . Y , exp ( AA t) Where: LLD is the "a priori" lower limit of detection as defined above, as microcuries per unit mass or volume, shis the standard deviation of the background counting rate or of tne counting rate of a blank sample cs appropriate, as counts per minute. E is the counting efficiency, as counts per disintegration, V is the sample size in units of mass or volume, 2.22 x 106 is the number of disintegrations per minute per microcurie, Y is the fractional radiochemical yield, when applicable. A is the radioactive decay constant for the particular radionuclide, and at for plant effluents is the elapsed time between the midpoint of sample collection and the time of counting. Typical values of E, V, Y, and 6tshould be used in the calculation.
- It should be recognized that the LLD is defined as an a_ priori (before the L fact) limit representing the capability of the measurement system and not as l a_ posteriori (after the _ fact) limit for a particular measurement.
i 1 SHOREHAM - UNIT 1 I.3-24 Revision 16 - July 1990 l l
TABLE 4.11.2.1.2-1(Continuedl TABLE NOTATIONS (Continued) b The principal gama emitters for which the LLD specification applies include the following radionuclides: Mn-54, Co-60, 2n-65, Cs-134. Cs-137 and Ce-144 in particulate releases. This list does not mean that only these nuclides are to be considered. Other gama peaks that are identifiable, together with those of the above nuclides, shall also be analyzed and reported in the Semiannual Radioactive Effluent Release Report pursuant to Control 6.9.1.7. C Sampling and analysis shall also be performed following shutdown, startup, or a THERMAL POWER change exceeding 15% of RATED THERMAL POWER within 1-hour period. d iritium grab samples shall also be taken at least once per 7 days from the ventilation exhaust from the spent fuel pool area, whenever spent fuel is in the spent fuel pool, until stable tritium release levels (5 consecutive samples) can be demonstrated.
'The ratio of the sample flow rate to the sampled stream flow rate shall be known for the time period covered by each dose or dose rate calculation made in accordance with Controls 3.11.2.1 and 3.11.2.3.
I Samples shall be changed at least once per 7 days and analyses shall be completed within 48 hours af ter changing, or af ter removal from sampler. Sampling shall also be performed at least once per 24 hours for at least 7 days following each shutdown, startup, or THERPAL POWER change exceeding 15% 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 This requirement does corresponding not apply if (LLDs may be increased by a factor of 10.1) analysis shows that the DOSE in the reactor coolant has not increased by more than a factor of 3; and (2) the noble gas monitor shows that effluent activity has not increased by more than a factor of 3. 9[NoLongerinUse] SHOREHAM - UNIT 1 1.3-25 Revision 17 - May 1991 -
__ __ _ _. . _ . . _ _ _ _ _ _ _ _ . - _ . - . _ _ . _ _ ~ _ . _ . _ __. RADIDACTIVE EFFLUENTS DOSE - NOBLE GASES CONTROLS
-3.11.2.2 _The air dose due to noble gases released in gaseous effluents, from each reactor unit, to areas at and beyond the SITE BOUNDARY (see Figure 5.1.3) shall_be_ limited to the following:
-a. buring any calendar quarter: Less than or equal to 5 mrads for gamma radiation and less than or equal to 10 mrads for beta radiation and,
- b. During any calendar year: Less than or equal to 10 mrads for gamma ,
radiation and less than or equal to 20 mrads for beta radiation. APPLICABILITY: At all times. ACTION:
- a. With the calculated air dose from radioactive noble gases in gaseous effluents exceeding any of the above. limits, prepare and submit to the Commission within 30 days, pursuant to Technical Specification Section 6.0, a-Special Report which identifies the cause(s) for exceeding the limit (s) and defines the corrective actions that have been taken to reduce releases and the proposed corrective actions to be taken to assure that subsequent releases will be in compliance'with the above limits, b, The provisions of Control 3.0.3 are not applicable.
SURVEILLANCE REQUIREMENTS: 4.11.2.2' Cumulative dose contributions for the current calendar quarter and current' calendar year for noble gases shall be determined in accordance with the methodology and parameters in the ODCM at least once-per 31 days. SHOREHAM - UNIT 1- - 1.3-26 Revision 18 - May 1991
_. . ~ . . _ - . - . . . - - .- . - . . - - . . _ - - . .- R_AD10 ACTIVE EFFLUENTS , DOSE - TRITIUM AND RADIONUCLIDES IN PARTICULATE FORM CONTROLS , l 3.11.2.3 The dose to a MEMBER OF THE PUBLIC from tritium and all radionuclides in particulate fonn with half-lives greater than 8 days in gaseous effluents released, from each reactor unit, to areas at and beyond the SITE BOUNDARY (see Figure 5.1.3) shall be limited to the following;
- a. During any calendar quarter: Less than or equal to 7.5 mrems to any organ and,
- b. During any calendar year: Less than or equal to 15 mrems to any organ.
APPLICABILITY: At all times. ACTION:
- a. With the calculated dose from the release of tritium and radionuclides in particulate form with half-lives greater than 8 days, in gaseous effluents exceeding any of the above limits, prepare and submit to the Comission within 30 days, pursuant to Technical Specification Section 6.0, a Special Report that identifies the cause(s) for exceeding the limit and defines the corrective actions that have been taken to reduce the releases and the proposed corrective actions to be taken to assure that subsequent releases will be in compliance with the above limits,
- b. The provisions of Control 3.0,3 are not applicable.
'SURVEILLAhCE REQUIREMENTS 4.11.2.3 Cumulative dose contributions for the current calendar quarter and current calendar year for tritium and radionuclides in particulate. form with half-lives greater than 8 days shall be determined in accordance with the methodology and parameters in the ODCM at least once per 31 days.
SHOREHAM_- UNIT 1 1.3-27 Revision 18 - May 1991
-RADIOACTIVE EFFLUENTS CASEOUS RADWASTE TREATHENT SYSTEM CONTROLS 1 3.11.2.4 [No Longer in Use)- SURVEILLANCE REQUIREMENTS 4.11.2.4 (No Longer in Use) SHOREHAM - UNIT 1 1.3-28 Revision 17 - May 1991
RADIDACTIVE EFFLUENTS M'TILATION EXRAUST TREATMENT SYSTDi CONTROLS 3.11.2.5 (No Longer in Use] SURVEILLANCE REQUIREMENTS 4.11.2.5.1 (No Longer in Use) 4.11.2.5.2 (No Longer in Use) 1 SHOREHAM - UNIT 1 I.3-29 Revision 17 - May 1991
I RADIDACTIVE EFFLUENTS EXPLOSIVE GAS MIXTURE LIMITING CONDITION FOR OPERATION ___ 3.11.2.6 (NotUsed). rap 10ACTIVEEFFLUENTS MAIN CONDENSER LIMITING CONDITION FOR OPERATION 3.11.2.7 (NotUsed). SHOREHAM -. UNIT 1 I.3-30 Revision 16 - July 1990
s RADI0 ACTIVE EFTLUENTS CONTAIhMENT PURGING AND VENTING
., CONTROLS 3.11.2.8 [No Lonter in Use)
SURVEILLANCE RE0';IREMENTS 4.11.2.8.1 [No Longer in Use] 4.11.".6.2 [No Longer in Use] 4.11.2.8.3 [No Longer in Use) SHOREHAM - UNIT 1 1.3-31 Revision 17 - May 1991
RADI0 ACTIVE EFFLUENTS , SURVEILLANCE REQUIREMENTS This page intentionally left blank. SHOREHAM - UNIT 1 1.3-32 Revision 17 - May 1991
s RADI0 ACTIVE EFTLUENTS
- SURVEILLANCE REQUIRDfENTS RADIOACTIVE EFFLUENTS 3/4.11,3 (No Longer in Usej E
SHOREHAM - UNIT 1 I'3'33 Revision 17 - Nay 1991 l r
RADIDACTIVE EFFLUENTS 3/4.11.4 TOTAL DOSE CONTROLS 3.11.4 The annual (calendar year) dose or dose commitment to any MEMBER OF THE PUBLIC due to releases of radioactivity and radiation from unranium fuel cycle sources shall be lim'ted to less than or equal to 25 mrem; to the total body or any organ, except the thyroid, which shall be limited to less than or equal to 75 mrems. APPLICABILITY: At all times. ACTION:
- a. With the calculated doses from the release of radioactive materials in liquid or gaseous effluents exceeding twice the limits of Controls 3.11.1.2a., 3.11.1.2b., 3.11.2.2a., 3.11.2.2b.,
3.11.2.3a., or 3.11.2.3b., calculations should be made including direct radiation contributions from the reactor units and from outside storage tanks to determine whether the above limits of Control 3.11.4 have been exceeded. If such is the case, prepare and submit to the Commission within 30 days, pursuant to Technical Specification Section 6.0, a Special Report that defines the corrective action to be taken to reduce subsequent releases to prevent recurrence of exceeding the above limits and includes the schedule for achieving conformance with the above limits. This > Special Report, as defined in 10-CFR 20.405c, shall include an analysis that estimates the radiation exposo.e (dose) to a MEMBER OF THE PUBLIC-from_ uranium fuel cycle sources, including all effluent pathways and direct radiation, for the calendar year that includes the release (s) covered by this report. It shall also describe _ levels of radiation and concentrations of radioactive material involved, and the cause of the exposure levels or concentrations. If the estimated dose (s) exceeds the above limits, and if the release condition resulting in violation of 40 CFR Part 190 has not already been corrected, the Special Report shall include a request for-a variance-in accordance with the provisions of 40 CFR Part 190. Submittal of the report is considered a timely request, and a variance is granted until staff action on the request is complete,
- b. -The provisions'of Control 3.0.3 are not applicable.
SURVEILLANCE REQUIREMENTS 4.11.4.1 Cumulati. . dose contributions from liquid and gaseous effluents shall be determined in accordance with Controls' 4.11.1.2, 4.11.2.2, and 4.11.2.3, and in accordance with the methodology and parameters in the ODCM. ; 4,11.4.2 Cumulative dose contributions from direct radiation from the i reactor units and from radwaste storage tanks shall be determined in i accordance wich the methodology and parameters in the ODCM. This requirement i is applicable only under conditions set forth in Control 3.11.4a. ' SHOREHAM - UNIT 1 1.3-34 Revision 18 - May 1991 )
3/4.12 RADI0 ACTIVE ENVIRONMENTAL MONITORING 3/4.12.1 MONITORING PROGRAM CONTROLS 3.12.1 The radiological environmental monitoring program shall be conducted as specified in Table 3.12.1-1.- APPLICABILITY: At all times. ACTION:
- a. With the radiological environmental program not being conducted as specified in Table 3.12.101, prepare and submit to the Conmission, in the Annual Radiological Environmental Operating Report required by Control 6.9.1.6, a description of the reasons for not conducting the program as required and the plans for preventing a recurrence.
- b. With the level of radioactivity as the result of plant effluents in an environmental sampling medium at a specified location exceeding the reporting levels of Table 3.12.1-2 when averaged over any calendar quarter, prepare and submit to the Commission, within 30 days, pursuant to Technical Specification 6.9.2, a Special Report that identifies the cause(s) for exceeding the limit (s) and defines the corrective actions to be taken to reduce radioactive effluents so that the potential annual dose
- to A MEMBER OF THE PUBLIC is less than the calendar year limits of Controls 3.11.1.2, 3.11.2.2, and 3.11.2.3. When more than one of the radionuclides in. Table 3.12.1-2 are detected in the sampling medium, this report shall be submitted if:
concentration (1) -+ concentration (2) + ... fl.0 reporting level (1) reporting level (2) When radionuclides other than those in Table 3.12.1-2 are detected and are the result of plant effluents, this report shall be submitted if the potential annual dose
- to A MEMBER OF THE PUBLIC is equal to or greater than the calendar year limits of Controls 3.11.1.2, 3.11.2.2, and 3.11.2.3. This report is not required if-the measured level of radioactivity was not the result of plant ,
effluents; however, in such an event, the condition shall be reported and described in the Annual Radiological Environmental Operating Report.
- The methodology and parameters used to estimate the potential annual dose to a MEMBER OF THE PUBLIC shall be indicated in this report.
SHOREHAM UNIT 1 1.3-35 Revision 16 - July 1990
~
RADIOLOGICAL Eh,lRONMENTAL MONITORING CONTROLS (Continued) ACTION: (Continued)
- c. With fresh leafy vegetable samples discontinued from one or more of the sample locations required by Table 3.12.1-1, identify locations for obtaining replacement samples and add them to the radiological environmental monitoring program within 30 days. The specific locations from which samples were unavailable may than be deleted from the monitoring program. Pursuant to Control 6.9.1.7, identify the cause of the unavailability of samples and identify the new location (s) for obtaining replacement samples in the next Semiannual Radioactive Effluent Release Report and also include in the report a revised _ figure (s) and table for the ODCM reflecting the new location (s).
- d. The provisions of Control 3.0.3 are not applicable.
SilRVE1LLANCE REQUIREMENTS 4.12.1 The radiciogical environmental samples shall be collected pursuant to Table 3.12.1-1 from the specific locations given in the table and figures in the ODCM. and shall be analyzed pursuant to the requirement of Table 3.12.1-1 and the detection capabilities required by 4.12.1-1, I l i SHOREHAM - UNIT 1 1.3-36 Revision 18 - May 1991 l l
' TABLE : .1-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM
- EXPOSURE PATHWAY NUMBER OF REPRESENTATIVE SAMPLING AND TYPE AND FREQUENCY a
AND/0R SAMPLE SAMPLES AND SAMPLE COLLECTION COLLECTION FREQUENCY OF ANALYSIS b
- 1. DIRECT RADIATION 18 routine monitoring stations. Quarterly Garra dose quarterly.
DRI-DR16, DR30-DR31 either with two or more dosimeters or with one instrument for measuring and recording dose rate continuously, placed as follows:
- a. A ring of' stations, one in each meteorological sector in the general area of the SITE BOUNDARY,
,s DRI-DR16; w $; b. The remaining'two stations, DR-30 and DR31 serve as control locations.
E' 1
?
8 1 3 4 G 2
TABLE 3.1 1 (Continued) RADIOLOGICAL ENVIR0tCdTAL MONITORING PROGRAM
- EXPOSURE PATHWAY NUMBER OF REPRESENTATIVE SAMPLING AND TYPE AND FREQUENCY a
AND/0R SAMPLE SAMPLES AND SAMPLE COLLECTION COLLECTION FREQUENCY OF ANALYSIS
- 2. AIRBORNE Gross Beta and Samples from 5 locations. Al-A5: Continuous sampler Particulate Sampler:
Gamma Isotopics operation with sample Gross beta radioactivity 3 samples, Al-A3* from close collection weekly, or analysisfolleging
-to the 3 SITE BOUNDARY locations, more frequently if filter change; Gap in different sectors, of the required by dt:st isotopic analysis of nighest calculated annual average loading. composite (by location) groundlevel D/Q. quarterly.
I sample, A4, from the vicinity . of a comunity having the highest Y calculated annual average groundlevel M D/Q. I sample, AS, from a control location as for example 15-30 km distant and I" the least prevalent wind direction.c
- 3. WATERBORNE x a. Surface h 1 sample control, Wal Grab sample Gamma isotopic analysis' 3 (Long Island I sample discharge, Wa2 or Wa3 semiannually. and tritium analysis
". Sound) semiannually. O
- b. Not Used
- c. Sediment from I sample from downstream area with Semiannually. Gama isotopic analysis'
- r shoreline existing or potential recreational semiannually.
4 value, Wdl.
*The first and second highest D/Q sectors have particulate samples. The third highest D/Q sector at the SITE BOUNDARY is approximately 150 ft from the first highest sector.
TABLE 3.17 1 (Continued) RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM
- EXPOSURE PATHWAY NUMBER OF REPRESENTATIVE SAMPLING AND TYPE AND FREQUENCY a
AND/OR SAMPLE SAMPLES AND SAMPLE COLLECTION COLLECTION FREQUENCY OF ANALYSIS
- 4. INGESTION
- a. Not Used
- b. Fish and I sample of each commercially and Sample in season Gamma isotopic analysis' Invertebrates .recreationally important species in or serciannually if on edible portions.
vicinity of plant discharge area, they are not seasonal. Ibl-Ib2. I sample of same species in areas not influenced by plant discharge, Ib3.
- c. FOOD PRODUCTS Samples of 3 different kinds of At time of harvest.I Gamma isotopic' analysis.
e broad leaf vegetation grown nearest each of two different offsite locations of highest predicted annual average ground-level D/Q, Ic1 - Ic2. I sample of each of the similar At time of harvest.I Gamma isotopic
- analysis.
broad leaf vegetation grown 15-30 km distant in the least prevalent wind
,, direction, Ic3.
E s' C a b i 3 G 5
TABLE 3.12.1-1 (Continued) TABLE NOTATIONS a Specific paraneters of dit ance and direction sector from the et sterline of one reactor, and additional description where pertinent, are provided for each and every sample location in Table 3.12.1-1 in a table and figure in the ODCM. Refer to NUREG-0133, " Preparation of Radiological Effluent Technical Specifi-cations for Nuclear Power Plants,' October 1978, and to Radiological Assessment Branch Technical Position, Pevision 1, November 1979. Deviations are permitted from the required sa.1pling schedule if specimens are unobtain-able due to hazardous conditions, seasonal unavailability, rnalfunction of automatic sampling equipnnt, and other legitimate reasons. If specinens are unobtainable due to sampling equipment malfunction, every effort shall be made to complete corrective action prior to the end of the next sampling period. All deviations from the sampling schedule shall be documented in the Annual Radiological Environmental Operating Report pursuant to Controls 6.9.1.6. It is recognized that, At tirnes, it tray not be sossible or practicable to continue to obtain samples of the media of cloice at the niost desired location or time. In these instances suitable alternative media and locations may be chosen for the particular pathway in question and appropriate substitutions made within 30 days in the radiological environmental monitoring program. Pursuant to Control 6.9.1.7, identify the cause of the unavailability of samples for that pathway and identify the new location (s) for obtaining replacement samples in the next Semiannual Radioactive Effluent Release Report and also include in the report a revised figure (s) and table for the ODCM reflectingthenewlocation(s). b 0ne or more instruments, such as a pressurized ion chamber, for measuring and recording dose rate continuously may be used in place of or in addition to, integrating dosinieters. For the surposes of this table, a thermoluminescent dosimeter (TLD) is considered to )e one phosphor; twu or more phosphors in a packet are considered as-two or more dosimeters. Film badges shall not be ' used as dosimeters for ineasuring direct radiation. The frequency of ar.alysis or readout for TLD systems will depend upon the characteristics of the specific system used and should be selected to obtain optimum dose information ' with minimal fading. C The purpose of this sample is to obtain background infonnation. If it is not practical to establish control locations in accordance with the distance and wind direction criteria, other sites that provide valid background data 'nay be substituted. i d Airborne particulate sample filters shall be analyzed for gross beta radioactivity 24 hours or more after sampling to allow for radon and thoron
-daughter decay. If gross beta activity in air particulate samples is greater than 10 times the yearly mean of control samples, gama isotopic analysis
-shall be performed on the individual samples.
'Garua isotopic analysis means the identification and quantification of gama-emitting radionuclides that may be attributable to the effluents from the facility.
SHOREHAM - UNIT 1 1.3-40 Revision 16 - July 1990 l l-- -
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TABLE 3.12.1-1(Continued) ; TABLE NOTATIONS (Continued) I Not Used 9The dose shall be calculated for the maximum organ and age group, using the enethodology and parameters in the ODCH. h The " control" sample shall be taken at a distance beyond significant influence of the discharge. The " discharge" sample shall be taken in an area beyond but near the mixing zone. 1 1f harvest occurs more than once a year, sampling shall be perfonned during each discrete harvest It' harvest occurs continously, sampling shall be rnonthly. Attention v:,411 be paid to including samples of tuberous and root food products. SHOREHAM - UNIT 1 1.3 A1 Revision 17 May 1991
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- r 1.3-42 Revision 17 - May 1991
~
x , TA8: .12.1-1 ab DETECTION CAPABILITIES FOR ENVIRONNENTAL SAMPLE ANALYSIS LOWER LIMIT OF DETCCTION (LLD)c AIRBORNE PARIICULATE FISH FOOD PR0t/JCTS SEDIMENTS WATER OR GAS (pC1/L) (pCi/m3 ) Q s/kg, wet) (pCf/kg, wet) (pCf/kg, dry) ANALYSIS Gross Beta 4 0.01 H-3 3000 7 Y Mn-54 15 130 0 130 Co-60 15 Zn-65 30 260 0.05 130 60 150 Cs-134 15 0.06 150 80 180 Cs-137 18 E' 1 lL 8 I x 2 1 i
TABLE 4.12.1-1 (Continued) TABLE NOTATIONS aT his list does not mean that only these nuclides are to be considered. Other peaks that are identifiable, together with those of the above nuclides, shall also be analyzed and reported in the Annual Radiological Environmental Operating Report pursuant to Control 6.9.1.6. IRequireddetectioncapabilitiesforthermoluminescentdosimetersusedfor , environmental measurements are given in Regulatory Guide 4.13. 1 CThe LLD is defined, for the purposes of these specifications, as the smallest concentration of radioactive material in a sample that will yield a net count, above system background, that will be detected with 95% probability with only 5% probability of falsely concluding that a blank observation represents a "real" signal. For a particular nieasurement system, which may include radiochemical separation: LLD = 4.66 s b
~~
E . V . 2.22 . Y. exp (- Aht) Where: LLD is the "a priori" lower limit of detection as defined above, as picocurie per unit mass or volume, ssis the standard deviation of the background counting rate or of the cDunting rate of a blank sample as appropriate, as counts per minute. E is the counting efficiency (as counts per transfonnation), V is the sample size in units of mass or volume, 2.22 is the number of transformations per minute per picoeurie, Y is the fractional radiochemical yield, when applicable. A is the radioactive decay constant for the particular radionuclide, and At for environmental sampler is the elapsed time between sample collection, or end of the sample collection period, and time of counting. Typical values of E, V, Y, and At shall be used in the calculations. SHOREHAM - UNIT 1 1.3-44 Revision 17 - May 1991
i TABLE 4.12.1-1 (Continued) TABLE NOTATIONS (Continued) It should be recognized that the LLD is defined as an a prior (before the fact) limit representing the capability of a measuremeiit system and not as an a posteriori (af ter the fact) limit for a 3 articular measurement, Analyses , shall be performed in such a manner that 11e stated LLDs will be achieved under routine conditions. Occasionally background fluctuations, unavoidably small sample sizes, the presence of interferring nuclidn, pr other uncontrollable circumstances may render these LLDs unachievable. In such cases, the contributing factors shall be identified and described in the Annual Radiological Environmental Operating Report pursuant to Control 6,9.1.6. SHOREHAM - UNIT 1 1.3-45 Revision 17 - May 1991
RADIOLOGICAL ENv!RONMENTAL MONITORING 3/4.12.2 LAND USE CENSUS CONTROLS , E12.2 A l'and use census shall be conducted and shall identify within a distanceof8km(5 miles)thelocationofeachofthe16 meteorological sectors of the nearest milk 2animal, jhe nearest residence, and the nearest garden of greater than 50 m' (500 f t ) producing broad leaf vegetation.* For elevated releases as defined in Regulatory 'iuide 1.111, Revision 1. July 1977, the land use census shall also identify within a distance of 8 km (5 rniles) the locations in each of the 16 ojeteorological sectors of all milk animals and all gardens of greater than 50 m (500ft)producingbroadleafvegetation. Appt!CABILITY: At ali times. ACTION:
- a. With a land use census identifying a location (s) which yields a calculated dose or dose conenitment greater than the values currently being calculated in Control 4.11.2.3, identify the new location (s) in the next Semiannual Radioactive Effluent Release Report, pursuant to Control 6.9.1.7. ,
- b. With a land use census identifying a location (s) which yields a calculated dose or dose commitment (via the same exposure pathway) 20 percent greater than at a location from which samples are currently being obtained in accordance with Control 3.12.1, add the new location (s) to the radiological environmental monitoring program within 30 days. Thesamplinglocation(s),excludingthecontrol !
station location, having the lowest calculated dose or dose commitment (s) (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. pursuant to Control 6.9.1.7, identify the new location (s) in the next Semiannual Rrdioactive Effluent Release Report and also include in the report a revised figure (s) and table for the ODCM reflecting the new location (s),
- c. The provisions of Control 3.0.3 are not applicable.
SURVEILLANCE REOUIREMENTS 4.12.2 The land use census shall be conducted during the growth season at least once per 12 months using that information that will provide the best ; results, such as by a door to-door survey, aerial survey, or by consulting local agriculture authorities. The results of the land use census shall be included in the Annual Radiological Environmental Operating Report pursuant to Control 6.9.1.6.
- Broad. leaf vegetation sampling of at least three different kinds of vegetation may be performed at the SITE BOUNDARY in each of two different direction sectors with the highest predicted D/Qs in lieu of the garden census. Specifications for broad leaf vegetation sampling in Table 3.12.1-1,
. item 4,c., shall be followed, including analysis of control samples, SHOREHAM - UNIT 1 1.3-46 Revision 18 - May 1991 1
. - - --- 4--. v.+,%~ ,m.,m,, n+--,-.. ,..,w ,,, ..--..__,..y.. ...,_-w--~,,. _.,-,,.,_,.,_y. . , . ,,.,,,~.%., ..y,._,,
6 mmIE RADIOLOGICAL EkVIRONMENTAL MONITORING 3/4.12.3 INTERLABORATORY COMPARISON PROGRAM CONTROLS 3.12.3 Analyses shall be performed on radioactive materials supplied as part of an Interlaboratory Comparison Program that has been approved by the Connission, that corresponds to samples required by Table 3.12.1 1. APPLICABILITY: At all tines. ACTION:
~
- a. With analyses not being performed as required above, report the corrective actions taken to prevent a recurrence to the Commission in the Annual Radiological Environmental Operating Report pursuant to Control 6.9.1.6.
- b. The provisions of Control 3.0.3 are not applicable.
$URVEILLANCE REQUIREMENTS
- 4.12.3 The Interleboratory Comparison Program _shall be described in the ODCM.
A summary of the results obtained as part of the above required Interlaboratory Comparison Program shall be included in the Annual Radiological Environmental Operating Report pursuant to Control 6.9.1.6. SHOREHAM - UNIT 1 1.3-47 Revision 18 - May 1991
f. t
$NPS-1 ODCM j PART 1 SECTION 4 t
t i RADIOLOGICAL EFFLUENT i CONTROLS : h BASES FOR SECTIONS 3.0 AND 4.0 : CONTROLS AND ! SURVElLLANCE REQUIREMENTS
?
1 [
?
d i l. e 1.4-0 Revision 16 - July 1990 , ;
i 4 i I i l I r fj0TE ! 1he BASES contained in succeeding pages sunnarize ! the reasons for the Controls in Sections 3.0 and s 4.0, but in accordance with 10 CFR 50.36 are > not part of these Controls. ; i r I d I s b e
?
i 1 1,4-1 Revision 16 . July 1990 , i r t
- . . . , , . _ . , . . , _ _ . _ . - . _ . , _ . , , , , _ . . _ . . . . . ,..,..._.,_.,____.._..,__,,__m.._....s_,.,
. - , . . ,. . _ _ . _ . . ~ . . . , , , .. , . . . , . - , _ . , , . . . _ . ., - . .
INDEX , BASES SECTION PAGE INSTRUMENTATION 3/4.3.7 HONITORING INSTRUKENTATION Radioactive Liquid Effluent Monitoring......... 1.4-3 Instrumentation Radioactive Gaseous Effluent Monitoring........ 1.4-3 Instrumentation 3/4.11 RADIOACTIVE EEFLUENTS 3/4.11.1 LIQUID EFFLUENTS Concentration................................ 1.4-3 Dose......................................... 1.4-4 Liquid Radwaste Treatment System............. 1.4-4 3/4.11.2 GASEOUS ETTLUENTS Dose Rate.................................... 1.4-5 Dose - Noble Gases........................... 1.4-5 Dose - Tritium and Radionuclides in Particulate Tora........................... 1.4-6 3/4.11.4 TOTAL D0SE................................... 1.4-7 3/4.12 RADIOLOGICAL ENVIRONMENTAL MONITORING 3/4.12.1 MONITORING PR0 GRAM........................... 1.4-8 3/4.12.2 LAND USE CENSUS.............................. 1.4-8 3/4.12.3 INTERLABORATORY COMPARISON PROGRAM........... 1.4-9 SHORERAM - UNIT 1 1.4-2 Revision 17 - May 1991 l i ,- . . ~ , _ _ , . - _ , . , . _ _ . , _ _ , . . _ _ _ _ , _ _ _ _, , _ _ _ _ _ _ _ _ _ _ ___ _ . _ , . _
INSTRUMENTATION M5T5 3/4.3.7 MO E ORING INSTkURUlTATION 3/_4.3.7.10_ RAJ10ACTlkE LIQUID EFFLUENT MONITORING INSTRUMENTATION The radioactive liquid effluent monitoring instrumentation is provided to monitor and control, as applicable, the releases of radioactive material in liquid effluents during actual or potential releases of liquid effluents. The alarm / trip setpoints for these instruments shall be calculated and adjusted in accordance with the methodology and parameters 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. 3/4.3.7.11 RADI0 ACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION The radioactive gaseous effluent monitoring instrumentation is provided to monitor and control, as applicable, the releases of radioactive materials in gaseous effluents during actual or potential releases of gaseous ef fluents. The alarm / trip setpoints for these instruments shall be calculated and adjusted in accordance with the methodology and parameters in the ODCM to ensure that the alarm / trip will occur prior to exceeding the limits of 10 CFR Part 20. This instrumentation also includes provisions for monitoring (and controlling) the concentrations of potentially explosive gas mixtures in the -main condenser offgas treatment system. 1he 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. 3/4.11.1 LIQUID EFFLUENTS 3/4.11.1.1 CONCENTRATION This Control is provided to ensure that the concentration of radioactive materials released in liquid waste effluents to UdRESTRICTED AREAS will be less than the concentration levels specified in 10 CFR Part 20. Appendix B,_ Table 11. Column 2. This limitation provides additional assurance that the levels of radioactive materials in bodies of water in UNRESTRICTED AREAS will result in exposure within (1) the Section !!.A design objectives of Appendix 1, 10 CFR 20.106(e) to the population. The concentration limit for dissolved or entrained noble gases is. based upon the assumption that Xe-135 is the controlling radioisotope and its MPC air (submersion) was converted to an equivalent concentration in water using the methods described in International Comission on Radiological Protection (ICRP) Publication 2. This Control applies to the release of radioactive materials in liquid effluents from all reactor units at the site. The required detection capabilities for radioactive materials in liquid waste samples are tabulated in terms of the lower limits of detection (LLDs). Detailed discussion of the LLD, and other detection limits can-be found_in HASL Procedures Manual, HASL.300 (revised annually), Currie, L. A., " Limits for Qualitative Detection and Quanotative Determination - Application -to Radiochemistry," Anal-Chem, 40, 586-93 (1968), and Hartwell, J. K., Detection Limits for Radioanalytical Counting Techniques, Atlantic Richfield Hanford Company Report ARH-SA215 (June 1975). SHOREHAM - UNIT 1 1.4-3 Revision 16 - July 1990
3/4.11 RADIDACTIVE_ EFFLUENTS BASES 3/4.11.1.2 DOSE This Control is provided to implement the requirements of Sections ll.A, Ill.A and_IV.A of Appendix 1, 10 CFR Part 50. The Control implements the guides set forth in Section ll.A of Appendix 1. The ACTION statements provide the required operating flexibility and at the same time implement the guides set forth in Section IV.A of Appendix I to assure that the releases of radioactive material in liquid effluents will be kept "as low as reasonably achievable." The dose calculation methodology and parameters in the ODCM implement the requirements in Section Ill.A of Appendix 1 that confomance with the guides of Appendix I be shown by calculational procedures based on models and data, such that the actual exposure of a MEMBER OF THE PUBLIC through appropriate pathways is unlikely to be substantially underestimated. The equations specified in the ODCM for calculating the doses due to the actual release rates of radioactive materials in liquid effluents are consistent with the inethodology provided in Regulatory Guide 1.109,
" Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix 1,"
Revision 1, October 1977 and Regulatory Guide 1.113. " Estimating Aquatic Dispersion of Effluents from Accidental and Routine Reactor Releases for the Purpose of implementing Appendix 1," April 1977. This Control applies to the release of radioactive materials in liquid effluents from each reactor at the site. For units with shared radwaste treatment systems, the liquid effluents from the shared system are proportioned among the units sharing that system. 3f_4.11.1. 3 LIQUID RADWASTE TREATMENT SYSTEM The OPERABILITY of the liquid radwaste treatment system ensures that this system will be available for use whenever liquid effluenu require treatment prior to release to the environment. The requirement that the appropriate portions of this system be used when specified provides assurance that the releases of radioactive materials in liquid effluents will be kept "as low as-is reasonably achievable." This Control implements the requirements of 10 CFR 50.36a, General Design Criterion 60 of Appendix A to 10 CFR Part 50 and the design objective given in Section !!.D _of Appendix ! 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 ll.A of Appendix 1, 10 CFR Part 50, for liquid effluents, 3/4.11.2 GASE0US EFFLUENTS SHOREHAM - UNIT 1 1,4-4 Revision 16 - July 1990 4
RADIOACTIVE EFFLUENTS UATE5 3/4.11.2.1 DOSE RATE This Control is provided to ensere that the dose at any time at and beyond the SITE BOVNDARY 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. These limits provide reasonable assurance that radioactive material discharged in gaseous effluents will not result in the exposure of a MEMBER Of THE PUBLIC in an unrestricted area, either within or outside the SITE BOUNDARY, to annual average concentrations exceeding the limits specified in Appendix B. Table 11 < of10CFRPart20(10CFR20.106(b)). For a MEMBER OF THE PUBLIC who may at times be within the SITE BOUNDARY, the occupancy of the MEMBER OF THE PUBLIC will be sufficiently low to compensate for any increase in the atmospheric diffusion factor above that for the SITE BOUNDARY. The specified release rate l limits restrict, at all times, the corresponding gamma and beta dose rates above background to a MEMBER Of THE PUBLIC at or beyond the SITE BOUNDARY, to i 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 rate above background to a child via the inhalation pathway to less than or equal to 1500 mrem / year. This Control applies to the release of radioactive materials in gaseous effluents from all reactor units at the site. The required detection capabilities for radioactive materials in gaseous waste samples are tabulated in terms of the lower limits of detection (LLDs). Detailed discussion of the LLD, and other detection limits can be found in HASL Procedures Manual. HASL-300 (revised annually) Currie, L. A., " Limits for Qualitative Detection and Quantitative Determination - Application for Radiochemistry," Anal. Chem 40,586-93(1968), and Hartwell, J. K., Detection . Limits for Radioanalytical Counting Techniques," Atlantic Richfield Hanford , CompanyReportARH-SA215-(June 1975). 3/4.11.2.2 DOSE - NOBLE GASES This Control is provided to implement the requirements of Sections 11.B. 111. A and IV. A of Appendix 1,10 CFR Part 50. The Control implements the guides set forth in Section II.B of Appendix 1. The ACTION statements provide the required operating flexibility and at the same time implement the guides set forth in Section IV.A cf Appendix ! to assure that the releases of radioactive material in gaseous effluents will be kept "as low as is reasonably achievable." The Surveillance Requirements implement the . requirements in Section 111.A of Appendix ! that conformance with the guides of Appendix ! be shown by calculational procedures based on models and data such that the actual exposure of a MEMBER OF THE PUBLIC through appropriate pathways is unlikely to be substanially underestimated. The dose calculation methodology and parameters established in the ODCM for calculating the doses due to the actual release rates of radioactive noble gases in gaseous - effluents-are consistent with the methodology provided in Regulatory Guide 1.109, " Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50 Appendix 1, October 1977 and Regulatory Guide 1.111. " Methods for estimating SHOREHAM - UNIT 1 1.4-5 Revision 16 - July 1990
DOSE - NOBLE CASES (Continued) Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases . from Light-Water Cooled Reactors." Revision 1. July 1977. The ODCH equations l provided for determining the air doses at the SITE BOUNDARY are based upon the historical average atmospheric conditions. 3/4.11.2.3 DOSE - TRITItH AND RADIONUCLIDES IN PARTICULATE FORM This Control is provided to implement the requirements of Sections 11.C. III.A and IV.A of Appendix 1, 10 CFR part 50. The Controls are the guides set forth in Section II.C of Appendix 1. The ACTION statements provide the required operating flexibility and at the same time implement the guides set forth in Section IV.A of Appendix ! to assure that the releases of radioactive materials in gaseous effluents will be kept "as low as is reasonably achievable." The ODCH calculational methods specified in the Surveillance Requirements implement the requirements in Section III.A of Appendix ! that conformance with the guides for Appendix 1 be shown by calculational procedures based on models and data, such that the actual exposure of a MEMBER OF THE PUBLIC through appropriate pathways is unlikely to be substantially underestimated. The ODCH calculational methods 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 of Reactor Ef fluents f or the purpose _ of Evaluating Compliance with 10 CFR part 50, Appendix 1 " Revision 1, October 1977 and Regulatory Guide 1.111. "Hethods for Estima. ting Atmospheric Transport and Disperaion of Gaseous Effluents in Routine P leases from Light-Water-Cooled Reactors," Revision 1 July 1977. These equations also provide for determining the actual doses based upon the historical average atmospheric conditions. The release rate specifications for radionuclides 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 grace with consumption of the milk and meat by man, and (4) deposition on the ground with subsequent exposure of man. 3/4.11.2.4 [No Longer in Usel SHOREHAM - UNIT 1 1.4-6 Revision 17 - May 1991 l i
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RADIDACTIVE TFFLPflg BASES 3/4.11.2.5 [No Longer in Use] 3/4.11.2.8 (NoLongerinUsel
}/4.11.4 TOTAL DOSE This Contol is provided to mee he dose limitations of 40 CFR Part 190 that have been incorporated into 10 R Part 20 by 46 TR 18525. The Control requires the preparation and submittal of a Special Report whenever the calculated doses from plant-generated radioactive effluents and direct radiation exceed 25 mrems to the total body or any organ except the thyroid, which shall be limited to less than or equal to 75 mrems. For sites containing up to four reactors, it is highly unlikely that the resultant dose to a MEMBER OF THE FUBLIC vill exceed the done limits of 40 CTR Part 190 if the individual reactors remain within twice the dose design objectives of Appendix 1, and if direct radiation doses from the reactor units and outside storage t anks are kept small. The Special Report will describe a course of action that should result in the limitation of the annual dose to a HEMBER OF THE PUBLIC to within 40 CTR Part 190 limits. For the purposes of the Special Report, it may be assumed that the dose committnent to the MEMBER Or THE PUBLIC from other uranium fuel cycle sources is negligible, with the exception that dose contributions from other nuclear fuel cycle facilities at the same site or within a radius of 8 km must be considered. If the dose to any MEMBER OF THE FUBLIC is estimated to exceed the requirements of 40 CTR Part 190, the Special Report with a request foi a variance (provided the release conditions resulting in violation of 40 CFR Part 190 have not already been corrected). In accordance with the provisions of 40 CFR 190.11 and 10 CFR 20.40$c, is considered to be a timely request and fulfills the requirements of 40 CFR Part 190 until NRC staff action is completed. The variance only relates to the Itcits of 40 CFR Part 190, and does not apply in any voy to the other require-ments for dose limitation of 10 CTR Part 20, as addressed in Controlo 3.11.1.1 and 3.11.2.1. An individual is not considered a MEMBER OF THE PUBLIC during any period in which he/she is engaged in carrying out any operation that is part of the nuclear fuel cycle.
SHORERAM - UNIT I I.4-7 Revision 17 - May 1991
3/4.12 RADIOLOGICAL ENVIRONMENTAL. MON!TORING BASES 3/4.12.1 MONITORING PROGRAM The radiological monitoring program required by this Control provides representative measurements of radiation and of radioactive materials in those exposure pathways and for those radionuclides that lead to the highest ' potential radiation exposures of individuals resulting from station decontamination. This monitoring program implements Section IV.B.2 of Appendix ! to 10 CFR Part 50 and thereby supplements the radiological effluent monitoring program by verifying that the measurable concentrations of radioactive materials and levels of radiation are not higher than expected on the basis of the effluent measurements and modeling of the environmental exposure pathways. Guidance for this monitoring program is provided by the Radiological Assessment Branch Technical Position on Environmental Monitoring. The required detection capabilities for environmental sample analyses are tabulated in terms of the lower limits of detection (LLDs). The LLDs required by Table 4.12-1 are considered optimum for routine environmental measurements in industrial laboratories. It should be recognized that the LLD is defined as an a priori (before the fact) limit representing the capability of a measurement system and not as an a posteriori (af ter the fact) limit for a particular mearurement. Detailed discussion of t' e LLD, and other detection limits, can be found in HASL Procedures Manual, HASL-300 (revised annually), Currie, L. A.. " Limits for Qualitative Detection and Quantitative Determination - Application to Radiochemistry," Anal. Chem. 40,586-93(1968), and Hartwell. J. K.,
Detection Limits for Radioanalytical Countin Hanford Company Report ARH-SA-215 (June 1975)g Techniques," Atlantic Ric Composite sampling and drinking water requirements are not applicable.
.No public drinking water supplies could be affected by the plant's discharge since groundwater drainage is to the north into Long Island Sound (ER2.5.3.2).
3/4.12.2 LAND USE CENSUS This Control is provided to ensure that changes in the use of areas at or beyond the SITE BOUNDARY are identified and that modifications to the monitoring program are made if required by the results of this census. The best survey information from the door-to door survey, from aerial survey, or from consulting with local agricultural authorities shall be used. This census satisfies the requirements of Section IV.B.3 of Appendix 1 to 10 CFR Part 50. Restricting the census to gardens of greater than 500 square feet provides assurance that significant exposure pathways via leafy vegetables will be identified and monitored since a garden of this size is the minimum SHOREHAM - UNIT 1 1,4-8 Revision 17 - May 1991
I RADIOLOGICAL, ENVIRONMENTAL MONITOR!kG ; BASES 3/4.,12.2 LAND USE CENSUS (Continued) ! required to produce the quantity (26 kg/ year) of leafy vegetables assumed in -f Regulatory Guide 1.109 for consumption by a child. To determine this minimum i garden size, the following assumptions were used (1) that 20% of the garden l was used for growing broad leaf vegetation (i.e., similar to lettuce and i cabbage),and(2)avegetationyieldof2kg/squaremeter. l t 3/4.12.3 1NTERLABORATORY COMPARISON Pk9 GRAM ! The requirement for participation in as 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 part of the quality assurance program for l environmental monitoring in order to demonstrate that the results are. reasonably valid for the purposes of Section IV.B.2 of Appendix ! to 10 CFR ! Part 50. i I i i P b SHOREHAM - UNIT 1 1.4-9 Revision 16 - July 1990
s i i, i SNPS-1 ODCM i PART I : SECTION 5 1 E RADIOLOGICAL EFFLUENT CONTROLS 1 SECTION 5.0 DESIGN FEATURES i i t t i I i r f l 1. 1.5-0 Revision 16 - July 1990 i
INDEX DESIGN FEATURES SECTION PAGE 5.1 SITE
$11E BOUNDARY for Radioactive Gaseous and Liquid :
Effluents.......................................... 1.5-3 ' 1 1.5-1 Revision 16 - July 1990 l
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}NDEX l 1
LIST OF FIGURES 1
- _Fl GURE PAGE_
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1,5-4 Revision 16 - July 1990
l SNPS 1 ODCM i PART I SECTION 6 RADIOLOGICAL EFFLUENT CONTROLS SECTION 6.0 ADMINISTRATIVE CONTROLS i l i. 1
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INDEX ADMINISTRATIVE CONTROLS SECTION PAGE l 6.8 REPORTING REQUIREMENTS i 6.8.1 ANNUAL RADIOLOGICAL ENVIRONMEN1AL OPERATING REPORT..... 1.6 2 SEM1 ANNUAL RADI0 ACTIVE EFFLUENT RELEASE REPORT......... 1.6-2 i 6.13 0FFSITE D0$E CALCULATION MANUAL (0DCM)..................... 1.6 3 6.15 MAJOR CHANul5 TO RADIOACTIVE LIQUID AND GASEOUS. WASTE TREATMENT _5YSTEM5........................................ l.6-4 I t
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ADMINISTRAT!YE CONTROLS ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT 6.8.1.3 Routine Annual Radiological Environmental Operating Reports covering the operation of the unit during the previous calendar year shall be submitted prior to May 1 of each year. The initial report shall be submitted prior to May 1 of the following year following initial criticality. The Annual Radiological Environmental Operating Reports shall include sumaries, interpretations, and an analysis of trends of the results of the radiological environmental surveillance activities for the report period, including a comparison with preoperational 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 Control 3.12.2. The Annual Radiological Environmental Operating Reports shall include the results of analysis of all radiological environmental samples of all environmental radiation measurements taken during the period pursuant to the locations specified-in the table and figures in the ODCM, as well as sumarized and tabulated results of these analyses and measurements in the femat of the table in the Radiological Assessment Branch Technical Position, Revision 1, November 1979. In the event that some individual results are not available for inclusion with the report, the report shall be submitted noting and explaining the reasons for the missing results. The missing data shall be submitted at soon as possible in a supplementary report. The reports shall also include the following: a sumary description of the radiological environmental monitoring program; at least two legible maps
- covering all sampling locations keyed to a table giving distances and directions frcm the centerline of one reactor; the results of licensee participation in the Interlaboratory Comparison Program, required by Control 3.12.3; discussion of all deviations from the sampling schedule of Table 3.12-1; and discussion of all analyses in which the LLD required by Table 4.12 1 was not achievable.
}EMIANNUALRADIOACTIVEEFFLUENTRELEASEREPORT 6.8.1.4 Routine Semiannual Radioactive Effluent Release Reports covering the operation of the unit during the previous 6 months of operation shall be submitted within 60 days after January 1 and July 1 of each year. The period of the first report shall begin with the date of initial criticality. The Semiannual Radioactive Effluent Release Reports shall include a sumary of , the quantities of radioactive liquid and gaseous effluents and solid waste released from the unit as outlined in Regulatory Guide 1.21, " Measuring, Evaluating, and Reporting Radioactivity in Solid Wastes and Releases of Radio-active Materials in Liquid and Gaseous Effluents from Light-Water-Cooled Nuclear Power Plants," Revision 1, June 1974, with data sumarized on a quarterly basis following the format of Appendix B therof, ione map shall cover stations near the SITE BOUNDARY; a second shall include the more distant stations. SHOREHAM - UNIT 1 1.6-2 Revision 18 - May 1991
. o MMINISTRATIVECONTROLS ((MIANNUALRADI0ACTIVEEFFLUENTRELEASERip0RT(Continued) The Semiannual Radioactive Effluent Release Report to be submitted 60 days af ter January 1 of each year shall include an annual sumary of hourly meteorological data collected over the previous year. This annual suninary may be either in the form of an honr-by-hour listing of wind speed, wind direction, atmospheric stability and precipitation (if measured) on inagnetic tape, or in the form of joint frequency distribution of windspeed, wind direction and atmospheric stability." This some report shall include an assessment of the radiation doses due to the radioactive liquid and gaseous effluents released from the Unit or station during the previous calendar year. This same report shall also include an assessment of the radiation doses from radioactive liquid and gaseous effluents to MEMBERS OF THE PUBLIC due to their activities inside the $11E BOUNDARY (rigure $.1.3-1) during the report period. All assumptions used in making these assessments (i.e. specific activity, exposure time and location) shall be included in these reports. The meteorological conditions concurrent with the time of release of radioactive materials in 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 the methodology and parameters in the OFFSITE DOSE CALCULATION MANUAL (ODCM).
-The Semiannual Radioactive Effluent Release Report to be submitted 60 days af ter January 1 of each year shall also include an assessment of radiation doses to nearby uranium fuel cycle sources (including doses from primary effluent pathways and direct radiation) for the previous calendar year to show conformance with 40 CFR Part 190. Environmental Radiation protection Standards for Nuclear Pcwer Operation. Acceptable methods for calculating the dose contribution from liquid and gaseous effluents are given in Regulatory Guide 1.109. Rev. 1. October 1977.
The Semiannual Radioactive Effluent kelease Reports shall include a list and description of unplanned releases from the site to UNRESTRICTED AREAS of - radioactive materials in gaseous and liquid effluents made during the reporting period. The Semiannual Radioactive Effluent- Release Re> orts shall include any changes made during the reporting period to the OFFSITi DOSE CALCULATION MANUAL (0DCM), as well as listing of new locations for dose calculations and/or environmental monitoring identified by the land use census pursuant to Control 3.12.2. 6.13 0FFSITEDOSECALCULATIONMANUAL(ODCd See Technical Specification 6.13.
"In lieu of submission with the Semiannual Radioactive Effluent Release Report, the licensee has the option of retaining this summary of required meteorological data on file, in a file that shall be provided to the NRC upon request.
SHOREHAM - UNIT 1 1.6-3 Revision 18 - May 1991 miA 14ill
m . _ _ _ _ _ . _ _ _ - _ _ _ _ _ . _ _ F
-ADMINISTRATIVE CONTROLS 6.15- MAJOR CHANGES TO RADI0 ACTIVE LIQUID AND GASEOUS WASTE TREA1 MENT SYSTEMS 6.15.1- Licensee-initiated major changes to the radioactive waste treatment '
system (liquidandgaseous): ; I
- a. Shall be reported to the Commission in the Semiannual Radioactive Effluent Release Report for the period in which the evaluation was reviewed by the Review of Operations Comittee. The discussion of ,
each change shall contain: !
- 1. A summary of the evaluation that led to the determination that -
the change could be made in accordance with 10 CFR 50.59; .-
- 2. Oufficient detailed information to totally support the reason I for the change without benefit of additional or supplemental infonnation;
- 3. A detailed description of the equipment, components, and processes involved and the interfaces with other plant systems; ;
4 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; ;
- 5. An evaluation of the change which shows the expected maximum .
i exposures to a MEMBER OF 1HE pVBLIC in the UNRESTRICTED AREAS and to the general population that differ from those previously , estimated in the license application and amendments thereto;
- 6. A comparison of the predicted releases of radioactive materials, in liquid and gaseour affluents, to the actual releases for the period prior to when the changes are to be -
made;
- 7. An estimate of the exposure to plant operating personnel as a result of the change; and
- 8. Documentation of the fact that.the change was reviewed and found acceptable by the Review of Operations Committee,
- b. .Shall become effective upon review and acceptance by the ROC.
l SHOREHAM - UNIT 1- 1.6-4 Revision 16 - July 1990 ,
-. . - ~ . . - . - . . - - . - - . - . - . ~ . - . - - - i SNPS-1 ODCM , ? - PART 11 . , SECTION 1 ; INTRODUCTION r 1The' purpose of this manual is to show the calculational methodology and parameters i used to comply with the Radiological Effluent Controls (REC, Part 1) of the ODCM. I Section and the Gaseous2 establishes methods Eff1':ent Monitortuset calcultie points the Liquid in order Effluentwith to comply Monitor REC set Sections point -l 3.11.1.1 and 3.11.2.1, respectively. Section 3 establishes dose calculational methods for liquid and gaseous effluents.- The liquid effluents dose calculation methods are used to show compliance with REC l l Sections 3.11.1.2 and 3.11.1.3. . For liquid pathways, the dilution factor of 8.85 uesd in Section 3.1 is a calculated value based on a submerged, multiport diffuser wich a port discharge velocity of 12 fps, a 300 ft radius mixing zone, and 4 circulating water pumps dischar ing. If only service water pumps are discharging, the dilution factor is one (1.0 ThegaseouseffluentdosecalculationmethodsareusedtoshowcompliancewithRECl Sections 3.11.2.1, 3.11.2.2, and 3.11.2.3. _The otmospheric dispersion and deposi-tion factors used in calculation methods were calculated based on onsite metenr- + ological-data for the 2-year period of October 1, 1973 through September 30, 1975.- Regulator, Guide 1.109, Rev. 1-(October 1977), Methodology and Parameters, with the exception of the dilution factor of 8.85, when circulating water flow exists, were , used in Method 2 (the Backup Method) dose rate and. dose conversion factors. Tables 3.5-10, 3.5-12 and 3.5-13 are incorporated only for future use if there is a change _in the land use census which requires considering any combination of cow's milk and meat pathways. Section !4 identifies the' receptor locations which represent ' critical pathway locations, water dilution, atmospheric dispersion, and deposition factors used in calculation Method 2. Table 4-1 summarizes the above factors for the : gaseous ef fluent pathways. Section 5 indicatas locations at which environmental sampling may be conducted. Section 6 addresses the Interlaboratory Comparison Program._ h l 11.1-1 Revision 16 --July 1990 [ BN1-11600.02-92
..- _ _ . , _ m_-,
SNPS-1 ODCM i PART 11 SECTION 2 SET POINTS 2.1 LIQUID ETTLUENT NONITOR SET POINTS (Compliance with Section 3.11.1.1 of the Radiological Ef fluent Controls (REC, Part 1 of the ODCM). The radionuclide concentrations released via liquid affluents to mr stricted areas shall be limited to the concentrations specified ru 10CFR20 Ap er 3D B. Table II, Column 2 for radionuclides other than dissolved or entrained nM'e gaser. For disgolved or entrained noble gases, the total concentration shall be limited to 2 x
~
10 UC1/ml. l The set points of the effluent monitors are dependent on circulating or service water as follows:
- 1. a. With the circulating water system (a once-through system) in use, the circulating water flow rate (the circulating water system is composed of one pump and circulates sea water at a rate of 143,500 gpm). l
- b. The service water flow ratt with the service water system composed of two reactor building service water pumps, each having a capacity of 8600 gpm.
- 2. Flow rates of effluents from tanks and/or from the RER heat exchanger service water outlet, and/or yard piping drain-sump.
- 3. Individual concentrations of gamma emitters (other than dissolved or entrained e-ble gases) and Sr-89, Sr-90, Fe-55, and E-3; and the total concentratita of dissolved or entrained noble gases and gross concen-tration of the alpha emitters in the liquids to be discharged.
- 4. Maximum allowable concentration of 2 x 10' pCi/ml for the total concen-tration of dissolved or entrained noble gases and maximum permissible concentrations (MPCs) of other gamma emitters, Sr-89, Sr-90, Fe-55. H-3, and alpha emitters in the effluents as specified in 10CFR20 Appendix B.
Table II, Column 2 for an unrestricted area. NOTE: Precautions should be taken to assure that the circulating water system flow rate or the service water system flow rate used in determining the set point remains constant during the period of discharge. If the circulating or service water flow rate during discharge becomes less than the flow rate that was used in calculating the distharge set point, the discharge must be terminated and a new set point calculated. Service water via the RER heat exchanger service water outlet will be released continuously to the environment when the RHR heat exchanger is in operation. Reactor building salt water drain tank contents are released to the environment continuously. The discharge vaste sample tanks, recovery sample tanks, and yard piping drain sump contents will always be released to the environment as batch processes. BN1-11600.02-92 11.2.1-1 Revision 17 - May 1991
SNPS-1 ODCM For batch as well as continuous releases, the sampling and analysis program shall be in accordance - with the minimum requirements of REC Table 4.11.1.1.1-1.- Spec-ifically, the analysis program will include the de t ermim.t ion of gross alpha concentration of the alpha emitters. In addition, it will include isotopic anal-ysis for determination of individual concentrations of principal gamma emitters, and the specific radionuclides, St-89 St-90, Fe-55, and U-3. It will also include the determination of total concentration of the dissolved and entrained noble gases (gamma enitters) in the liquids. The concentrations of individual gamma emitters are determined by gamma spectral analysis of 1) the batch sample prior to its release for the batch releases and 2) the monthly grab sample for continuous releases. For gross alpha and the specific radionuclides Sr-89, Sr-90. Fe-55, and H-3, if analysis cannot be performed prior to discharge, then the following concen-trations are used in the monitor set point calculations: Cross Alpha and H-3 Gross alpha cencentration and H-3 concentrations as determined by analysis of the previous monthly composite sample for batch releases. For continuous releases gross alpha and H-3 concentrations are determined by analysis of previous monthly grab sample. Sr-89, Sr-90. Fe-55 Individual concentrations are determined by analysis of the previous quarterly composite sample for batch releases. For continuoun releases the individual concentrations are determined by analysis of the previous quarterly grab sample. Representative Samples Representative composite samples utilized in determining the concentrations of H-3, Sr-89, Sr-90, Fe-55, and the gross alpha concentration both for batch and contin-uous releases,and in determining the concentrations of gamma emitters (excluding dissolved and entrained noble gases) for continuous releases are obtained in accordance with the method stated for obtaining such samples in the REC Table 4.11.1.1.1-1. The tank contents are recirculated prior to obtaining samples for analysis. The minimum recirculation time t shall be r t r"b I t where: v a the volume of liquid in the tank to be sampled f = the recirculation flow rate being used to mix tl.e tank contents. r For the yar c' train sump, the above methodology will be used unless it can be
-determined ti.n there h.'s been no condensate storage tank overflow events since the last batch release. Althvugh designated a batch release, there may be times when non-contaminated yard drain runoff to ' the sump will occur during the discharge period. This input will not increase the discharge concentration.
BN1-11600.02-92 11.2.1-2 Revision 17 - May 1991 l
SNPS-1 ODCM The above methodology will ensure that a representative sample will be obtained for batch releases. Set Point Philosophy The philosophy of the set points will be based on the sum of the ratios of isotopic concentrations to MPCs being less than 1 for discharges into unrestricted areas. Specifically: N
= t C C 4 g i=1 C, C C Cg
, , C b + ..... + n + c-+
b a b C C
+ 3 , t .CFe <1 (2.1.1)
K K
~
where: kPCFe a b .......C Concentration of the individual gamma emitting C ,C = n radionuclides identified (pCi/ml)
, C = The gross alpha concentration (ECi/ml)
C G
= The total concentration of dissolved- or entrained noble gases (pCi/ml)
.C 3
=
The Sr-89 and Sr-90 concentrations (ECi/ml) C = The H-3 concentration (pCi/ml) t C a The Fe-55 concentration (pCi/ml) Fe MPC j = MPC,, MPC b ..... MPC , MPC n , MPC a , GMPC , 3MPC ,tMPCFe a the maximum permissible concentration of thE respective radio-isotope i (pCi/ml)-from 10CFR20, Appendix B. Table 11 Column 2. For dissolved or entrained noble gases, the maximum allowable concentration (MPC be 2.00E-04 (pC1/ml). 'ir gross alpha, the MPC assuk). ed willwill be 3.00E-08 (pCi/ml). If the C/MPC calculated is greater than 1, then no release is possible'. ,The normalization-factor (as definec' in Etion 2.1.1) must be greater than 1 to permit releases. To permit. releases, tios factor.can be increased to a value greater than 1 by increasing dilution flow F by running more circulating or service water - pumps in the applicable discharge s(tructure), and/or decreasing the effluent flow rates f , f, f f etc. (defined in Section 2.1.1),- and recalculate- C/MPC usingn[wC S in h ,ati$ ,2.1-1. 4 BN1-11600.02-92 11.2.1-3 Revision 8 - February 1986
SNPS-1 ODCM 2.1.1 Radiation Effluent Monitor (RE-13) High/ Trip Alarm Set point for Discharge Waste Sample Tanks, Recovery Sample Tanks, or YARD Piping Drain ' Sump The function of this monitor set point is to ensure that the sum of the ratios of the discharge concentrations to the MPCs of the corresponding radionuclides of the discharges. monitored by this monitor and other liquid waste discharges, if any, does not exceed 1. If the monitor count rate is higher than the calculated set point, the radiation monitor will tenninate the release. A-sample'is taken from any of the following tanks or sump which is to be discharged along with any streams which are in the process of being discharged.
- 1. Discharge weste tanks
- 2. Recovery sample tanks
- 3. Yard piping drain sump
- 4. Reactor building salt water drain tank
- 5. Residual heat removal heat exchanger service water
-Only one of the first three items above is discharged at any one time, which can be combined with releases from item 4 and/or 5.
Obtain the circulating or ser/ ice water flow rate from the control room (see NOTE inSection2.1). Define. Normalizing factor [fD*IHA + IHB + s + (Fc ~IHA ~ IHB)) ,
*0,8 N
I '(C f I I f HiA HA + C HiB HB + C 34 s) i=1 { Di D MPC j+ C g
-An_ isotopic analysis of each sample is performed. This analysis includes isotopic c.nalysis- for gamma - emitters; gross alpha emitters; total dissolved . or entrained noble gases; and Sr-89, Sr-90, Fe-55, and H-3. This should be done for all moni- -
tors. Then the set point-(NOTE: the. background (cpm), if it can be determined, is also added to the set point value. If, however, it cannot be determined, 'it is con-sidered as zero) for detector RE-13 is calculated as:. N
-(cpm)
S 13 5 F*IC Di *E g
- i=1 l
l BN1-11600.02-92 11.2.1-4 Revision 8 - February 1986 1
- _~.._. _ __ ,__ _ _ . _ . , . - - . _ _ _ - _ - . - , _ _ _ , , . .
SNPS-1 ODCM where: C 01
= concentration of radioisotope (i) (pCi/ml) in any of the following tanks or sump that is to be discharged:
- 1. discharge waste tanks
- 2. recovery sample tanks
- 3. yard piping drain sump f
D
= Discharge flow rate (gpm) from any of the following tanks or sump that is to be discharged:
- 1. discharge waste tanks
- 2. recovery sample tanks
- 3. yard piping drain sump.
(Maximum design discharge flow rate = 150 gpm) C 34
= Reactor building salt water drain tank concentration of radioisotope (i)
(UCi/ml) chi A = RHR heat exchanger service water outlet concentration of radioisotope (i) (UCi/ml) from loop A. CHiB = RHR heat exchanger service water outlet concentration of radioisotope (i) (pCi/ml) from loop B. f 3
= Reactor building salt water drain tank discharge flow rate (gpm).
(Maximum design discharge flow rate = 100 gpm) f HA
= RHR heat exchanger service water outlet discharge flow rate (gpm) from loop A (Maximum design discharge flow rate = 9340 gpm) f HB
= RHR heat exchanger service water outlet discharge flow rate (gpm) from loop B (Maximum design discharge flow rate 9340 gpm)
F C
= Total circulating or service water flow rate (gpm) (this includes fHA and fHB)
E = Gamma counting efficiency of RE-13 for radionuclide (i) (cpm /pCi/ml). Figure 2.1-1 shows the ener3y response. For non-gamma emitters, E =0. 4 0.8 = Safety factor MPC is defined in Section 2.1. The above calculation is made for each batch to be 4 released. After each bt.tch release, the high alarm set point shonid be reset as close to tha bar.kgrour.d cs practical to prevent spurious alarms and yet assure an alarm should an ir. advertent release occur. Bhl-11600-02-92 11.2.1-5 Revision 8 - February 1986
.. . - - . - - . . . _ . . - - - . . ~ . - - - . - . _ . . - - . - .- .--
SNPS-1 ODCM 2.1.2 Radiation Effluent Monitor (RE-79) High Alarm Set Point for Reactor Building Salt Water Drain Tank The function of this monitor set point is to ensure that the sum of the ratios of the discharge concentrations to the MPCs of the corresponding radionuclides of the discharges monitored by this monitor and other liquid waste discharges, if any, does not exceed 1. If the monitor count rate is higher than the- calculated set point, the radiation monitor will alarm in the control room. A sample' will- be taken from the reactor building salt water drain tank discharge, along with individual samples of any of the following streams which may be in the process of being discharged:
- 1. . Discharge waste sample tanks
- 2. Recovery sample tanks
- 3. Yard piping drain sump
- 4. Residual heat removal heat exchanger service water In the case of continuous release, samples will be taken as per requirement REC Table 4.11.1.1.1-1.-
Obtain _the circulating or service water flow rate from the control room (see N01E in Section 2.1). The set point for continuous or batch release (see NOTE in Section 2.1.1) will be calculated as follows:- 5 CE S 79 2f* lj.1 3$ g] (cpm) where: E = Gamma counting efficiency of RE-79 for radionuclide i 4 (cpm /pCi/ml). Figure 2.1-2 shows the energy response._ For non-gamma-emitters. Ej=0 All other parameters are as defined in_Section 2.1.1, When the tank operates in a batch mode, the above calculation is made for each batch to be released. After each batch release or continuous release period, the high alarm set point should be reset as close to the backgrourc' . practical to prevent spurious alarms and yet assure an alarm should an inadvertent release occur. BN1-1 500-02-92~ 11.2.1-6 Revision 1C - July 1990
SNPS-1 ODCM 2.1.' Residual Heat Removal Heat Exchanger Service Water Outlet Monitors (RE-23A, RE-23B) High Alarm Set Points The function of this monitor set point is to ensure that the sum of the ratios of the discharge concentrations to the MPCs of the corresponding radionuclides of the discharges monitored by this monitor and other liquid waste discharges 'if any, does not exceed 1. If the monitor count rate is higher than the calculated set point, the radiation monitor will alarm in the control room, Monitors _ RE-23A and RE-23B are independent. Each is dedicated to monitor its respective RHR loop. A sample will be taken from the RH9 heat exchanger service water outlet ( A and/or B). along with individual reples of any of the following streams which may be in .- the process of being discharged:
- 1. Discharge waste samp~e tanks
- 2. Recovery sample tankt
- 3. Yard piping drain sump 4 Reactor building salt water drain tank discharge Obtain the circulating or service water flow rate from the control room (see NOTE in Secticn 2.1).
The set points for RE-23A and RE-23B are calculated as follows: N S23A
- I
- Ei1 b Cg$gEiA3 N
S238jF*[${3 C HiB EiB3 where: E iA
= Gamma counting efficiency of RE-23A for radionuclide i (cpm /pCi/ml).
Figure 2.1-2 shows the gama energy response. For non-gamma _ emit- l ters, Eg g- = 0 E iB
= Gamma counting efficiency of RE-238 for radionuclide i (cpm /pCi/ml).
Figure 2.1-2 shows the gamma energy response. For non-gamma emit- l ters, EiB = 0 All other parameters are as defined in Section 2.1. BN1-11600.02-92 11.2.1-7 Revision 13 - November 1988
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SNPS-1 ODCM 2.2 CASE 0VS EFFLUENT HONITOP SET POINTS (Compliance with Section 3.11.2.1 of the REC) The high alarm set point for the Station Ventilation Exhaust Monitor (RE-42) is set in accordance with the dose rate 1,'mit for noble gases at the site boundary spec. ified in Section 3.11.2.1 of the REC, Less than or equal to 500 mrem /yr to the total body and less than or equal to 3000 mrem /yr to the skin. The set point for this monitor will be determined based on the lower of the two set points calculated for 1) the total kody dose rate and 2) the skin dose rate, calculated respectively in Sectic s 2.2.1 and 2.2.2. i BN1-11600.02-92 11.2.2-1 Revision 17 - May 1991
SNPS-1~0DCM The methodology of multiplying the observed _ cpm by the calculated scale factor.will be used to_obtain'the set point in the. range where the detector response is linear -1 with changes in nuclide concentration. In the non-linear-' region, appropriato i correction as derived'from Figures 2.2-2 will- be made. ) 2.7.1 Gaseous Effluent Monitor High Alarm ' Set' Point for Station Ventilation I Exhaust Monitor (RE-42) ! 2'. 2.1.1 Gaseous Effluent Monitor High Alarm Set Point for Station Ventilation Exhaust Monitor (RE-42) Based on Noble Gases-Total Body Dose Rate
- 1. The net count rate (excluding background), CR (cpm), of the Station Ventilation Exhaust Noble Gas Radiation Monitor is given-by:
CR = 10'6
- C(Kr-85)*E(Kr-85) (cpm) where:
E(Kr-85) = detector efficiency-(cpm / Ci/cc) for RE-42 for Kr-85 as provided in Figure 2.2-1. The linearity response for RE-42 is shown in Figure 2.2-2.-
- 2. The noble gas total body dose rate is calculated using the following equation:
DR(Kr-85) = A/Q
- V
- OFB (Kr-85)
- C (Kr-85) (mrem /yr) where:
DR(Kr-85)-= predicted dose rate for (Kr-85) (mrem /yr), X/Q = annual average - X/Q (sec/m8) ht 366 meters NNE due to releases via the station ventilation exhaust. point (6.6E-07.sec/m3), DFB(Kr-85)= total body dose rate conversion factor-(mrem /yr/pCi/m3),from_ Table 2.2-1, C(Kr-85) = isotopereleaseconcentration(pCi/cc)"samplingnot required",
-V = station' ventilation exhaust rate (cc/sec).. (Maximum exhaust rate = 1.73E+08 cc/sec (3.66E+05 cfm).)
- BN1-11600'02-92_ . 11.2.2-2 Revision 17 - May 1991
,,,..e.,--r , , . .n - ,,e4w-- .w. e., .m m w- m = r-,. w.w.-- ,__m--..--,--,.,e.-.mw. e x wr w, = , , w- .r e
SNPS-1 ODCM
- 3. The isotopic release activity concentration is nonnalized to a total body dose rate of 500 mrem /yr by multiplying by the folinwing normalizing factor:
=
Fg 500/ DR (Kr-85)
- 4. From the above, the set point (see NOTE in Section 2.1.1) based en total l body dose rate can be calculated as follows:
B (cpm) 3 42 0.8
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B S 2
= high alarm set point that results in a total body dose rate of less than 500 mrem /yr.
F B
= n rmalization factor (unitiess)
CR = station ventilation exhaust noble gas radiation monitor count rate (cpm), and 0.8 = safety factor. 2.2.1.2 Gaseous Effluent Monitor High Alarm Set Point for Station Ventilation Exhaust Monitor (RE-42) Based on Noble Gases Skin Dose Rate
- 1. The net count rate (excluding background), CR (cpm), of the station ventilation exhaust noble gas radiation monitor is given us noted in Section 2.2.1.
- 2. The. noble gases beta and gama skin dose rate is given the following equation:
DR(Kr-85) = Xf,Q*V* K(Kr-85)* C(Kr-85) (mrem /yr) sim where: DR(Kr-85) = predicted dose rate for Kr-85 (mrem /yr), BN1-11600.02-92 11.2.2-3 Revision 17 - May 1991
SNPS-1 ODCM X/Q = annual average X/Q (sec/m8) at 366 meters NNE due to releases via the station ventilation exhaust point, (6.6E-07 sec/m8), K(Kr-85) = skin dose rate conversion factor (mrem /yr/pCi/m3), frc,a sim Table 2.2-1 C(Kr-85) = isotopereleaseconcentration(pCi/cc)samplingnot required, V = station ventilation exhaust rate (cc/sec). (Maximum exhaust rate = 1.73E+08 cc/sec (3.66E405 cfm).)
- 3. The isotopic release activity concentration is normalized to a skin dose l rate of 3000 mrem /yr by multiplying by the following normalizing factor:
F3=3000/DR(Kr-85)
- 4. From the above, the alarm set point (see NOTE in Section 2.1.1), based on l skin dose rats, con be calculated as follows:
S
- CR = 0.8
- 3000
- E(Kr-85) (cpm)
S 2 j 0.8
- F3 X/Q
- V
- Ksim (Kr-85) where:
S S 2
= high alarm set point that results in a skin dose rate of less than 3000 mrem /yr (cpm),
F = normalization factor (unitiess), 3 CR = station ventilation exhaust noble gas radiation monitor countrate(cpm),and 0.8 = safety factor. BN1-11600.02-92 11.2.2-4 Revision 17 - May 1991
SNPS-1 ODLM TABLE 2.2-1 DOSE FACTORS.FOR EXPOSURE TO A SEMI-INFINITE CLOU0 0F NOBLE GASES' Ksi.I4I K (5) sim d-uci de B-Air (1) (DFbg ) B-Skin (2)-(DFS9 ) Y-Air (I) (DF ) Y-Body (2) (DFBg ) ' Skin Dose (2}' Skin Dose ( } 1.93E-05 7.56E- 08 1.5E-05 2.1E-05 Kr-83m 2.88E-04(3) --- 1.46E-03 1.23E-03 ' 17E- 03 2.4E-03 2.8E Kr-85m 1.97E-03 .. 1.34E-03 1.72E-05 1.61E- 05 1.4E-03 1.4E-03 Kr-85 1.95E-03 9.73E-03 6.17E-03 5.92E- 03 1.5E-02 1.7E-02 Kr-87 1.03E-02 2.37E-03 1.52E-02, 1.47E- 02. 1.4E-02 1.9E-02 Kr-88 2.93E-03 1.01E-02 1.73E-02 1.66E- 02 2.4E-02 2.9E-02 Kr-89 1.06E-02 7.29E-03 1.63E-02 1.56E- 02 2.0E-02 2.5E-02 Kr-90 7.83E-03
-4.76E-04 1.56E-04 9.15E- 05 6.0E-04 6.5E-04 Xe-131m 1.11E-03 9.94E-04 3.27E-04' 2.51E- 04 1.2E-03 1.4E-03 Xe-133m 1.48E-03 3.06E-04 3.53E-04 2.94E- 04 5.8E-04 7.0E-04 Xe-133 1.05E-03 7.11E-04, 3.36E-03 3.12E- 03 3.3E-03 4.4E-03 Xe-135m 7.39E-04 1.86E-03, 1.92E-03 1.81E- 03 3.4E-03 4.0E-03 Xe-135 2.46E-03 1.22E-02 1.51E-03 1.42E- 03 1.3E-02 1.4E-02 Xe-137 1.27E-02 1 of 2 Revision 10 - August 1987 BN1-11600.02-93
. . = _ _ . .. ..
SNP3-1 ODCM. TABLE 2.2-1 (CONT'D) KsiI4) K (5)
- sim 1 de S-AirIII'(DFbj ) 'B-SkinI2) (DFS$ ). Y-AirII) (DF ) Y-Body (2)'(DFB )
9 Skin Dose (2) Skin Dose (2)' ; Xe-138 4.75E-03 4.13E-03 9.21E-03 8.83E- 03 1.1E-02 1.4E-02 Ar-41 3.28E-03 2.69E-03 9.30E-03 8.84E- 03 9.9E-03 1.3E-02 (1) mrad-m3 - j pC1-yr (2) mrem-m3 - pCi-yr j (3) 2.8SE-04 = 2.88
- 10-4 (4) K si = (0.7
- 1.11
- DFT) + DFS g (5) K 39,=(1.11*DF})+DFS g
[ t BW1-11600.02-93 2 of 2 Revision 10 - August 1987 i 4
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.. . _. . _ _ . _ . . _~ --__-______.._.__..._.._.-m . _ . . . _ . _ , SNPS-1 ODCM PART II SECTION 3 DOSE CALCULATION METHODS This section presents _ the calculational specifics required to demonstrate compli . ance with the following Radiological Effluent Controls (REC, Part I of the ODCMi sections: 3.11.1.2 - Liquid Effluent Dose Calculation 3.11.1.3 - Operation of 1.iquid Radwaste Treatment System 3.11.2.1 - Gaseous Effluent Dose Rate 3.11.2.2 - Noble Gas Air Dose 3.11.2.3 - Gaseous Effluent Dose From Radiofodines, Tritium, and Radionuclides In Particulate Form Calculation methods are based on the equation and calculational methods described in Regulatory Guide 1.109, " Calculation of Annual Doses to Man f rom Routine Re-leases of Reactor Effluents for the Purpose of Evaluating Compliance with 10CFR50 Appendix 1." Two methods are provided for each analysis. The first method is the method used by the computerized radiation monitoring system. Method 2 is a backup hand calcula-tional method to be used only if the computer is not functional. The Semi-Annual Effluent Release Report is produced and the land use census is evaluated using NRC codes which implement Regulatory Guide 1.109. BN1-ll600.02-92 11.3.0-1 Revision May 1991
SNPS-1 ODCM 3.1 LIQUID EFFLUENT, DOSE CALCULATION To comply with Section 3.11.1.2 of the REC, the liquid effluents released to unrestricted areas shall be limited:
- 1. During any calendar quarter to less than or equal to 1.5 mrem to the total body aid to less than or equal to 5 mrem to any organ.
- 2. During any calendar year to less than or equal to 3 mrem to the total body and to less than or equal to 10 mrem to any organ.
The site boundary for liquid effluents is shown in Part I Figure 5.1-3. The liquid radwaste system model is shown in Figure 3.1-1. 3.1.1 Method 1: (Computerized Method) The equations which follow are used by the computer software to calculate the offsite doses due to release of liquid radwaste. For this dose calculation the actual concentration to be discharged by isotope, the total volume of liquid to be discharged, and the number of circulating water puiaps running, supplied by the operator, shall be used. The software computes the isotopic releases by multiplying the lab measurements by the volume of the liquid to be released: Q = 3.785 x 10-3 yq j 4 where: Og = total inventory of isotope i in the liquid to be released (C1) qg
= concentration of isoto e i in the liquid to be discharged (as measured in laboratory) p(WCi/cc)
-V = volume of liquid to be discharged (gallons) 3.785 x 10-3 = [(Ci/pCi) (cc/ gal)]
The dose equations which follow are from Regulatory Guide 1.109, with minor modif-ications. They are employed for the computation of dose from any single batch
~
discharge (continuous discharges are handled as batch discharges in the com-puterized method). Weekly and quarterly cumulative doses are also calculated and stored in data files for reporting. (a) Organ Dose Due to Ingestion of Salt Water Fish R g fish = 0.389 U 5(1/K) y IQB4 S p DFI e -24 A i for circ. water part+1 ija R 9 fish = 57.4/(K2 + 0.930 K3 ) U, I Q 4 DFl ija* I part+1 for service water C L 11600.02-92 11.3.1-1 Revision 17 - May 1991
SNPS-1 ODCM where: ing fish R ja = dose to organ j of individual in age group a due to ingestion of fish contaminated with particulates and radiciodines ', mrem) (Ref. Reg. Guide 1.109, with the following special values: l
- F (flow rate of liquid effluent) is represented by productis the nu 3
K *F ft /sec], where KTstheflowrateperunit s9 stem P M*803r[ating and F pump. Forthecirculati8d*NATersystem,m=1;forthereactor building service water system, m=2; for the turbine building m=3 servicewatersystgm
= gpm] = 319.7 [ft $/sec)
'F = 19.16 Fft3/sec'
- fpump,1 8,000 =[gpm1.435x10'
=17.82[ft/sec'J 3
Fpump,2 0.113 == 8,600 [gpm (1/8.85) I MP i81$ing ratio at the point of exposure) = ifcirculatingwaterisinuse;
= 1.0 if service water is in use. (see below)
D dose factor) = DFl tahr(ansit time required $r nuclides to reach the Soint ofof the R eRposure) = 24 [or) (see pg 1.109-12 group a [kg/yr]
= fish consumption rate by individual in age U"5 (from Table E-5 of the Guide, for maximum individual) a number of pumps of system m operating K
m
= total activity of isotope i released [Ci], from fish saltwater above[(pCi/kg)/
Q. I = Bioaccumulation factor for (pCi/ liter)) (from Table A-1 of the Guide)
=
dose conversion f actor for nuclide i to organ j of individuil DFIQa . in age group a due to ingestion [ mrem /pCi ingested] (from Tables E-11 through E-14 of the Guide)
= radionuclide decay constant [hr'I] (from Table 3.1-1)
A
= 1100 x 0.113 / 319.7 [(pCi/L)/(Ci/yr)] for 0,389 -
1100 Mp/Fpump.1 care water
= 1100/19.16 [(pCi/1)/(Ci/yr)] for reactor
=
57.4 1100/FPU*P'2 building service water pump,3/Fpump,2
= F 0.930
= 68 particulates and 5 iodines in the sumation sign part+1 (b)
Organ Oose Due to Ingestion of Salt Water Invertebrate e i for circ. water 9 I"V =0.389Uf"p(1/K))I V QBf"p*DFl 4 ija R E Oi DFl ija" 9 I"" R = 57.4/(K2 + 0.930 K ) p part+1 3 for service water Revision 8 - February 1986 11.3.1-2 BN1-11600.02-92 ~~ --~
- . _ . . _ . _ _ - . . . . _ - . . - . - . . ~-- . - . . - - . -
SNPS-1 ODCM where: R 9 I"Y = dose to organ j of individual in age group a due to the ' ingestion of saltwater invertebrate contaminated with radioactive particulates and -iodines [ mrem] (Ref.: Reg. Guide 1.109 Eq. A-3 with the special values identified in the fish-ingestion equation above) IV = Bioaccumulation factor for saltwater invertebrate BI "P [(pCi/kg)/(pCi/ liter)](fromTableA-1oftheGuide) V Uf"p = invertebrate consumption rate by individual in age group a [kg/yr] (from Table- E-5 of the Guide, for maximum individual) (c) Total Body Dose From Shoreline Deposits
-R ' = 0.561 Ushore(1/K) E Q$ DFG 4 ) [1-e-tb i) for circ. water part+1 4
-t re
=82.9/(K2+0.930K)Ufp 3 r Q4 0FG4 ) (1-eA b i) service water part+1 where:
R ore = total body dose to individual in age group a from shoreline de-
,a posits [ mrem](Ref.: Reg. Guide 1.109 Eq. A-7 with the follow-ing special values:
' F(flow rate of liquid effluent) is represented by the product F operatin(*puM%
g Poi s [ystemmandFft3/sec], is the where K isper flow rate the numb pump m unit pump For the circulating water system, m=1; for the reactor build-ing service water system, m=2; for the turbine building service water system m=3 F 1.435 x 105[gpm]=319.7[ft3/sec]
- Fpump,1 = 8,600 'gpm] = 19.16 'ft3/sec]
Fpump 2== 8,000 lgpm]=17.82lft3/sec]
*MPUT812ing ratio) = 0.113 if. circ. water is in use P
= 1.0 if service water is in use W (shore-width factor that describes the geometry of the exposure) = 0.5 for ocean site (from Table A-2 of the guide) t (transit time from source to shoreline) = 0 (see Reg.
G81depg1.109-69, forEq.A-7) Tj (radionuclide half life,-days) = 0.693/(24A ) wh 4 0.693 = loge 2 and y is the decay constant-in [hr'9]re Daipj y DFGj ) (see below)
= shoreline exposure time for individual in age group a [hr/yr]
(from Table E-5 of the Guide, for maximum individual) BN1-11600-92 11.3.1-3 Revision 8 - February 1986
SNPS-1 ODCM , _ number of pumps of-system m operating
=
K, 0 4
= -
total activity of isotope i released [Ci], from above DFG 4j = total body conversion factor for standing on contaminated ground (shore) [(mrem /hr)/(pCi/m e )] (from Table E-6 of the guide)
=
t b timeperiogoverwhichaccumulationisevaluated(15 years,or 1.314 x 10 hours) 0.561 = 110,000 pM W-(T j4 A )/ Fpump,1 [(p i/ )/( 1/yr)]
= 110,000 x 0.113 x 0.5 x (0.693/24)/ 319.7 for circ. water 82.9 =
110,000W (Tj Aj) Fpump2[(pCi/t)/(Ci/yr)]
= 110,000 x 0.5 x (0.693/24)/19.16 for reactor building service water
=
0.930 F pump,3/Fpump 2 4 part+1 = 68 particulates and 5 iodines in tha summation sign (d) Skin Dose From Shoreline Deposits shore = R 0.561 Ushore (1/K ) I p part+I Q4 DFGi2 (1-e A j b i) for circ. water A
=
E 82.9/(K2 + 0.930 K3 ) p i part+1 O DFG12 (1-e A b i) 4 for service water where: d
* = skin dose to individual in age group a from shoreline deposits n,a
[ mrem]; (Ref.: Reg. Guide 1.109 Eq. A-7 with the special values listed for the total body dose)_. DFG i2
= skin dose conversion factor for standing on contaminated ground (shore)-[(mrem /hr)/(pCi/m?)]_(from Table E-6 of the Gt.ide)
Other parameters are as defined earlier for the total body dose from shoreline deposits. (e) Total Doses The individual dose-components described in items (a), (b), (c), and (d) above are summed in the following way for the computation of total doses:
=_ o ing fish , fing inv R
ja ja Ja _p , shore wb a Ob.aingfish,bb,ainginv,Ob,a
, sshere ps kin,a -Ekin,a BN1-11600 II.3.1-4 Revision 8 - February 1986
SNPS-1 0DCM where: .f R. = total dose to organ j (exclusive of the total body) of individ-Ja ual in age. group a due to the ingestion of fish and invert-ebrate (mrem) R g ',
= total dose to the total body of individual in age group a due to the ingestion of fish and invertebrates, and direct radiation from shoreline deposits and R = total dose to the skin of an individual in age group a from skin a shoreline deposits (mrem).
3.1.2 Method 2: (Backup Method) The dose contributions for the total release period shall be calculated for all radionuclides identified in liquid effluents released to unrestricted areas using the-following expression: M-g D7 = ),3 [A47 d 3Atg C gFg] $ (3.1-1) where: D7
= the cumulative dose or dose commitment to the total body or an organ from the liquid effluents for the total release period
$ At (mrem).
_g,3 g
^
At g
- the length of the tth release period over which C $g and F g are averaged for all liquid released (minutes), '
C it
= the average concentration of radionuclide C i in undiluted. liquid effluent during release period Att from any liquid release.(pCi/cc).
A".
=: the site-related ingestion dose or dose commitment factor to the total body or any organ for each identified principal gama and beta emitter listed in Table 3.1-2 (mrem / min per pCi/cc), see Appendix A-for_ derivation Fg = Undiluted liquid effluent flow rate Fc-I"p F
c
= total circulating water flow rate with the number of circulating pumps in:use
= total service water flow rate if the circulating water is not in use M P-(Mixing factor) = 0.113 if circulating water is in use;
= 1.0-if service water only is in use BN1-11600-92 11.3.1-5 Revision 8 - February 1986
' g,,-. _m g, ,,9 ,, , --,,,m ,,..
+'-'+e -- ,i--aw-. 3 y7 9._,.,- 9
SNPS-1 ODCM The total dose from-liquid effluents from all discharges. DTotal' IS CD 7g UTotal
- UtD+DTR tD33 + D7p
.where:
D = Dose contribution from discharge waste sample tanks as calculated in TD Equation 3.1-1 D TR
= Dose contribution from recovery sample tanks as calculated in Equation 3.1-1 D 7g = Dose contribution from RHR heat exchanger, service water as calculated in Equation 3.1-1 D = Dose contribution from reactor building salt water drain tank as 73 calculated in Equation 3.1-1 0 = Dose contribution from. yard piping drain sump as calculated in 7P Equation 3.1-1.
If the calculated total dose exceeds the limit specified in Section 3.1, consult REC Section 3.11.1.2 BN1-11600.02-92 11.3.1-6 Revision 16 - July 1990
SNPS-1 ODCM ; TABLE.3.1-1 OECAYCONSTANTS(1/hr)- Radio-- Radio-nuclide Constant nuclide Constant H-3 6.408E-06 Ru-103 7.300E-04 C-14 1.379E Ru-105 1.600E-01 Na-24 4.600E-02 Ru-106 7.800E-05 ' P-32 2.000E-03 Ag-110m_ 1.100E-04 Cr-51 1.044E-03 Te-125m 5.000E-04 Mn-54 -9.252E-05 Te-127m 2.600E-04 Mn-56 2.700E Te-127- 7.400E-02 Fe-55 2.930E-05 Te-129m- 8.600E-04 Fe-59. 6.480E-04 Te-129 5.900E-01 Co-58 4.068E-04 Te-131m 2.300E-02
-Co-60 1.501E-05 Te-131 1.700E+00 Ni-63 8.600E Te-132 8.900E-03 Ni-65 2.700E-01 1-130 5.600E-02 Cu-64 5.400E-02 1-131 3.593E-03 Zn-65 1.184E-04 I-132 3.000E-01 s
.Zn-69 7.296E-01 1-133 3.334E-02 Br-83 2.900E-01 1-134 7.900E-01 Br-84 .1.300E+00 I-135 1.100E-01 Br-85 1.449E+01 Cs-134 3.852E-05 Rb-86 1.500E-03 Cs-136 2.203E Rb-88 2.400E+00 Cs-137 2.635E-06 Rb-89 2.700E+00 Cs-138 1.300E+00 Sr-89 '5.724E-04 Ba-139 5.000E-01 Sr-90 2.776E-06 Ba-140 2.257E-03 Sr-91 7.300E-02 Ba-141 2.300E+00 Sr-92 2.600E Ba-142 3.900E+00 Y-90 1.100E-02 La-140 1.700E-02 LY-91m 8.300E-01 La-142 4.500E-01 o .Y-91 4.900E Ce-141 .8.892E-04
-Y-92 2.00E-01' Ce-143 2.100E Y 6.800E-02 Ce-144 1.019E-04 Zr-95 4.392E-04 Pr-143 2.100E-03 Zr-97 -4.100E-02 Pr-144 2.400E+00-Nb-95 8.200E-04 Nd-147 2.600E-03
.Mo-99_ 1.000E-02 W-187 2.900E-02 Tc-99m' 1.200E-01 Np-239- 1.200E-02 Tc-101- 2.900E+00 l
l BN1-11600-112 1 of 1 Revision 3 - December 1983 b _ _ ______ _ ._ ___ _ _ _ __ _ - - _ _. _ _ _ , - ._- .
. u.,
i SNPS-1 ODCM TABLE 3.1-2 ADULT DOSE _ RATE' CONVERSION FACTORSIII, A 37
- FOR (FISH AND INVERTEBRATE) INGESTION PATHWAY (mrem / min per Ci/cc)
Liver T. Body ~ Thyroid Kidney Lung GI-LLI Nuclide Bone H-3 -iib , 4.6E-03 4.6E-03 4.6E-03 4.6E-03 4.7E+01 4.6E-03 4.7E+01 4.6E-03 4.7E+01~ C-14 2.4E+02 4.7E+01- 4.7E401 4.7E+01 1.4E-06 - - 3.7E-07 F-18 1.2E-05 - 2.5E-03 2.5E-03 '2.5E-03 2.5E-03 2.5E-03 2.5E-03 2.5E-03 NA-24 - 3.0E+04 P-32' 2.6E+05 1.6E+04 1.0E+04 - - 9.0E-02 5.3E-02 2.0E-02 1.2E-01 2.2E+01 CR-51 - , - 3.5E+02 MN-54 - 1.2E+02 2.2E+01 - 3.4E+01 - 4.6E-03 8.1E-04 - 5.9E-03 - 1.4E-01 MN-56 - 3.3E402. 8.3E+02 5.8E+02 1.4E+02 - - 3.2E+02 FE-55 1.0E+04 1.3E+03 3.1E+03 1.2E+03 - - 8.6E+02 FE-59 2.0E+02 CO-58 - 9.8E+00 2.2E401 - - - 2.8E+01 6.3E+01 - - - 5.4E+02 C0-60 -
- 1.2E+01 NI-63 8.1E+02 5.6E+01 2.7E+01 - -
6.2E-04 2.9E-04 - - 1.6E-02 NI-65 4.8E-03 - 8.2E+01 CU-64 -- -9.6E-01 4.5E - 2.4E+00 - 8.4E+03 3.8E+03 - 5.6E+03 - 5.3E+03 ZN-65 2.7E+03- 4.9E-01 ZN-69M 1.7E+00 '3.3E+00 2.2E-01 - 2.1E+00 - 1.1E-06 - - - 1.6E-06 BR-83 - - BR-84 - - 2.7E-17 - - - 4.6E+00 - - 1.9E+00 RB-86 - 9.8E+00 - 2.3E+00 - - - 1.3E+01 SR-89 8.1E+01 - 5.8E+01 SR-90 2.0E+03 -- 5.0E+02 - - - 1.0E-02 - - 1.2E+00 SR-91 2.6E-01 - 2.4E-02 SR-92 1.2E-03 - 5.3E-05 - - - 2.1E-03. - - 8.2E+02 Y-90 7.6E-02 - 5.4E-12 Y-91M 1.9E-12 - 7.2E-14 - - - 3.9E-02 - - - 8.0E+02 Y-91 ~1.4E+00 - 2.3E-06 - - 1.4E+00 Y-92 7.9E-05 - 1.8E+02 Y-93 5.4E-03 - 1.5E-04 - - - 8.3E-02 .5.6E-02 1.3E-01 - 2.6E+02 ZR-95 2.6E-01 - BN1-11600-116 1 of 3 Revision 3 - December 1983
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0000 s++-e OOOOOOOONOOOOOOOOOOMMOOOOOOO
+ i ++ t + e e e+ e+ a e a i + + + 4 I e # e t + + a W WWWW WWWWWWWWWWWWWWWWWWWWWWWWWWWW
> MOCM w e e e e v em eMe M e m e@ O. v. v. 5.. . C. N. M.
. - e We 4e M e N v CeO.-W N W< N N ve NeW e e e W MvwM i l l N MM WM@mMWWMGM NTNNOMMMMvMM MO WOMMMOOONWMOmOMOvMONNMNWNMNONMON CO e+. COOOOOOOOOOOMOOOOOMOOOOMOOOOOOOO e+ t + ++++ 4 + B + 1 + e+ e i I e+++ t + a a e I + 4 0 WW WWWWWWWWWWWWWWWWWWWWWWWWWWWWWWWW C
o - v N. MNT@@mmmmmhMMNNMNmMMMMmCMcNN.mOmM e e e e o e e e e e e e e e e e e e e e e e e e e e e e e m WN IMMMNNvMmNMNMMNMMMmmMMMMMQNWNm@Nm . M M O O 0 E EE E E @ T EMm@OvmNNmmMMN - v@NmmOONMMMM M NmmmOOOMNNNNNNMMMOWNMvmMMMMMvvvvvv4 M
~
O mmmmMMMMMMMMMMMMMMMMMMMMMMMMMMMMMMM I 8 4 4 8 I t i I I l l I I l i e IMMMMMM I I I I I e i I 4 I i i M 3 MMCODDDOmWWWWWWWW I 4 i l I S DDDDvvvvWWWZ Z Z NZEWM&%vD&&&&&&&&MMMMMMUUUUmmWJUUUk m
E ' . l , SNPS-1.0DCM TABLE 3.1-2 (CONT *D) T. Body Thyroid Kidney Lung GI-LLI Nuclide Bone Liver 7.1E-02 4.2E-03 4.1E-02 - 3.4E+02 ND-147 6.1E-02 - 2.IE+01 W-187 7.5E-02 6.3E-02 2.2E-02 - - - 4.2E-05 2.3E-05 1.3E-04 - 8.7E+00 NP-239 .4.3E-04 - II The dash (-) indicates insuf ficient data or that the dose factor is <1.0E-20. 3 of 3 Revision 3 - December 1983 BN1-11600-116
' -10D01 DELE 4-1 (Omt'd.) E D i A A la g Term Relative 9 N/A N/A 5.16FA 6 m
-2 c) 5.16"4 m-2 c)
-2 c)
Depmiticn Factor for 10 5.1GO3 m Statfrn Verw itatim Exhaust D/Qg 4 4 4
- 0) Iag Islard 14i tirs Cmpmy, Surehan Nuclear Statim - Ihit Or,
- FIML D.YDOrnTAL SUIDET, NCFH; C285, October 1977, Dmket 30-322. ( *tmpliance With 10CH00 Ammlix I," Shorehm Neler lher Station -Ikit One, i lag Islaruf Li@ ting Canpary, Docket 50-322, SN;0-119, July 30,1976. 4 l 0) Based m Stone & Wbster r*1m1=rian 19.6A4-120. Rev. O, arul NED minitarim CX1f039215 Eer. O. 1 t i i i 4 4 i Re718I32 II - ? LIT 199I . IN1-11600.02-109 2 of 2 i 1
SNI)S 1 ODCH TABLE 4-2 GENERAL $1TE SPECIFIC DATA PARAMETER gg Elevation of lower level met, instruments 33 ft above ground level Elevation of upper-level met. instruments 150 ft above ground level Temperature sensor separation 117 feet i Release height for station vent 249 ft above MSL j Station grade elevation 20 ft above MSL i Reactor building height 65 m , Reactor building cross sectional area 2600 mr l Station vent equivalent diameter 2.664 m , Maximum effective plume height allowed 400 m f Height of inversion layer alof t 600 m Maximum plume vertical standard deviation o , = 1000 m Fraction of_ the year that animals grare on pasture f = 1.0 p Fraction of daily feed that is pasture grass when f 5= 0.84 the animal grazes on pasture Average transport time of activity from the feed tf = 24 hours ; into the milk ind to the receptor t i 4 i i BN1-11600-112 1 of 1 Revision 18 - May 1991 l' I
.,--.:-..-.......... .:.... - - - . . . - - - - , - .-. . - . , .--- .-,,, _ ,-..,..,.,:~ , - ,-
L SNPS-1 ODCM PART 11 SECTION 5 RADIOLOGICAL ENVIRONMENTAL MONITOR!NG PROGRAM SAMPLING LOCATIONS The purpose of this section is to identify those sampling locations from which the radiological enviror- W al monitoring samples shall be collected pursuant to Radiological Effluer Re rols 3/4-12 (Part 1 of the ODCM). Table 3.12.1-1, ir . 1.3-37), beSed on NUREG 0473, defines an acceptable Radiological Envirotenental Monitoring Program by providing guidelines for the sampling locations according to pathways. It specifies the number, location and frequency of sample collection and the required analyses. The Shoreham-specific implementation of the pr& gram is given in Tables 5-1, 5-2, S 3 and 5-4, corresponding to the four pathways of direct, airborne, waterborne and ingestion doses. The corresponding onsite and offsite sampling locations are shown in Figures 5-1 and 5-2, respectively. L i l l
\
BN1-11600.02 11,5-1 Revision 17 - May 1991
SNPS-1 ODCM TABLE S-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM (REMP) DIRECT RADIATION MONITORING STATIONS Functional Designation Location Code (NUR.:G-0473) _(Shoreham REMP) location Description DR1 151 Beach east of intake 0.3 mi, N DR2 2A2 West end of Creek Road. 0.2 mi. NNE DR3 351 Site Boundary. 0.1 mi. NE DR4 451 Site Boundary. 0.1 mi. ENE DRS 552 Site Boundary 0.1 mi. E DR6 652 Site Boundary, 0.1 mi. ESE DR7 7A2 North Country Road 0.7 mi. SE DR8 8A3 North Country Road. 0.6 mi. SSE DR9 951 Service Road SNPS, 0.2 mi 5 DR10 10A1 North Country Road 0.3 mi. SSW DR11 11A1 Site Boundary. 0.3 mi SW DR12 12A1 Meteorological Tower, 0.9 mi, WSW DR13 1353 Site Boundary. 0.2 mi. W DR14 1452 St. Joseph's Villa, 0.4 mi. WNW DRIS 1551 Beach west of intake 0.3 mi, NW DR16 1652 Site Boundary 0.3 mi. NNW DR30 12G1 Central Islip Substation, 19.9 mi. WSW DR31 11G1 MacArthur Substation, 16.6 mi. SW 1
)
BN1-11600.02-112 1 of 1 Revision 17 - May 1991
4 SNPS-1 ODCM TABLE 5 2 RADIOLOGICAL ENVIRONMENTAL ' MONITORINGPROGRAM(REMP) AIRD0RNE MONITORING STATIONS Functional Designation Location Code (NURi:G.0473) (Shoreham REMP) location Description A1 652 Site Boundary. 0.1 mi. ESE A2 2A2 West end of Creek Road, 0.2 mi. NNE A3 351 Site Boundary, 0.1 mi. NE A4 7B1 Overhill Ro-4, 1.4 mi. SE A5 11G1 MacArthur '.oostation,16.6 mi. SW f BN1-11600.02-112 1 of 1 Revision 17 - May 1991
SNPS-1 ODCM TABLE 5-3 RADIOLOGICAL ENVIRONMENTAL MONITORINGPROGRAM(REMP) WATERBORNE MON 110 RING STATIONS Functional Desii) nation Location Code (NUR:G-0473) .(Shoreham REHP) location Description WA1 13G2 Surface, background area, 13.2 mi. W WA2 1401 Surface, outfall area 2.1 mi. WNW WA3 3C1 Surface, outfall area, 2.9 mi. NE Wd1 2A4 Sediment, beach. 0.4 mi. NNE l BN1-11600.02-112 1 of 1 Revision 17 - May 1991 i _ _ ..._ _..,._, ._,. _ , _ _ _ ~ _ _ _ _
SNPS-1 ODCM TABLE S-4 1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM (REMP) INGESTION MONITORING STATIONS j Functional , Designation Location Code (NURe.G 0473) (ShorehamREMP) Location Description la, la2 Not Used , Ib1 301 Fish and Invertebrates, Outfall Area, 2.9 Mi NE Ib2 1401 Fish and Invertebrates. Outfall Area 2.1 Mi, WNW lb3 13G2 Fish and Invertebrates, Background, 13.2 Mi. W Ic1 BB1 Food Product Local Farm,1.2 Mi. SSE Ic2 6821 Food Product. Condzella farm, 1.8 Mt. ESE Ic3 12H1 or Food Products, Background Farm 26 Mi, WSW , 12H2 Food Products, Background Farm, 32.1 Mi WSW I BN1-11600.02-112 1 of 1 Revision 17 - May 1991
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tulu 1m j (Filot) - nt.7 g 10 BlffUltt y FIGURE 3,1-1 LIQUID RADWASTE SYSTEM MODEL SHOREHAM NUCLEAR POWER STATION UNIT 1 OFFSITE DOSE cat.CULATION MANUAL REVISION 17, M AY 1991 s
,, e-nmr, r.-,,w,--we. , - , - > , , , , , , ..,--.-.-e ~-<-<-.,,-r,-~--, ,,--e,-,- ,-n-. . - , - - - - - - -----e.e- - , - - p
1 : SNPS-1 ODCM - 3.2 OPERATION Of LIQUID WASTE TREATMENT SUBSYSTEMS l The dose projection analysis will be performed using the methodology descrit,ed in Section 3.1 with the exception that the calculated doses will be compared with the limits specified in REC Section 3.11.1.3. The liquid radwaste treatment system shall be OPERABLE and appropriate portions of the system shall be used to reduce releases of radioactivity when the projected doses due to the liquid effluent to UNRESTRICTED AREAS would exceed 0.06 mrem to , the total body or 0.2 mrem to any organs in a 31-day period. A model of the liquid radwaste treatment subsystems is shown on Figure 3.1-2. l Although the RHR Service Water Discharge, RBSWDT, and yard piping drain sump ! systems are not part of the radwaste treatment subsystems, they are included in i figure 3.1-2 because they represent locations of potentially radioactive dis-charges. , t t 8 I i BN1-11600.02 92 11.3.2 1 Revision 16 - July 1990
SNPS-1 ODCM 3.3 DOSE RATL DUE TO GASEOUS EFFLUENTS To comply with Section 3.11.2.1 of REC, the dose rate at any time in the un-restricted area for noble gas dose and for organ dose due to radioactive materials in gaseous effluents released via the station ventilation exhaust duct shall be
'imited to the following values:
- 1. 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
- 2. For 1-131, 1-133, tritium, and for all radionuclides in particulate fonn with half lives greater than 8 days: Less than or ecual to 1500 mrem /yr to any organ.
The gaseous effluent model is shown in Figure 3.3 1. 3.3.1 Method 1: (Computertred Method) 3.3.1.1 Release Rate Estimation Dose rate estimation is performed every 15 minutes by making use of the atmospheric dispersion calct.lation made every hour from meteorological data taken every minute (see Section 4), and of the following ecuation for the release rate (Ci/hr):
= F' f Qg. 3 where:
45 F' = 4ky,3 F,(j) bngI3) At f4 = 10~0 q$ (t) /bngIT) _ k = 2.832 x 104 (cc/ft8 ) F3 (j) = vent flow during time interval j (cfm) ~ 2 . Cng(j)
= noble gas effluent monitor count rate during time interval j(cpm) t -=
timeinterval(=1 minute) qg
= concentration of isotope i in the effluent as measured in the lab at time T (pCi/cc).
F' = 15-minute average of the flow and countrate product (for dose rate estimation every 15 minutes) assumed to apply = for a 60-minute interval [(cc/hr) (cpm)J 4 x 15 = number of t intervals per hour (1/hr) { i.- BN1-11600.02-92 11.3.3-1 Revision 16 - July 1990 i
SNPS-1 ODCM l 3.3.1.2 Total Body Dose Rate inh Dground l D wb
= Dcloud wb
+ D wb
+
wb i where: oud , (gg)s p' 2.22 x 104 D i nhbles f DFB 4
' 4 D =
(X/Q)S8 F 3.17 x 10 R ad pdt+1 f iDFA ij,ad 1I ' D{ und
=
(D/Q)F 7 x 10 p{rt+1 I DFG i 4j[1-e-tab iq l oud D r- total body dose due to direct radiation from the radio- ' active cloud [ mrem /hr) (Ref.: Reg. Guide 1.109 Eq. B-81 also similar to qEq. (X/Q)andtheDFB B-6ofif DF instead one{.dosemakes use of the- gam conversion ij D rh = total: bod dose (j = total body) due to inhalation [ mrem /hr) y(Ref.: Reg. Guide 1.109. Eqs. C-3 and C-4, for i an adult)
= total body dose due to particulate and iodine radio-D[und activity depositing on the ground [ mrem /hr] (Ref.: _ Reg.
Guide 1.109 E C-1 and C-2 with the product 8760 [hr/yr) (1/A ) [qs.yr)replacedby(1/A)[hr)andparameter 4 6g(r.0) repre,sented by the (D/Q)). l DFB 9
= gamma dose to body conversion factor [(mrem /yr)/(pCl/m8)]
(from Table B-1 of the guide) DFA ij,ad
= dose conversion factor for nuclide i to organ j of an '
adult individual [ mrem /pCi inhaled] (from Tables E-7 i
-through E-10 of Reg. Guide 1.109)
= total body conversion factor for standing on contaminated DFG4 ) ground [(mrem /hr)/(pCi/m')] (from Table E-6 of Reg. Guide ,
1.109) t
.(X/0)$ ' ..concentrationdispersionfactor(sector-averagemodel)_for the period of release _(site boundary only) (sec/m3)
(X/0)$8 y
= gamma (X/Q)(finitecloudsector-averagemodel)forthe period of release (site boundary only) (sec/m8)
-(D/Q) a particulate' deposit'nrate(siteboundaryonly)(1/m*)
F' f g = Q4 (Ci/hr) (as defii ed in Section 3.3.1.1) , i l BN1-11600-02-92 11.3.3-2 Revision 3 - December 1983
t I i SNPS 1 ODCM R ad
= adultbreathingrate(m8/yr)(fromTableE-5oftheGuide) ,
Ag
= radionuclide decay constant (hr*I) j tb =
time period over which the ac5umulation is evaluated, which is 15 years (1.314 x 10 hours) (Reg. Guide pg - 1.109-24) 3.17x10 4 = 10 I2(8760x3000)[(pC1/01)(yr/sec)]
/
4 2.2x10 = 3.17 x 104 x 0.7, where 0.7 is the shielding factor which accounts for the dose reduction due to the shielding - effects of residential structures during occupancy (Ref.: Reg. Guide 1.109 Table E-15) 12 7x10 II = 10 x 0.7, where 0.7 is the shielding factor and 10 12 4, the number of pCi per C1 (see Eqs. C-1 and C 2 of the '
-guide)
P part+1 = 68 particulates and 5 iodines in M,.e summation sign l 3.3.1.3 Skin Dose Rate D a D cloud 4 Dground skin skin skin where: ; 4 Dc1
,k ud 1.11 x 0.7 (>/Q)sa y F' 3.17 x 10 n bles f i DF}
=
4 4 DF5 (X/Q)S"F'3.17x10 nhbles#1 4 l
-t Dhund
=
(D/Q) F' 7 x 10Il{rt+1p f iDFGi2 [g , g b 1]/h l t c1 ud = skin dose due to direct gama radiation from the D s n radioactive cloud (first - component of the equation with finite cloud modeling) and beta radiation (second component, semi-infinite cloud innersion) < [ mrem /hr) (Ref.: Reg. Guide 1.109 Eq. B-9; also ! similar to Eq. B-7 if one makes use of the ganma (X/Q)) DQund
= skin dose due to particulate and iodine radioactivity !
depositing on the ground [ mrem /hr) (Ref.: Reg. Guide ; 1.109 8760 hr/yr)
-(1/Ad [Eqs. C-1 and C-2 -4 with the productyr) replace representedbythe-(D/Q))
0F{
= gamma dose to air conversion factor [(mrad /yr)/(pCi/m3)]
(from Table B-1 of the Guide) DFS 4
= beta dose to skin conversion factor [(mrem /yr)/(pC1/m3)]
(from Table B-1 of the Guide) BN1-11600-02-92 11.3.3-3 Revision 3 - December 1983 I i
SNPS 1 ODCM DFG = skin dose conversion factor for standing on contaminated i2 ground [(mrem /hr)/(pCi/mt)] (from Table E-6 of Reg. Guide 1.109) D 1.11
- average ratio of tissue to air energy absorption coefficient (fromReg. Guide 1.109,pg1.109-6) 0.7 = shielding dose reduction factor (see pg 1.109-68 of the Guide)
-= radionuclidedecayconstant[hr*I) x4 3.3.1.4 Organ Dose Rate (1 131. 1-133, Tritium and Particulatt- Release)
, (g sa F' 3.17 x 10 4 R,)pfrt+1 f DFA
~
Dhnh i 43, where: inh D ja
= dose to organ j of individual in age grou a due to inhalation of airborne radioactivi,y (mrem /hr)p(Ref.: Reg.
Guide 1.109 Eqs C-3 and C-4.) DFA gja
= dose conversion factor for nuclide i to organ j of individual in age group a [ mrem /pCi inhaled]_ (from Tables E-7 through E-10 of the Guide)
R,
= breathing rate of individual in age group a [m8/yr] (from Table E-5 of Reg. Guide 1.109, for the maximum individ-uals)
The analysis is limited to the computation of the thyroid dose to a child at the _
--site boundary in the downwind sector for the-period of the release (i.e., .' thy. l
._roid, a a child).
BN1-11600-02-92 11.3.3-4 Revision 3 - December 1983
_ _ . . _ _ _ _ _ ~ - _ _ . _ _ _ . _ . _ . . _._. _ SNPS-1 DDCM 3.3.2 Method 2: (Backup Method) 3.3.2.1 Noble Gas Total Body Dose Rate The following equation thould be used: DT 3
=
0.7
- Vj*X/Qj*I[DFB4*C4j) (mrem /yr) i where j DT,
= total body dose rate from all radionuclides releases (mrem /yr).
DFB4= the total body dose rate factor due to genna emissions for each identified noble gas radionuclide (mrem /yr per pC1/m8) (Table 2.21), C = the station ventilation exhaust duct release concentration of il radionuclide, i, (pC1/cc) (from the isotopic analyses performed on the gaseous sample taken from the station ventilation exhaust monitor), BN1-11000-02-92 11.3.3 5 Revision 17 - May 1991
SNPS-1 ODCM V = 1.73E408 cc/sec (3.66E405 cfm), station ventilation exhaust duct 1 ventilation exhaust flow rate, X/Q3 = long term dispersion factor due to release via the station ventila-tion exhaust point; refer to Table 4-1, cells Al and A3, , 0.70 = shielding factor that accounts for dose reduction due to shielding from residential structures. 3.3.2.2 Noble Gas Skin Dose Rate The following equation should be used: DS, a V)*X/Q)*j[K 34 *C4j] (mrem /yr) where: DS s
= skin dose rate from all radionuclides released (mrem /yr),
i I i BN1-11600.02-92 11.3.3-6 Revision 17 - May 1991 l l .- - _ - . .. - . .. . - . - __ .-
I l SNPS-1 ODCM I K gj
= the skin dose factor due to beta and gama emissions for each identified noble gas radionuclide (mrem /yr per pC1/m8) from Table 2.2-1, C = the station ventilation exhaust duct release concentration of II radionuclide, i, (pCi/cc) (from isotopic analyses performed on the gaseous sample taken from the station ventilation exhaust monitor),
l V = 1.73E+0B cc/sec (3.66E+05 cfm), station ventilation exhaust duct . 3 ventilation exhaust flow rate, g I/Q3 = long term dispersion factor due tc release via the station ventila-tion exhoust point; refer to Table 4-1, cells Al and A3, l 3.3.2.3 Organ Dose Rate (Particulate Releases) The following equation should be used: 106,p *E (mrem /yr) ij * */01
- C 4)
D 33 = V)
- A BN1-11600.02-92 11.3.3-7 Revision 17 - May 1991
SNpS-1 ODCH < l wheret D,)
= total dose rate to organ, j, mrem /yr.
P = the inhalation dose conversion factor, for radionuclides other than i ij noble gases,1, and organ, j, in mrem per pC1 f rom Table 3.5-3. The dose f actor P is based on the critical individual organ for theChildgroup,v!dchismostrestrictive. Inhalation done factors for other age groups are given in Tables 3.5-1, 3.5-2, and 3.5-4. R, a inhalation rate (ms/yr), from Table 3.5-5. C = the station ventilation exhaust duct release concentration of I radionuclide, 1, (uci/ce) (from the isotopic analyses perforned on the filter paper and charcoal cartridge taken from the station , ventilation exhaust monitor), V = 1.70E+08 cc/sec (3.60E+05 cf m), station ventilation exhaust duct + 3 ventilation exhaust flow rate,
= long term dispersion factor due to releases via the station ventila-X/Q 3 tion exhaust points refer to Table 4-1, cells A2 and A4, BN1-11600.02-92 11.3.3-8 Revision 17 - May 1991
,i ;
. 1
_ T I
- N U
- L m e
. LN A y
EOI UN ego e n
- DT A OA M y MTS t f
O TRE T 9 I 1 c' N WA9 h EO L 1 UF UC LR L YA m w t t e FA A M w m e n W 1F EL C - E m e 3. E C U S 7 m e e - 3S N O 1 w - D m Ut t N E R OA H TE IO U EE I S GSR S I I A OH FF VE FGS O R
- j
, 3g
=
_3J W j l _- j e e v m. s. i N ' t
=
= - -
=
m s e u , e
, s n -
r e u t ,
, m m = ,
~= ,
, m
- a. ,
e
- ~ , -
~
g e s 3g e i
,iG t
=
=
e S J II J l
~
m m my
,MJ L sQ i
m m-e
- e e
r 'm t a a t t e m s t s r e me r e e e j 4 , i * ' , '
l i l SNPS-1 ODCM l 3.4 GASEOUS EffLVENTS NOBLE GAS AIR DOSE : To comply with Section 3.11.2.2 of the REC the air dose in unrestricted area i location due to releases via the station ventilation exhaust point shall be limited i to the following - I
- 1. During any calendar quarter: Less than or equal to 6 mrads for gamma i radiation and less than or equal to 10 mrads for beta radiation, j
- 2. During any calendar year: Less than or equal to 10 mrads for genna radiation and less than or equal to 20 mrads for beta radiation.
{ 3.4.1 Method 1: (Computerized Method) Cumulative doses are calculated by making use of hourly dose rate equations presented in the following subsections. 3.4.1.1 Release Estimation l Dose estimation is performed every hour by making use of the atmospheric dispersion calculation made every hour from meteorological data taken every minute (see l Section 4), and of the following equation for the release rate (Ci/hr):
= ;
Qi F' f g where: i 6Q . l F' = k ),'gF3(j) C ng Id) 01 fg = 10-6 q )j{ (,) s
-k =
2.832 x 104 (cc/ft3) . F(j) 3
= vent flow rate during interval j (cfm) -
dng (j)- = noble gas effluent monitor count rate during interval j ;
'(cpm)
. At = time interval (= 1 minute) , qg
= concentration of isotope i in the effluent as measured in the lab at time T (pCi/cc) 60-minute- average of -the flow and count-rate product
- F' =-
[(cc/hr)(cpm))- 60 = number of at intervals per hour (1/hr) BN1-11600.02-92 11.3.4-1 Revision 16-July 1990l 7 wwe v--eve--wr4-+=m-me-ee-. en .ww w - , e . .ir+.w s, --es u- we w r t w m e-=, v rwmem< w r,n err <-r werm'V****w*--Wr=*Wtr-e WT-*-gr*9-r-'+"+-P' W t""C'P1'-t'"Trwec' v% "
SNPS-1 ODCM 3.4.1.2 Noble Gas Ganna Air Dose 4
=
DY, air (X/Q)S8 F' 3.17_X 10 no les Y i DF[ where Dy*34I
- gama dose to air at the site boundary in the downwind sector during the period of release (mrad /hr) (Ref.: Reg.
Guide 1.109. Eqs. B-4 and B-5, and also Eq. B-1 with the substitutionof(yjQ)y (X/Q)S" .
= finite-cloud sector-average ' cama' dilution factor at the downwindsite-boundary [sec/ml]
DFY I
. genna dose to air conversion factor (from Taole B-1 of _
Reg. Guide 1.109)[(mrad /yr)/(pCi/m8)] F'f 4 = Qg_(C1/hr)(seeSection3.4.1.1) 3.4.1.3 Noble Gas Beta Air Dose 4 0 (X/Q)S" F' 3.17 X 30 nohles f iDF 3 US . air __ where 0g, air
- in the downwind beta sector dose to air during theatperiod the site boundary [ mrad /hr) (Ref.: Reg.
of release Guide 1.109. Eqs. B-4 and B-5)
= beta dose to air conversion factor (from Table B-1 of Reg.
DF{ Guide 1.109) [(mrad /yr)/(pCi/m3)] F'f g = 04(C1/hr)(seeSection3.4.1.1) (X/Q)S" = sector-average concentration dilution factor at the site boundary during the period of release [sec/m8]
'BN1-11600.02-92 11.3.4-2 Revision 3 - December 1983 I
l
S SNPS-1 ODCM 3.4.2 Method 2: (BackupMethod) 3.4.2.1 Noble Gas Gama Air Dose The following equation should be used:
= (mrad) I D gg 3.17E-08 *V) *tj
- X/Qg
- I [Mg *C)]
g wheret ) D gg = the total gama air dose from the releases (mrad), 3.17E-08 = the inverse of number of seconds in a year, Hj = the air dose factor due to gama emissions for each identified noblegasradionuclide(mrad /yrper Ci/m8) from Table 3.4-1, 1 = 7.88E406 see for quarterly dose calculation. 3 = 3.15E+07 see for yearly dose calculation C 93
= the station ventilation exhaust duct release concentration of radionuclide, i, ( Ci/cc) (from the isotopic analyses perfonned on the gaseous sample taken from the station ventilation ;
exhaustmonitor), BN1-11600.02-92 !!.3.4-3 Revision 17 - May 1991
SNPS-1 ODCM
.Y = 1.73E408 cc/sec (3.66E405 cfm), station ventilation exhaust 3
duct ventilation exhaust flow rate. X/Q3 = long term dispersion factor due to release via the station ventilation exhaust point; refer to Table 4-1, cells B1 and B3, 3.4.2.2 Noble Gas Beta Air Dose The following equation should be used: l Dg = 3.17E-08
- X/Q)
- Vj *t)
- I [Ng *Cgj] (mrad) s 1 BN1-11600.02-92 11.3.4-4 Revision 17 - May 1991
SN!'S-1 ODCH vhere D 33
= beta air dose from all radionuclides released (erad),
N = A the air dose factor due to beta emissions for each identified noble gas radionuclide (mrad /yr per uCi/m') from Table 3.4-1, 3.17E-08 = the inverse o.' number of seconds in a year, 1 t g
= 7.88E+06 see for quarterly dose calculation. )
= 3.1$E+07 see for yearly dose calculation, '
)
C gg = the station ventilation exhaust duct release concentration of radionuclide, 1, (uct/cc) (from the isotopic analyses performed on the gaseous sample taken from the station ventilation exhaust monitor), V 3
= 1.73E+08 cc/sec (3.66E+0$ cin), station ventilation exhaust duct ventilation exhaust flow rate.
= long term dispersion f actor due to release via the station X/Q 3 ventilation exhaust point; refer to Table 4-1, cells B1 and B3, l
EN1-11600.02-92 11.3.4-5 Revision 17 - May 1991 l
i SNPS-1 ODCM TABLE 3.4-1 NOBLE GAS DOSE FACTORS , c Gamma Air Beta Air : Dose factor Dose Factor M N
!sotope Imrad/yr peh VCi/m8) (mrad /yrphrUC1/m8) [
Kr_- 83m 1.9E+01 2.9E402 l Kr - 85m 1.iE*03 2.0E+03 Kr - 85 1.7E401 2.0E+03 Kr - 87 6.2E403 1.0E404 Kr - 88 1.5E404 2.9E+03 , l Kr - 89 1.7E404 1.1E404 Kr - 90 1.6E+04 7.8E403 Xe - 131m 1.6E+02 1.1E403 Xe - 133m 3.3E+02 1.5E+03 Xe - 133 3.5E+02 1.1E403 Xe - 135m 3.4E403 7.4E+02 Xe - 135 1.9E+03 2.5E+03 . Xe - 137 1.5E+03 1.3E+02 Xe - 138- 9.2E+03 4.8E403 Ar - 41 9.3E+03 3.3E403 BN1-11600.02-112 1 of 1 Revision 1 - August 1983
SNPS-1 ODCM 3.5 GASEOUS EFFLUENTS, DOSE DUE 10 RADI0 ACTIVE MATERIALS IN PARTICULATEFORMANDRADIONUCLIDES(otherthanNoble Gases) WITH HALF LIVES GREATER THAN 8 DAYS To comply with Section 3.11.2.3 of the Radiological Effluent Controls, the organ dose to maximum individual in unrestricted area due to particulate releases via the station ventilation exhaust point shall be limited to the following:
- 1. During any calendar quarter: Less than or equal to 7.5 mrem to any organ, and
- 2. During any calendar year: Less than or equal to 15 mrem to any organ.
3.5.1 Method 1: (Computerized Method) Cumulative doses are calculated by making use of hourly dose rate equations presented in the following subsections. 3.5.1.1 Release Estimation Dose estimation is performed every hour by making use of the atmospheric dispersion calculation made every hour from meteorological data taken every minute (see Section 4), and of the following equation for the release rate (C1,hr):
= F' f Q4 4 where:
go . F' = k 3,) F3 (j) Cng(j)At f 4
= 10-6 j q(7)/f ng IT)
L = 2.832 x 104 (cc/ft8) F(j) 3
= vent flow rate during interval j (cfm) b (j) = noble gas effluent monitor count rate during interval j 09 (ctm)
At = timeinterval(*1 minute) qq
= concentration of isotope i in the effluent as measured in the lab at time 1 (pCi/cc)
F' = 60-minute avera of the flow and count-rate product [(cc/hr) (cpm)) ge C0 = number of at intervals por hour (1/hr) BN1-11600.02-112 11.3.5 1 Revision 17 - May 1991
SNPS-1 ODCM 3.5.1.2 Tota? Body Dose
= eloud +
inh + Dgr und D D D wb wb wb wb where: eloud 4 D , (yjgga F' 2.22 x 10 no les f iDFB 4 h 4 (. qsa F' 3,17 x 10 Radpaht+1 if 0 ij,ad l1 d D{ound
=
(D/Q) F' 7 x 10 par (+1 F4 DFG4 ) [1 - e b i]/ A 4 D,c cud = total body dose due to direct radiation from the radioactive cloud [ mrem /hr] (Ref.: Reg. Guide 1.109 Ea. B-8; aiso simila to Eq. B-6 if one makes use of the gron' (X/Q) and the DFB instead of dose conversion factor) h D = total dose (j = total body) due to inhalation [ mrem /hrbody(Ref. : Reg. Guide 1.109, C-3 Eqsand C-4, for an aJalt 4 D{ound
= total body dose due to particulate and iodine radioactivity depositing on the ground [ mrem /hr] (Ref.:
Reg. Guide 1.109, Eqs. C-1 and C-2 with the product 8760 - Lhr/yr) (1/A 6(,0)reprAs)en[yr]replacedby)[1/A)[hr]andparameter ted by the (D/Q ) 4 4 DFB. = gamma dose to body conversion foctor [(mrem /yr)/(pCi/m3)] I (from Table B-1 of the Reg. Guide) DFA ij,ad
= dose conversion factor for nuclide i to organ j of an adult individual [ mrem /pCi inhaled] (from Table E-7 of Reg. Guide 1.109)
= total body conversion factor for standing on contarr.inated DFGj )
ground [(mrem /hr)/(pCi/m?)] (from Table E-6 of Reg. Guide 1.109) (X/Q)S
= concentration dispersion factor (sector-average model) for the period of release (site boundary only) (sec/m3)
Btil-11600.02-112 11.3.5-2 Revision 10 - August 1987 v.
SNPS-1 ODCM
- ( X/Q)S"y
= gama (X/Q) (finite cloud sector-average model) for the ;
period of release (site boundary only) (sec/m3) (D/Q) = particulate deposition rate (site boundary only) (1/me ) F' f = 4 Q4 (Ci/hr) (as defined in Section 3.5.1.1) R ad
= adult breathing rate (m3/yr) (from Table E-5) g = radionuclide decay constant (1/hr) t b
=
time period over which the- accuplation is evaluated, which is 15 years (1.314 x 10 hours) (Reg. Guide pg 1.109-24) 4 3.17x10 = 10 12/ (8760 x 3600) L(pCi/Ci) (yr/sec)] 4 2.22x10 = 3.17 x 104 x 0.7, where 0.7 is the shielding factor which accounts for the dose reduction due to the shielding effects of residential structures during occupancy (Ref.: Reg. Guide 1.109 Table E-15) 7x10 II = 10 12 x 0.7, where 0.7 is the shielding factor and 10 12 43 the number of pCi per C1 (see Eqs. C-1 and C-2 of the guide) part+1 = 68 particulates and 5 iodines in the summation sign Note that. the total " total body" dose as computed above is used only for hourly assessment of plant operation within the specification limits. The reports pre. pared by the dose software include the total oody dose due to inhalarion as a separate parameter. Also note that the equation conservatively includes the dose due to the airborne noble gases, even though this section addresses only the iodines and particulates. 3.5.1.3 Skin Dose
= D cloud + Dground D
skin skin skin wheret el d = 1.11 x 0.7 (X/Q)sa p. 3.17 x 10 4 D f nobles i DFf
+ (X/Q)sa p. 3.17 x 104 f iDFS 4 nobles l BN1-11600.02-112 11.3.5-3 Revision 3 - December 1983
-- - . . - - .. . - . _ . ~ . - . - - . . . . - - . . - . . _ , - - - - ~ . - -
-SNPS-1 ODCM II parbl I iDFG 12 [1 - e'Ibi]/q 9
0 ]"nd n
=
(D/Q)F'7_x10 - l D eloud a skin dose due to direct gamma radiation from the-skin- radioactive cloud -(first component of the equation with - finite cloud modeling) and beta radiation (second compon- ; ent, semi-infinite cloud inunersion) [ mrem /br] (Ref.: Reg. Guide 1.109 Eq. B-9; also similar to Eq. B-7 if one makes use of the gamma (X/Q)) D{"nd n skin dose due to particulate and iodine radioactivity ! depositing on the ground [ mrem /nr] (Ref.: Reg. Guide 1.109, Eqs. C and C-2 with the product 8760[hr/yr] (1/A )[yr) replaced by (1/A )[hr] 4 j and parameter 6 4 (r 0) represented by the (D/Q)) DFT 4
= gangna dose to air conversion factor [(mrad /yr)/(pCi/m8)]
(from Table B-1 of the Guide)- DFS j- = beta dose to skin -conversion factor [(mrem /yr)/(pCi/m8)] (from Table B-1 of the Guide) DFG 12
= skin dose conversion factor for standing on contaminated ground [(mrem /hr)/(pCi/m e )) (from Table E-6 of Reg. Guide 1.109) 1.11 = avera ent (ge from ratio Reg.ofGuide tissue to airpgenergy 1.109, absorption coeffici-1.109-6) 4 0.7 = shieldin dose-reduction factor (from Reg. Guide 1.109. pg
-1.109-68 and the remaining parameters are as defined above in Section 3.5.1.2.
- Note that : the total skin dose as described here -includes the contribution of
. airborne .: noble gases, even though this section addresses only the iodines and particulates.-
BN1-11600.02-112 11.3.5-4 Revision 3 - December 1983
- - -- . .. - ~ - .- .. . . - . - _ . . _ . _ - ,.
.SNPS-1 ODCM 3.5.'1.4 Organ Doses Due to Inhalation- ,
D h , - (pg)sa F' 3.17 x 104 R a paft+1 f DFAj ), i where:- inh D ja -
= dose. to organ j of individual in age grou a due to inhalation of airborne radioactivity [ mrem /hr]p(Ref.: Reg.
Guide 1.109 Eqs. C-3 and C-4) DFA jja = dose conversion factor for nuclide i to organ j of individual in age group a [ mrem /pci inhaled] (from Tables
- E-7 through E-10 of the Guide)
R,
= breathing rate of-individual-in age group a [m3/yr] (from Table E-5 of Reg. Guide 1.109, for the maximum-individuals) !
( x/Q)sa = concentration dispersion factor (Sector-Average model) for the- period of release (nearest garden and nearest residence)[sec/m8] . 3.5.1.5 p__rganDeseDuetoIngestionofLeafyVegetables I = ing i I Dj a"9 (D ja ) part + (D "9) ja iodines + (D "9)C14 ja ! where:
= 0 (D]9)part (D/Q) F' 1.1 x 10 pa t
" f i DFl ija 9 A 0.2 + 1v e'24 i
)
xE(A4 2
+ 0.0021) 240 A j 7
-- (D 9) iodines
=
(D/Q) F' 5.5 x 10 iodines i DFl ija B 1.0 + iv e'24A1 1) xb(Aj 2 + 0.0021) 240A DFI (D a"9)C14
=-
(X/Q)" F' 5.5 x 10Iff C14 C14,ja 7 l
= DFI (D 9)H3 (X/Q) F' (1.2 x 10 ) U, fH3 H3,ja BN1-11600.02-112 11.3.5-5 Revision 3 - December 1983
~. - . . - -. . . . .- - . . . - . - - . . . . . . - - .
r SNPS-1 ODCM
= dose to organ j- of individual in age group a due to (Dh"9)- part ingestion-of leafy vegetables contaminated with particulate radioactivity [ mrem /hr] (Ref.: Reg. Guide 1.109, Eqs ' C-5, C-6 and C-13 for leafy vegetables only, with-the following:
- r(fraction of' deposited activity retained on crops)
= 0.2 (see pg 1.109-68 oftheGuide) i
*t (time period that crops are exposed to c 8ntaminationduringgrowingseason)= [h-s]
- tu (time period over which the accumulation is evaluated) = [ hrs]
" ts (time delay between harvest of vegetation or cPopsandingestion)=24[ hrs]
*Yy (agricultural productivity) = 2 [kg/mr ]
"P(soileffectivesurfacedensity)=240[kg/m] r
+ 0.0021 [hr*I] (Ref.: Reg. Guide 1.109,
*xh=1.b9-4and1.109-69) p ,
*$ $-(r,0)=(D/Q)[m-2]
- f y (fraction of leafy vegetables growing in garden of interest) = 1.0 in = dose to organ j of individual in age group a due to (DJ ,g) iodines ingestion of leafy vegetables contaminated with radiciodines [ mrem /hr] (Ref.: Reg, Guide 1.109 Eqs.
C-5, C-7 and C-13 for leafy vegetables only; similar to the organ dose due to particulate radioactivity given above but with r = 1.0 and different-multiply-ing constant) I (Dja"9) = dose to organ j of individual in age group a due to C14 ingestion of leafy vegetables exposed to airborne Carbon-14 [ mrem /hr] (Ref.: Reg. Guide - 1.109, Eqs. C-8 and C-13 for leafy vegetables only, with p (the ratio of the total annual release time to the total annual time during which photosynthesis occurs) = 1) (D 9) -= dose to organ j of individual in age group a due to H3 ingestion of leafy vegetables exposed to airborne tritium [ mrem /hr] (Ref.: Reg. Guide 1.109. Eqs. C-9 and C-13 for leafy vegetables only) r BN1-11600.02-112 11.3.5-6 Revision 3 - December 1983 l l
-.s _- - . , . _ _ _ . _ , _ _ _ _ - . _ _ , .
SNPS-1 ODCM l U a
=
- ingestion rate of leafy vegetables by individual in.- age g[roup]a(fromTableE-5oftheGuide,maximumindividual) kg/yr
- 8 4V = concentration factor for uptake of radionuclide i from soil: by edible parts of crops [(pCi/kg)(wet weight)/
(pCi/kg) (dry soil)] (Ref.: Reg. Guide 1.109. Table -E and included on Table 3.5-6) DFI kja
= dose conversion factor for-nuclide i to organ j of individual in age group a due to ingestion of contaminated food [ mrem /
the Guide) pCi ingested] (from Tables E-11 through E-14 of DFI C14.ja = DFl
$p for Carbon-14 DFI H3,ja
= DFl ija for tritium F
C14 i f r Carbon-14 (see Section 3.5.1.1 above) f
- f f r tritium H3 i H = absolute humidity of the atmosphere at the location of interest [g/m3](SeeTable3.5-7)
(X/Q)5 = concentra_ tion dispersion factor (Sector Average model) for the period of release (nearest garden and nearest-residence)[sec/m3] (D/Q) = particulate deposition rate (nearest garden and nearest residence)[1/m?] 3.5.1.6 Infant' Thyroid Dose Due to Ingestion of Goat Milk and Inhalation Bot. Infant thyroid dose equationi 82-inh --+ D thy,1nf
= D thy,1nt D milk, thy,1n f where:
milk
- milk #
milk
.O thy,inf (Othy,inf)'part $0 thy,inf) iodines
+
milk + milk (Dthy,inf) C14- (Dthy,inf) H3 4 D
,$nf
-=
(X/Q)S" F' 3.17 x 10 R infpaht+1 f iDFA i, thy,inf BN1-11600.02-112 11.3.5-7 Revision 13 - November 1988
SNP_S-1 ODCM i 8 (D inf) part * (D/Q) F' 1.1 x_10 art Uynf fi DFl i, thy,inf-0.2 + Biv x 6 F,$ [ 0.7tA + 0.0021) 3e-24AI 240x i i 7 (D inf) iodines
=
(D/O F' 5.5 x 10 iod nes Dynf fi DFl i thy.inf 1.0 , B iv -24kg x 6 F* ~ 3e
- 0. 7( A4+0.6071T 240A 4 7
ID inf)C14
=
(X/Q)S" F' 2.2 x 10 U nf C14 I DFI C14, thy,inf x6fm C14 **PI-2 C14) 7 ' milk = m (Dthy,inf)H3 (x/Q)sa F,[1.?x10 )Uinf H3 f DFI H3, thy,inf H
\
x6Fm,H3 **P(~24 H3) inh D thy,inf.
= infant thyroid dose due to inhalation of airborne radioactivity [ mrem /hr] (Ref.: Reg. Guide 1.109, Eqs. C-3 and C-4) ,
(gilk = infant thyroid dose due to ingestion of milk contam-thy,inf)part inated with radioactive particulates [ mrem /hr] (Reg. Guide Eqs. C-5, C-6, C-10, C-11 and- C-13) for _ milk, with the following:
- r (fraction of deposited activity retained on crops) = 0.2 (see pg 1.109-68 of the Guide)
"t '(time period that crops are exposed to c8ntamination during growing-season) = [ hrs]
- t ' (time period over which accumulation is
~
e haluated)= thrs]
*t
. =0 h ([ time delay1.109-69 hrs](seepg for ingestion of_ Reg. of forage Guide) by animals)-
*Y I mXn(agricultural pathway) = 0.7productivity,
[kg/m r] (Reggrass-animal-Guide 1.109, Rev. milk- .
- 0) I
- P (soil effective surface density) = 240 [kg/me ]
BN1-11600.02-112 11.3.5-8 Revision 10 - August 1987
. .-. - . - _ -~ - .. _ . _- . SNPS-1 ODCM
'A Ei
- Ai+0.0021[hr"I](seepgs1.109-4and 1.109-69) a 6 4(r.0)=(D/Q) [m'2]
t, (average transport time of activity from the pg. feed into the milk and to the receptor); data ,1 listed in Table 4-2 f (fractionofthe,"ehrthatanimalsgrazeon g y, pEsturebasedonsurveydata);datalistedinTable
'1 4-2 i f
when(fractionofdailyfeedthatispasturegrass p the animal grazes on pasture based on survey #1 data); data listed in Table 4-2 milk = infant thyroid dose due to ingestion of milk contam-(Dthy,inf) iodines inatedwithradio-iodines [ mrem /hr](Ref.: Reg. Guide Eqs. C-5, C-7, C-10, C-11, and C-13 for milk; similar ' to the infant thyroid dose due to the ingestion of particulates given above, d th the exception of a different multiplying factor and r = 1.0) milk = infant thyroid dose due to ingestion of milk contam-(Dthy,inf)C14 inated with C14 [ mrem /hr] (Ref.: Reg. Guide 1.109, Eqs. C-8, C-10, C-11 and C-13 for milk, with p (the ratio of the total annual release time to the total annual time during which photosynthesis occurs) = 1, and t, f and f 5 as given above for the partictflated, milk = infant thyroid dose due to ingestion of milk contam-(Dthy,inf)H3 inated with tritium [ mrem /hr] (Ref.: Reg. Guide 1.109, Eqs. C-9, C-10, C-11, and C-13 for milk, with t f, f , pand f as 3 given above for the particulates) R$ "f
= infant breathing rate [m3/yr] (from Table E-5 of the Guide, for maximum individual)
DFA i, thy inf
= dose conversion factor for nuclide i to the infant thyroid due -to inhalation [ mrem /pCi inhaled] (from Te.ble E-10 of the Guide)
DFI i, thy,inf
= dose conversion factor for nuclide i to the infant thyroid due to ingestion [ mrem /pci ingested] (from ,
Table E-14 of the Guide) DFI
- 0 f r Carbon-14 C14, thy,inf i thy,inf DFI
- O for tritium H3, thy,inf i, thy,inf BN1-11600.02-112 11.3.5-9 Revision 13 - November 1988
SNPS-1 ODCM ~ F C14
#1 for Carbon-14 (see Section 3.5.1.1 above)
F H3
- Ii for tritium Ujnf = milk ingestion rate by-infant [ liters /yr] (Ref.: Reg.
Guide 1.109 Table E-5, max ind.) Fgg =- average fraction of the animal's daily intake of radionuclide i which appears in each liter of milk [ days / liter] from Table E-2 of the Guide, with F, = F,j,forgoat) B a concentration - factor for uptake of' radionuclide i 4V
~ from soil by edible parts of crops [(pCi/kg) (wet weight) / (pC1/kg) (dry soil)] (from Table E-1 of the Guide and included on Table 3.5-6)
H- = absolute humidity of the atmosphere at the location ofinterest(g/m3](SeeTable3.5-7) 6 = amount- of feed consumed by a goat per day [kg/ day] (from Table E-3 of the Guide. Q p factor)
= concentration dispersion factor (Sector - Average (x/Q)sa of release (nearest goat model) for the location)[sec/m8] period (D/Q) = particulate deposition rate (nearest goat location) .
e L1/m] BN1-11600.02-112 11.3.5-10 Revision 13 - November 1988
1 SNPS-1 ODCM ! 1 3.5.2 Method 2: (Backup Method) 3.5.2.1 Organ Doses: The following equation should be used: D) = 3.17E-08 *V3
*t 3
*{[(106 *R, *P jj *x/Q3 + P gjj *u/Q3 )*C113 (*f**)
(3.5.2-1) l where: D j
= total dose to organ j (mrem),
P gd = the inhalation dose conversior factor for radionuclides,1, (other than noble gases), and organ j, (mrem per pCi inhaled) from Table 3.5-3. P values listed in Table 3.5-15 and 3.5-16 respectively are the dbe rate conversion factors for tritium and carbon-14 from inhalation and ingestion of leafy and stored vegetables and ingestion of goat's milk. l t i l l BN1-11600.02-112 11.3.5-11 Revision 17 - May 1991 l l-
SNPS-1 ODCM R,
= inhalation rate-(m3/yr) from Table 3.5-5, P the dose conversion factor for radionuclides, other than noble OId = gases, i, and organ j, for contaminated ground, ingestion of leafy and stored vegetables in m r(mrem /yr per uCi/sec) from Table 3.5-9.
The dose factors P P I are based on the critical individual organforthechildh,oup?$1ncethisgroupismostrestrictive, t 1
= 7.88E+06 see for quarterly dose calculation
= 3.15E407 see for yearly dose calculation, C
93
= the station ventilation exhaust duct release concentration of radionuclide,1, (uC1/cc) (from the isotopic analyses performed on the filter cartridge taken from the station ventilation exhaust monitor),
= 1.73E+08 cc/sec (3.66E+05 cfm), station ventilation exhaust duct V) ventilation exhaust flow rate, X/Q3 = long term dispersion factor due to releases via the station ventila-tion exhaust point; refer to Table 4-1, cells C1 and C3, BN1-11600.02-112 11.3.5-12 Revision 17 - May 1991 l
l
SNPS-1 ODCM long term deposition factor due to releases via the station D/Q) = ventilation exhaust point; refer to Table 4 1, cells C1 and C9, 3.17E-08 = inverse of 3.15E+07 sec/yr, and NOTE: If the land use census (see Table 3.5-8) changes, the critical location; i.e., the location where an individual would be exposed to the highest dose, must be reevaluated using Equation 3.5.2-1 for each of the following locations:
- 1. nearest residence,
- 2. nearest vegetable garden, and
- 3. nearest milk cow or goat.
P used in Equation 3.5.2-1 will include the values in Tables 3.5-10 through 3N14,ifthosepathwaysexist. U At each location, the following pathwaye m'.5 + be considered and dose (dose rates) reevaluated if any actual pathway exists:
- 1. inhalation,
- 2. leafyvegetables(fresh),
- 3. stored vegetables,
- 4. goat's or cow's milk (if both exist choose the one resulting in the higherdose),and
- 5. deposition on ground.
Since a person will always be present, pathways 1 and 5 must always be evaluated. Once the location of the critical individual is determined and found to be other thar the one listed in Table 4-1 (cell C1), the values of X/Q and D/Q at the updated critical location must be used. BN1-11600.02-112 11.3.5-13 Revision 17 - May 1991
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- E F p h T
o 4. o o c 'o o o o o o o o o o o o o o o o o o o o o o o 1 4 l' N7NNNNNNNNNNNNNNNNNNNNNNNNNN 3 PB Er NA Se f S. T Op D o m 1 N e. Or I m y 7766871 767661163889688640192610 T( 0000001000001101000000001101011 A d - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - L o EEEEEEEEEEEEEEEEEEEEEEEEEEEEEEE A B 8686579329514925110712923417576 H 5222282935881686096341061602572 N . - I T 1416172412111755331722173371133 7766' 60667661052 588 0000'a01000001101
- - - - t - - - - - - - - -
aaa000aaaaaaaaa
- - ttt - - - ttttttttt r EEEEaEEEEEEEEEEEaaaEEEaaaaaaaaa e 8684D55278432394DDD940DDDDDDDDD v
i L 5 2 2 6. o 95149406821 .ooo 6 8 2. o o o o o o o o o 1419N41231132118NhN143NNNNNNNNN 664 66 50 62 529071595 a 0 0 0 a' a a 0 0 a a 01 a01 aaaaaa t - - - ttt - - tt - - t - - t ttttt - - - - - - - - - 000101000 e aEEEaaaEEaaEEaEEaaaaaaEEEEEEEEE n D785DDD77DD02D53DDDDDD 044316898 o o 2 2 6. o o o 0 4. o o 4 9.o 0 2. o o o o o o 827462721 9 B N211NNN31NN51N44NNNNNN 317823511 9 2 0 0 0 e 6 d 1 oi 4 1465980354593456899012 m 1 i l dc 31 422555555666666888888899901 123 - au 3 - - - - - - - - - - - - - - - - - - - - - - 99999 1
- - a - rnneeooiiunnrrrbbb rrrr - - - - - N R n HCNPCMMFFCCNNCZZBBBRRRSSSSYYYYY B l lllll !! lill' ; ! il .I ' j i? 4 i:[ji ,
i SNPS-1 ODCM' TABLE 3.5-1 (CONT'D) Radio-nuclide T. Body, Kidney
-Bone- Liver Thyroid Lung GI-LLI j
Zr-95 1.34E-05 4.30E-06' 2.91E-06 No Data 6.77E-06 2.21E-04 1.88E-05 i ! Zr-97. 1.21E-08 2.45E-09 1.13E-09 No Data 3.71E-09 9.84E-06 6.54E-05 . Nb-95 1.76E-06 9.77E-07 5.26E-07 No Data 9.67E-07 6.31E-05 1.30E-05
- Mo-99 No Data 1.51E-08 2.87E-09 No Data 3.64E-08 1.14E-05 3.10E-05 -[
2 Tc-99m 1.29E-13 3.64E-13, 4.63E-12 No Data 5.52E-12 9.55E-08 5.20E Tc-101 -5.22E-15 7.52E-15' 7.38E-14 No Data 1.35E-13 4.99E-08 1.36E-21 t Ru-103 1.91E-07 No Data- 8.23E-08 No Data 7.29E-07 -6.31E-05 1.38E-05 .! Ru-105 9.88E-11 No Data 3.89E-11 No Data 1.27E-10 1.37E-06 6.02E-06, Ru-106 8.64E-06 No Data: 1.09E-06 No Data 1.67E-05 1.17E-03 1.14E-04 't Ag-1 1.35E-06 1.25E-06 7.43E-07 No Data 2.46E-06 5.79E-04 3.78E-05 ~ q Ie-125m' 4.27E-07 11.98E-07 5.84E-08 1.31E-07 1.55E-06 3.92E-05 8.83E-06' i Te-127m 1.58E-06 7.21E-07 1.96E-07 4.11E-07 5.72E-06 1.20E-04 1.87E-05 Te-127 1.75E-10 8.03E 3.87E-11 1.32E-10 6.37E-10 8.14E-07 7.17E-06 Te-129m 1.22E-06 5.84E-07; 1.98E-07 4.30E-07 4.57E-06 1.45E-04 4.79E-05 't Te-129 6.22E-12 2.99E-12' 1.55E-12 4.87E-12 2.34E-11 2.42E-07 1.96E-08 , Te-131m 8.74E-09 5.45E-09L 3.63E-09 6.88E-09 3.86E-08 1.82E-05 6.95E-05 i Te-131 1.39E-12 7.44E-13 4.49E-13 1.17E 5.46E-12 1.74E-07 2.30E-09 Te-132 3.25E-08 ' 2.69E-08 2.02E-08 2.37E-08 1.82E-07 3.60E-05 6.37E-05 I-130 5.72E-07 ,1.68E-06 6.60E-07 1.42E-04 2.61E-06 No Data 9.61E-07 l-131 3.15E-06 4.47E-06 2.56E-06 1.49E-03 7.66E-06 No Data 7.85E-07 i I-132 1.45E-07 4.07E-07 1.45E-07 1.43E-05 6.48E-07 No Data 5.08E-08 I-133 1.08E-06 1.85E-06 5'.65E-07 2.69E-04 3.23E No Data 1.11E-06 I-134 8.05E-08 2.16E-07 7.69E-08 3.73E-06 3.44E-07 No Data 1.26E-10 ! I-135 3.35E-07 8.73E-07 3.21E-07 5.60E-05 1.39E-06 No Data 6.56E-07 , Cs-134 4.66E-05 1.06E-04 9.10E-05 No Data 3.59E-05 1.22E-05 1.30E-06 ; Cs-136 4.88E-06 1.83E-05 1.38E-05 No Data 1.07E-05 1.50E-06 1.46E-06 Cs-137 5.98E-05 7.76E-05 5.35E-05 No Data 2.78E-05 9.40E-06 1.05E-06 1 Cs-138 4.14E-05 7.76E-08 4.05E-08 No Data 6.00E-08 6.07E-09 2.33E-13 Ba-139 1.17E-10 8.32E-14 3.42E-12 No Data 7.78E-14 4.70E-07 1.12E-07 Ba-140 4.88E-06 6.13E-09 3.21E-07 No Data 2.09E-09 1.59E-04 2.73E-05 Ba-141 1.25E-11 9.41E-15 4.20E-13 Po Data 8.75E-15. 2.42E-07 1.45E-17 Ba-142 3.29E-12 3.38E-15 , 2.07E-13 ho Data 2.86E-15 1.49E-07 1.96E-26 '
- -La-140 4.30E-08 2.17E-08 5.73E No Data No Data 1.70E-05 5.73E-05 La-142 8.54E-11' 3.88E-11 9.65E-12 No Data No Data 7.91E-07 2.64E-07 I)
BN1-11600.02-99 2 of 3 -Revision 1 - August'1983
SNPS-1 ODCM' TABLE 3.5-1 (CONT'D) ! Radio-nuclide Bone Liver T. Body Thyroid Kidney . Lung GI-LLI l Ce-141 -2.49E-06' 1.69E-06 1.91E-07 No Data 7.83E-07 4.52E-05 1.50E . Ce-143 2.33E-08 1.72E-08 1.91E-09 No Data 7.60E-09 9.97E-06 2.83E-05 ' Ce-144- 4.29E-04 1.79E-04 2.30E-05 No Data 1.05E-04 9.72E-04 1.02E-04 " Pr-143 1.17E-06 4.69E-07 5.80E-08 No Data 2.70E-07 3.51E-05 2.50E-05 - I Pr-144 3.76E-12 1.56E-12 1.91E-13 No Data 8.81E-13 ;1.27E-07 2.69E Nd-147 6.59E-07 7.62E-07 4.56E-08 -No Data 4.45E-07 2.76E-05 2.16E-05 . W-187 1.06E-09 8.85E-10 3.10E-10 No Data No Data 3.63E-06 1.94E-05 l 1 Np-239 2.87E-08' 2.82E-09 1.55E-09 No Data 8.75E-09 4.70E-06 1.49E-05 ., ! I i i i . P l i I ! l 4 BN1-11600.02-99 3 of 3 Revision 1 - August 1983 ; 6
w SNPS-1 ODCM TABLE 3.5-2 INHALATION DOSE FACTORS FOR TEENAGER (mrem per pCi inhaled) Radio- GI-LEI nuclide Bone Liver T. Body Thyroid Kidney Eung No Data 1.59E-07 1.59E-07 1.59E-07 1.59E-07 1.59E-07 1.59E-07 H-3 3.25E-06 6.09E-07 6.09E-07 6.09E-07 6.09E-07 6.09E-07 6.09E-07 C-14 1.72E-06 1.72E-06 1.72E-06 1.72E-06 1.72E-06 1.72E-06 1.72E-06 Na-24 2.36E-04 1.37E-05 8.95E-06 No Data No Data No Data 1.16E-05 P-32 Cr-51 No Data No Data 1.69E-08 9.37E-09 3.84E-09 2.62E-06 3.75E-07 No Data 6.39E-06 1.05E-06 No Data 1.59E-06 2.48E-04 8.35E-06 Mn-54 No Data 2.12E-10 3.15E-11 No Data 2.24E-10 1.90E-06 7.18E-06 Mn-56 4.18E-06 2.98E-06 6.93E-07 No Data No Data 1.55E-05 7.99E-07 Fe-55 1.99E-06 4.62E-06 1.79E-06 No Data No Data 1.91E-04 2.23E-05 Fe-59 Co-58 No Data 2.59E-07 3.47E-07 No Data No Data 1.68E-04 1.19E-05 No Data 1.89E-06 2.48E-06 No Data No Data 1.09E-03 3.24E-05 Co-60 7.25E-05 5.43E-06 2.47E-06 No Data No Data 3.84E-05 1.77E-06 Ni-63 4.59E-06 Ni-65 2.73E-10 3.66E-11 1.59E-11 No Data No Data 1.17E-06 ' No Data 2.54E-10 1.06E-10 No Data 8.01E-10 1.39E-06 7.68E-06 Cu-64 4.82E-06 1.67E-05 7.80E-06 No Data 1.08E-05 1.55E-04 5.83E-06 Zn-65 6.04E-12 1.15E-11 8.07E-13 No Data 7.53E-12 1.98E-07 3.56E-08 Zn-69 No Data No Data 4.30E-08 No Data No Data No Data < 1.00E-24 Br-83 ' No Data No Data 5.41E-08 No Data No Data No Data < 1.00E-24 Br-84 No Data No Data 2.29E-09 No Data No Data No Data < 1.00E-24 Br-85 2.21E-06 Rb-86 No Data 2.38E-05 1.05E-05 No Data No Data No Data Rb-88 No Data 6.82E-08 3.40E-08 No Data No Data No Data 3.65E-15 Rb-89 No Data 4.40E-08 2.91E-08 No Data No Data No Data 4.22E-17 5.43E-05 No Data 1.56E-06 No Data No D&ta 3.02E-04 4.64E-05 Sr-89 9.56E-05 Sr-90 1.35E-02 No Data 8.35E-04 No Data No Data 2.06E-03 1.10E-08 No Data 4.39E-10 No Data No Data 7.59E-06 3.24E-05 Sr-91 Sr-92 1.19E-09 No Data 5.08E-11 No Data No Data 3.43E-06 1.49E-05 Y-90 3.73E-07 No Data 1.00E-08 No Data No Data 3.66E-05 6.99E-05 Y-91m 4.63E-11 No Data 1.77E-12 No Data No Data 4.00E-07 3.77E-09 Y-91 8.26E-05 No Data 2.21E-06 No Data No Data 3.67E-04 5.11E-05 Y-92 1.84E-09 No Data 5.36E-11 No Data No Data 3.35E-06 2.06E-05 Y-93 1.69E-08 No Data 4.65E-10 No Data No Data 1.04E-05 7.24E-05 BN1-11600.02-100 1 of 3 Revision 1 - August 1983
SNPS-1 ODCM TABLE 3.5-2 (CONT'D) Radio-nuclide' Bone Liver T. Body Thyroid Kidney . Lung GI-LLI Zr-95 1.82E-05 5.73E-06 3.94E-06 No Data 8.42E-06 3.36E-04 1.86E-05 Zr-97 1.72E-08 3.40E-09 1.57E-09 No-Data 5.15E-09 1.62E-05 7.88E-05
.Nb-95 2.32E-06 1.29E-06 7.08E-07 No Data 1.25E-06 9.39E-05 1.21E-05
.Mo-99 No Data 2.11E-08 4.08E-09 No Data 5.14E-08 1.92E-05 3.36E-05 Tc-99m 1.73E-13 4.83E-13 6.24E-12 No Data 7.20E-12 1.44E-07 7.66E-07 Tc-101 7.40E-15 1.05E-14 1.03E-13 No Data 1.90E-13 8.34E-08 1.09E-16~
Ru-103 2.63E-07 No Data 1.12E-07 No Data 9.29E-07 9.79E-05 1.36E-05 Ru-105 1.40E-10 No Data 5.42E-11 No Data 1.76E-10 2.27E-06 1.13E-05 I Ru-106 1.23E-05 No Data 1.55E-06 No Data 2.38E-05 2.01E-03 1.20E-04 Ag-110m 1.73E-06 1.64E-06 9.99E-07 No Data 3.13E-06 8.44E-04 3.41E-05 le-125m. 6.10E-07 2.80E-07 8.34E-08 1.75E-07 No Data 6.70E-05 9.30E-06 I Te-127m 2.25E-06 1.02E-06 2.73E-07 5.48E-07 8.17E-06 2.07E-04 1.99E-05 1 Te-127 2.51E-10 1.14E-10 5.52E-11 1.77E-10 9.10E-10 1.40E-06 1.01E-05 > Te-129m 1.74E-06 8.23E-07 2.81E-07 5.72E-07 6.49E-06 2.47E-04 5.06E-05 Te-129 8.87E-12 4.22E-12 2.20E-12 6.48E-12 3.32E-11 4.12E-07 2.02E-07 Te-131m 1.23E-08 7.51E-09 5.03E-09 9.06E-09 5.49E-08 2.97E-05 7.76E-05 Te-131 1.97E-12 1.04E-12 6.30E-13 1.55E-12 7.72E-12 2.92E-07 1.89E-09
- Te-132 4.50E-08 3.63E-08 2.74E-08 3.07E-08 2.44E-07 5.61E-05 5.79E-05 I-130 7.80E-07 '2.24E-06 8.96E-07 1.86E-04 3.44E-06 No Data 1.14E-06 l-131 4.43E-06 6.14E-06 3.30E-06 1.83E-03 1.05E-05 No Data 8.11E-07
- I-132 1.99E-07 5.47E-07 1.97E-07 1.89E-05 8.65E-O' No Data 1.59E-07 I-133. 1.52E-06 2.56E-06 7.78E-07 3.65E-04 4.49E-06 No Data 1.29E-06
- I-134 1.11E-07 2.90E-07 1.05E-07 4.94E-06 4.58E-Oi No Data 2.55E-09 l-135 4.62E-07 1.18E-06 4.36E-07 7.76E-05 1.86E-06 No Data 8.69E j Cs-134 6.28E-05 1.41E-04 6.86E-05 No Data 4.69E-05 1.832-05 1.22E-06 Cs-136 6.44E-06 2.42E-05 1.71E-05 No Data 1.38E-05 2.22E-06 1.36E-06
- l. Cs-137 8.38E-05 1.06E-04 3.89E-05' No Data 3.80E-05 1.51E-05 1.06E-06 Cs-138 5.82E-08' 1.07E-07 5.58E-08 No Data 8.28E-08 9.84E-09 3.38E-11
, Ba-139 1.67E-10 1.18E-13 4.87E-12 No Data 1.11E-13 8.08E-07 8.06E-07' Ba-140 6.84E-06 8.38E-09 4.40E-07 No Data 2.85E-09 2.54E-04 2.86E-05 Ba-141 1.78E-11 1.32E-14 5.93E-13 No Data 1.23E-14 4.11E-07 9.33E-14 Ba-142 4.62E-12 4.63E-15 2.84E-13 No Data 3.92E-15 2.39E-07 5.99E-20
- La-140 5.99E-08 2.95E-08 7.82E-09 No Data No Data 2.68E-05 6.09E-05 La-142 1.20E-10 5.31E-11 1.32E-11 No Data No Data 1.27E-06 1.50E-06 BN1-11600.02-100 ? of 3 Revision 1 - August 1983
SNPS-1 ODCM TABLE 3.5-2 (CONT'0) , Radio-nuclide Bone Liver T.-Body l Thyroid Kidney l Lung GI-LLI i Ce-141- 3.55E-06 '2.37E-06 2.71E-07. No Data 1.11E-06 7.67E-05 1.58E-05 Ce-143- 3.32E-08 2.42E-08 2,70E-09 No Data 1.08E-08' '1.63E-05 3.19E-05' : Ce-144- 6.11E-04 2.53E-04 3.28E-05 No Data 1.51E-04 ,1.67E-03 1.08E-04 Pr-143 1.67E-06 6.64E-07 8.28E-08 No Data 3.86E-07 .6.04E-05 2.67E-05 Pr-144 5.37E-12 2.20E-12 2.72E-13 No Data" 1.26E-12. 2.19E-07 2.94E-14 s Nd-147- 9.83E-07 1.07E-06 6.41E-08 No Data- 6.28E-07 4.65E-05 2.28E-05 W-187 1.50E-09 1.22E-09 4.29E-10 No Data. No Data- 5.92E-06. 2.21E-05 , Wp-239 4.23E-08 3.99E-09 2.21E-09 No Data 1.25E-08 8.11E-06 1.65E-05 i i i i BN1-11600.02-100 3 of 3 Revision 1 - August 1983 i
i SWPS-1 ODCM TABLE 3.5-3 INHALATION DOSE FACTORS FOR CHILD i (mrem per pCi inhaled) ; i Radio- . nuclide Bone Liver T. Body Thyroid Kidney Lung _ GI-LLI , H-3 No Data 3.04E-07 3.04E-07 3.04E-07 3.04E-07 3.04E-07 3.d4E-07 C-14 9.70E-06 1.82E-06 1.82E-06 1.82E-06 1.82E-06 1.82E-06 1.82E-06 Na-24 4.35E-06 4.35E-06 4.35E-06 4.35E-06 4.35E-06 4.35E-06 4.35E-06 P-32 7.04E-04 3.09E-05 2.67E-05 No Data No Data No Data 1.14E-05 Cr-51 No Data No Data 4.17E-08 2.31E-08 6.57E-09 4.59E-06 2.93E-07 i Mn-54 No Data 1.16E-05 2.57E No Data 2.71E-06 4.26E-04 6.19E-06 . Mn-56 No Data 4.48E-10 8.43E-11 No Data 4.52E-10 3.55E-06 3.33E-05 t Fe-55 1.28E-05 6.80E-06 2.10E-06 No Data No Data 3.00E-05 7.75E-07 Fe-59 5.59E-06 9.04E-06 4.51E-06 No Data No Data 3.43E-04 1.91E-05 ! Co-58 No Data 4.79E-07 8.55E-07 No Data No Data 2.99E-0* 9.29E-06 Co-60 No Data 3.55E-06 6.12E-06 No Data No Data 1.91E-f 2.60E-05 Ni-63 2.22E-04 1.25E-05 7.56E-06 No Data No Data 7.43E-05 1.71E-06 Ni-65 8.08E-10 7.99E-11' 4.44E-11 No Data No Data 2.21E-06 2.27E-05 i Cu-64 No Data 5.39E-10 2.90E-10 No Data 1.63E-09 2.59E-06 9.92E-06 i Zn-65 1.15E-05 3.06E-05 1.90E-05 No Data 1.93E-05 2.69E-04 4.41E-06 ! Zn-67 1.81E-11 2.61E-11 2.41E-12 No Data 1.58E-11 3.84E-07 2.75E-06 Br-83 No Data No Data 1.28E-07 No Data No Data No Data <1.00E-24 Br-84 No Data No Data 1.48E-07 No Data No Data No Data <1.00E-24 j Br-85 No Data No Data 6.84E-09 No Data No Data No Data <1.00E-24 i Rb-86 No Data 5.36E-05 3.09E-05 No Data No Data No Data 2.16E-06 i f Rb-88 No Data 1.52E-07 9.90E-08 No Data No Data No Data 4.66E-09 Rb-89 No Data 9.33E-08 7.83E-08 No Data No Data No Data 5.11E-10 ! Sr-89 1.62E-04 No Data' 4.66E-06 No Data No Data 5.83E-04 4.52E-05 Sr-90 2.73E-02 No Data 1.74E-03 No Data No Data '3.99E-03 9.28E-05 Sr-91 3.28E-08 No Data 1.24E-09 No Data No Data 1.44E-05 4.70E-05 Sr-92 3.54E-09 No Data 1.42E-10 No Data No Data 6.49E-06 6.55E-05 Y-90 1.11E-06 No Data 2.99E-08 No Data No Data 7.07E-05 7.24E-05 Y-91m 1.37E-10 No Data 4.98E-12 No Data No Data 7.60E-07 4.64E-07 Y-91 2.47E-04 No Data 6.59E-06 No Data No Data 7.10E-04 4.97E-05 Y-92 5.50E-09 No Data 1.57E-10 No Data No Data 6.46E-06 6.46E-05 Y-93 5.04E-08 No Data 1.38E-09 No Data No Data 2.01E-05 1.05E-04 ! 4 BN1-11600.02-101 1 of 3 Revision 1 - August 1983 a
t SWPS-1.0DCM l TABLE 3.5-3 (CONT'D) s Radio-l' nuc1ide Bone' Liver .T; Body . Thyroid. Kidney Lung GI-LLI' .[ Zr-95 '5.13E-05 1.13E-05 1.00E-05 No Data 1.61E-05 6.03E-04 1.65E-05 Zr-97 5'.07E-08 7.34E-09 4.32E-09 No Data 1.05E-08 3.06E-05 9.49E-05 '! Nb-95 6.35E-06 2.48E 1.77E-06 No Data 2.33E-06 .1.66E-04 1.00E-05 Mo-99 No Data 4.66E-08 1.15E-08 No Data 1.06E-07 3.66E-05 3.42E-05' i Tc-99m 4.81E-13 9.41E-13 1.56E-11 No Data 1.37E-11 2.57E-07 1.30E-06 Tc-101 2.19E-14 2.30E-14 2.91E-13 No' Data 3.92E-13 1.58E-07 4.41E-09 j Ru-103 7.55E-07 No Data 2.90E-07 No Data 1.90E-06 1.79E-04 1.21E-05 5 Ru-105 4.13E-10 No Data' 1.50E-10 No Data 3.63E-10 4.30E 2.69E-05 l
- Ru-106 3.68E No Data 4.57E-06 No Data 4.97E-05 3.87E-03 1.16E-04 '
- Ag-110m 4.56E-06 3.08E-06' 2.47E-06 No Data- 5.74E-06 1.48E-03 2.71E-05 Te-125m 1.82E-06 6.29E-07 2.47E-07 5.20E-07 No Data 1.29E-04 9.13E-06 Te-127m 6.72E-06 2.31E-06 8.16E-07 1.64E-06 1.72E-05 4.00E-04 1.93E-05 i t Te-127 7.49E-10 2.57E-10 1.65E-10 5.30E-10 1.91E-09 2.71E-06 1.52E-05 Te-129m 5.19E-06 1.85E-06 8.22E-07 1.71E-06 1.36E-05 4.76E-04 4.91E-05' Te-129 2.64E-11 9.45E-12 6.44E-12 1.93E-11 6.94E-11 7.93E-07 6.89E-06 r 4 Te-131m 3.63E-08 1.60E-08 1.37E-08 2.64E-08 1.08E-07 5.56E-05 8.32E-05 !
Te-131 5.87E-12 2.28E-12 1. '8E-12 4.59E-12 1.59E-11 5.55E-07 3.60E-07. ' Te-132 1.30E-07 7.36E-08 .7.12E-08 8.58E-08 4.79E-07 1.02E-04 3.72E-05 i 4 I-130 2.21E-06 4.43E-06 2.28E-06 4.99E-04 6.61E-06 No Data 1.38E-06 ; I-131 1.30E-05 1.30E-05 7.3/F-06 4.39E-03 2.13E-05 No Data 7.68E-07 ; I-132 5.72E-07 1.10E-06 5.07E-07 5.23E-05 1.69E-06 No Data 8.65E-07 i 1-133 4.48E-06 5.49E-06 2.08E-06 1.04E-03 9.13E-06 No Data 1.48E-06 i
- I-134 3.17E-07 5.84E-07 2.69E-07 1.37E-05 8.92E-07 No Data 2.58E-07 I-135 1.33E-06 2.36E-06 1.12E-06 2.14E-04 3.62E-06 No Data 1.20E-06 Cs-1.34 1.76E-04 2.74E-04 6.07E-05 No Data 8.93E-05 3.27E-05 1.04E-06
, Cs-136 1.76E-05 4.62E-05 3.14E-05 No Data 2 58E-05 3.93E-06 1.13E-06 Cs-137 2.45E-04 2.23E-04 3.47E-05 No Data 7.63E-05 2.81E-05 9.78E-07 i i Cs-138 1.71E-07 2.27E-07 1.50E-07 No Data 1.68E-07 1.84E-08 7.29E-08 1 Ba-139 4.98E-10 2.66F-13 1.45E-11 No Data 2.33E-13 1.56E-06 1.56E-05 ! Ba-140 2.00E-05 1.75E-08 1.17E-06 No Data 5.71E-09 4.71E-04 2.75E-05 ! Ba-141 5.29E-11 2.95E-14 1.72E-12 No Data 2.56E-14 7.89E-07 7.44E
- Ba-142 1.35E-11 9.73E-15 '7.54E-13 No Data 7.87E-15 4.44E-07 7.41E-10 i La-140 1.74E-07 6.08E-08 2.04E-08 No Data No Data 4.94E-05 6.10E-05 i La-142 3.50E-10 1.11E-10 '3.49E-11 No Data No' Data 2.35E-06 2.05E-05 i i
i BN1-11600.02-101 2 of 3 Revision 1 - August 1983 ,
'l
~
l ] SNPS-1 ODCM TABLE 3.5-3 (CONT *D) '! ~ Radio-nuclide . Bone Liver -T. Body Thyroid Kidney Lung GI-LLI Ce-141 1.06E-05 5.28E 7.83E-07 No Data 2.31E-06 1.47E-04' 1.53E-05 Ce-143 9.89E-08 5.37E-08 7.77E-09 No Data 2.26E-08 3.12E-05 3.44E Ce-144 1.83E-03 5.72E-04 9.77E-05 No Data 3.17E-04 3.23E-03 1.05E-04 Pr-143 4.99E-06 -1.50E-06 2.47E-07 No Data 8.11E 1.17E-04 2.63E-05 i Pr-144 1.61E 4.99E-12 8.10E-13 No Data 2.64E-12 4.23E-07 5.32E-08 Nd-147 2.92E-06 2.36E 1.84E-07 No Data 1.30E-06 8.87E-05 2.22F-05 W-187 4.41E-09 2.61E-09 1.17E No Data No Data 1.11E-05 -2.46E-05 , Hp-239 1.26E-07 9.04E-09 6.35E-09 No Data 2.63E-08 1.57E-05 1.73E-05 i n BN1-11600.02-101 3 of 3 Revision 1 - August.1983
SNPS-1 ODCM TABLE 3.5-4' INHALATION DOSE FACTORS FOR INFANT (mrem per pCi inhaled) Radio-nuclide Bone Liver T. Body Thyroid Kidney Lung GI-LLI-H-3 No Data 4.62E-07 4.62E-07 4.62E-07 4.62E-07 4.62E-07 4.62E C-7.4 1.89E-05 3.79E-06 3.79E-06 3.79E-06 3.79E-06 3.79E-06 3.79E-06 Na-24 7.54E-06 7.54E-06 7.54E-06 7.54E-06 7.54E-06 7.54E-06 7.54E-06 P-32 1.45E-03 8.03E-05 5.53E-05 No Data No Data No Data 1.15E-05 Cr-51 No Data No Data 6.39E-08 4.11E-08 9.45E-09 9.17E-06 2.55E-07 Mn-54 No Data 1.81E-05 3.56E-06 No Data 3.56E-06 7.14E-04 5.04E-06 Mn-56 No Data 1.10E-09 1.58E-10 No Data 7.86E-10 8.95E-06 5.12E-05 Fe-55 1.41E-05 8.39E-06 2.38E-06 No Data No Data 6.21E-05 7.82E-07 Fe-59 9.69E-06 1.68E-05 6.77E-06 No Data No Data 7.25E-04 1.77E-05 Co-58 No Data 8.71E-07 1.30E-06 No Data No Data 5.55E-04 7.95E-06 Co-60 No Data 5.73E-06 8.41E-06 No Data No Data 3.22E-03 2.28E-05 Ni-63 2.42E-04 1.46E-05 8.29E-06 No Data No Data 1.49E-04 1.73E-06 Ni-65 1.71E-09 2.03E-10 8.79E-11 No Data No Data 5.80E-06 3.58E-05 Cu-64 No Data 1.34E-09 5.53E-10 No Data 2.84E-09 6.64E-06 1.07E-05 Zn-65 1.38E-05 4.47E-05 2.22E-05 No Data 2.32E-05 4.62E-04 3.67E-05 Zn-69 3.85E-11 6.91E-11 5.13E-12 No Data 2.87E-11 1.05E-06 9.44E-06 Br-83 No Data No Data 2.72E-07 No Data No Data No Data <1.00E-24 Br-84 No Data No Data 2.86E-07 No Data No Data No Data <1.00E-24 Br-85 No Data No Data 1.46E-08 No Data No Data No Data <1.00E-24 Rb-86 No Data 1.36E-04 6.30E-05 No Data No Data 'No Data 2.17E-06 Rb-88 No Data 3.98E-07 2.05E-07 No Data No Data No Data 2.42E-07 Rb R9 No Data 2.29E-07 1.47E-07 No Data No Data No Data 4.87E-08 Sr-89 2.84E-04 No Data 8.15E-06 No Data No Data 1.45E-03 4.57E-05 Sr-90 2.92E-02 No Data 1.85E-03 No Data No Data 8.03E-03 9.36E-05 Sr-91 6.83E-08 No Data 2.47E-09 No Data No Data 3.76E-05 5.24E-05 Sr -ac 7.50E-09 No Data 2.79E-10 No Data No Data 1.70E-05 1.00E-04 Y-90 2.35E-06 No Data 6.30E-08 No Data No Data 1.92E-04 7.43E-05 Y-91m 2.91E-10 No Data 9.90E-12 No Data No Data 1.99E-06 1.68E-06 Y-91 4.20E-04 No Data 1.12E-05 No Data No Data 1.75E-03 5.02E-05 Y-92 1.17E-08 No Data 3.29E-10 No Data No Data 1.75E-05 9.04E-05 Y-93 1.07E-07 No Data 2.91E-09 No Data No Data 5.46E-05 1.19E-04 BN1-11600.02-102 1 of 3 Revision 1 - August 1983 l
SNPS-1 ODCM TABLE 3.5-4 (CONT'D). Radio-nuclide Bone Liver T. Body Thyroid Kidney Lung GI-LLI Zr-95 8.24E-05' 1.99E-05 1.45E-05 No Data 2.22E-05 1.25E-03 1.55E Zr-97 1.07E-07. 1.83E-08 8.36E-09 No Data 1.85E 7.88E-05 1.00E-04 Hb-95 1.12E-05 4.59E-06 2.70E-06 No Data 3.37E-06 3.42E-04 9.05E-06. Mo-99 No Data 1.18E-07 2.31E-08 No Data 1.89E-07 9.63E-05 3.48E-05' Tc-99m 9.98E-13 2.06E-12 2.66E-11 No Data 2.22E-11 5.79E-07 1.45E-06 Tc-101 4.65E-14; 5.88E-14 5.80E-13 No Data 6.99E-13 4.17E-07 6.03E-07 Ru-103 1.44E-06 No Data 4.85E-07 No Data 3.03E-06 3.94E-04 1.15E-05 Ru-105 8.74E-10 No Data 2.93E-10 No Data 6.42E-10 1.12E-05 3.46E-05 Ru-106 6.20E-05 No Data. 7.77E-06 No Data 7.61E-05 8.26E-03 1.17E-04 Ag-110m 7.13E-06 5.16E-06 3.57E-06 No Data 7.80E-06 2.62E-03 2.36E-05 Te-125m . 3.40E-06 .1.42E-06 4.70E-07 1.16E-06 No Data 3.19E-04 9.22E-06 Te-127m 1.19E 4.93E-06 '1.48E-06 3.48E-06 2.68E-05 9.37E-04 1.95E-05 Te-127 1.59E-09 6.81E-10 3.49E-10 1.32E-09 3.47E-09 7.39E-06 1.74E-05 Te-129m 1.01E-05 4.35E-06 1.59E-06 3.91E-06 2.27E-65 1.20E-03 4.93E Te-129 5.63E-11 .2.48E-11 1.34E-11 4.82E-11 1.25E-10 2.14E-06 1.88E-05 Te-131m 7.62E 3.93E-08 2.59E-08 6.38E-08 1.89E-07 1.42E-04 8.51E-05 le-131 1.24E-11 5.87E-12 3.57E-12 1.13E-11 2.85E-11 1.47E-06 5.87E-06 Te-132 2.66E-07 , 1.69E-07 1.26E-07 1.99E-07 7.39E-07 2.43E-04 3.15E-05 I-130 4.54E-06 9.91E-06 3.98E-06 1.14E-03 1.09E-05 No Data 1.42E-06 I-131 2.71E-05 3.17E-05 1.40E-05 1.06E-02 3.70E-05 No Data 7.56E-07 I-132 1.21E-06 2.53E-06' 8.99E-07 1.21E-04 2.82E-06 No Data 1.36E-06 I-133 9.46E-06 1.37E-05. 4.00E-06 2.54E-03 1.60E-05 No Data 1.54E-06 I-134 6.58E-07 1.34E-06 4.75E-07 3.18E-05 1.49E-06 No Data' 9.21E-07 I-135 2.76E-06 5.43E-06 1.98E-06 4.97E-04 6.05E-06 No Data 1.31E-06 Cs-134 2.83E-04 5.02E-04 5.32E-05 No Data 1.36E-04 5.69E-05 9.53E-07 Cs-136 3.45E 9.61E-05 3.78E-05 No Data 4.03E-05 8.40E-06 1.02E-06 Cs-137 3.92E-04 4.37E-04 3.25E-05 No Data 1.23E-04 5.09E-05 9.53E-07 Cs-138 3.61E-07 5.58E-07 2.84E-07 No Data 2.93E-07 4.67E-08 6.26E-07 Ba-139 1.06E-09 7.03E-13 3.07E-11 No Data 4.23E-13 4.25E-06 3.64E-05 Ba-140 4.00E-05 4.00E-08 2.07E-06 No Data 9.59E-09 1.14E-03 -2.74E-05 l Ba-141 1.12E-10 7.70E-14 3.55E-12 No Data 4.64E 2.12E-06 3.39E-06 Ba-142 v 2.84E-11 2.36E-14 1.40E-12 No Data 1.36E-14 1.11E-06 4.95E-07 La-140 3.61E-07 1.43E-07 3.68E-08 No Data No Data. 1.20E-04 6.06E-05 La-142 7.36E-10 2.69E-10 -6.46E-11 No Data No Data '5.87E-06 4.25E-05 BN1-11600.02-102 2 of 3 Revision 1 - August 1983
.y
SNPS-1 ODCM TABLE 3.5-4.(CONT'D) Radio-nuclide Bone. Liver- T. Body Thyroid Kidney' Lung GI-LLI te-141 1.98E-05 1.19E-05 1.42E-06 No Data 3.75E-06 3.69E-04 1.54E-05 Ce-143 2.09E-07 1.38E-07 1.58E-08 No Data 4.03E-08 8.30E-05 3.55E-05
-Ce-144 2.28E-03 8.65E-04 1.26E-04 No Data 3.84E-04 7.03E-03 1.06E Pr-143 1.00E-05 3.74E-06 4.99E-07 No Data 1.41E-06 3.09E-04 2.66E-05 Pr-144 3.42E-11 '1.32E-11 1.72E-12 No Data 4.80E-12 ,1.15E-06 3.06E-06 Nd-147 5.67E-06 5.81E-06 3.57E-07 No Data 2.2SE-06 2.30E-04 2.23E-05 W-187 9.26E-09, 6.44E-09 2.23E-09 No Data No Data 2.83E-05 2.54E-05 Np-239 2.65E-07 2.37E-08 1.34E-08 No Data 4.73E-08 4.25E-05 1.78E-05 l
l BN1-11600.02-102 3 of 3 Revision 1 - August 1983
SNPS-1 ODCM TABLE 3.5-5 1 RECOMMENDED VALUES FOR U,p TO BE USED FOR THE MAXIMUM EXPOSED INDIVIDUAL IN LIEU OF SITE-SPECIFIC DATA l Pathway Infant Child Teg Adult Fruits, vege-tables (kg/yr) {yggy N/A(7) 520 630 520 Leafy vege-tables (kg/yr) (1) N/A 26 42 64 l Milk (t/yr)(1) 330 330 400 310 Meat &p%try (kg/yr) N/A 41 65 110 l Fish (fresh or salt) (kg/yr)(3) N/A 6.9 16 21 Otherseg{90d (kg/yr' N/A 1.7 3.8 5 Drinkinp4yater (t/yr) 330 510 510 730 Shoreline rec-reation(4) (hr/yr) N/A 14 67 12 Inhalation (m3/yr) 1400(5) 3700(6) -8000(6) 8000(5) (1) Consumption rate obtained from Reference 19 for average individual and age prorated ~and maximized using techniques contained in Reference 10 of Regula-tory Guide 1.109, Rev 1, Oct.-1977. (2) Consists of the following (on a mass basis): 22% fruit, 54% vegetables (including leafy vegetables), and 24% grain. BN1-11600.02-112 1 of 2 Revision 3 - December 1983
.. .. . . . _ . . _ _ _ . _ . _ _ _ . . _ . . _ . _ . _ _ . - . ~ . _ -
SNPS-1 ODCM TABLE 3.5-5(CONT'D) (3) Consumption rate for adult obtained by averaging data from References 10 and 21-24 of Regulatory Guide 1.109, Rev. 1, Oct. 1977 and age-prorated using techniques contained in Reference 10. (4). Data obtained directly from Reference 10 of Regulatory Guide 1.109, Rev.1, Oct. 1977. (5) Data . obtained directly from Reference 20 of Regulatory Guide 1.109, Rev.1
-Oct. 1977.
(6) Inhalation rate derived from data provided in Reference 20 of Regulatory Guide 1.109. Rev. 1, Oct, 1977. (7) N/A indicates not applicable. p l l i l BN1-11600.02-112 2 of 2- Revision 3 - December 1983
. _ _ . . _ . _ . _ - _ . . _m _ . . . . . _ _ _ _ _ . . ~ _ . . _ _ . _ . _ . . . . . _ _ . .
SNPS-1 ODCM 1ABLE 3.5-6 STABLE ELEMENT TRANSFER DATA (1) 8 F (Cow) F Element Veg/ Soil Milk (d/1) Meat (d/kg) H 4.8E+00 1.0E-02 1.2E-02 C 5.5E+00 1.2E-02 3.1E-02 . Na 5.2E-02 4.0E-02(3) 3.0E-02 , P 1.1E400 2.5E-02 4.6E-02 Cr 2.5E-04 2.2E-03 2.4E-03 Mn 2.9E-02 2.5E-04 8.0E-04 Fe 6.6E-04 1.2E-03 4.0E-02 Co 9.4E-03 1.0E-03 1.3E-02 Ni 1.9E-02 6.7E-03 5.3E-02 Cu 1.2E-01 1.4E-02 8.0E-03 2n 4.0E-01 3.9E-02 3.0E-02 Rb- 1.3E-01 3.0E-02 3.1E-02 Sr 1.7E-02 8.0E-04(3) 6.0E-04 Y 2.6E-03 1.0E-05 4.6E-03 Zr 1.7E-04 5.0E-06 3.4E-02 Nb 9.4E-03 2.5E-03 2.8E-01 Mo 1.2E-01 7.5E-03 8.0E-03 Tc 2.5E-01 2.5E-02 4.0E-01 Ru 5.0E-02 1.0E-06 4.0E-01 Rh 1.3E-01 1.0E-02 1.5E-03 Ag 1.5E-01 -5.0E-02 1.7E-02 Te 1.3E-00 1.0E-03 7.7E-02 1 2.0E-02 6.0E-03 2.9E-03 Cs 1.0E-02 1.2E-02 4.0E-03 Ba 5.0E-03. 4.0E-04(3) 3.2E-03 La 2.5E-03 5.0E-06 2.0E-04 Ce 2.5E-03 -1.0E-04(3) 1.2E-03 Pr 2.5E-03 5.0E-06 4.7E-03 ' Nd 2.4E-03 5.0E-06 3.3E-03 W 1.8E-02 5.0E-04 1.3E-03
- Np 2.5E-03 5.0E-06 2.0E-04(5) l II.I Data presented in this- table is from Reference 1 of Regulatory Guide 1.109, j
Rev. 1, Oct. 1977. I Meat and milk coefficients are based on specific activity considerations, f 4) From SeeReference 15 of Regulatory Guide 1.109, Rev.1, Oct.1977. text .(Reg'ulatory Guide 1.109, .Rev.1, Oct.1977).. (5) From Reference 13 of Regulatory- Guide 1.109, Rev.1, Oct.1977. BN1-11600-112 1 of 1 Revision 1 - August 1983
L SNPS-1 ODCMJ
-TABLE _3.5 HUMIDITY PARAMETERS AT RECEPTORS
~ Monthly Average Absolute Humidity (gm/m3)
January 3.06 February 3.09 , March 3.83 April - 5.71 May 8.19 June 12.62
- July 15.53 August 14.62 September 11.68 October 8.11 November 5.37 December 3.73 BN1-11600-112 1 of 1 Revision 1 - August 1983 f
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3 -l SMPS-1 ODCM 7-TABLE 3.5-9 (CONT'D) Nuclide Bone Liver , T. Body Thyroid Kidney Luna GI-LLI i PR-143 1.4E+05 4.2E+04 6.8E+03 -- 2.3E+04 - 1.5E+08 l PR-144 1.8E+03 1.8E403 1.OE403 1.8E+03 1.8E+03 1.8E+03 1.8E+03
- ND-147 ' 8.5E4 36 8.5E+06~ 8.4E&O6 8.4E+06 '
8.4E+06 8.4E+06 9.5E+07 ! W-187 2.5E+06 2.4E+06 2.4E+06 2.4E+06 2.4E+06 2.4E+06- 7.6E+06 NP-239 1.7E+06 1.7E+06 1.7E+06 1.7E+06 1.7E+06 1.7E+06 1.5E+07 1 (I) The dash (-) indicates insufficient data or that the dose factor is <1.0E- 20. i i I 1 l 3 [ i I i j l 1-d- l V i 1 4 i BN1-11600-117 3 of 3 Revision 3 - December 1983 1
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c 4 ONN.ON@OWNOWWWMNONvMmWOVMNNMNONNm e e e e e e e e e e e e e e e e e e e e e e o e e e e e e e MMNmMNmMMMmM4MN4NMNNMM4MWNmMWN@M U i M
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I-SNPS-1 ODCM [ - TABLE 3.5-10 (CONT'D) i Nuclide Bone Liver T. Body Thyroid Kidney Lunpq GI-LLI l 1 r o - i- ND-147 ..2.1E+02 1.7E+02 1.3E+01 - 9.1E+01 - 2.6E+05 W-187 1.4E+04 8.3E+03 3.7E+03 - - - 1.2E+06 l NP-239 . 8.3E+00 6.0E-01 4.2E-01 - 1.7E400 - 4.4E+04 i !. [ t i i i !,. II) The dash (-) indicates insufficient data or that the dose factor-is <1.0E- 20. I i i -! ? ? ! 1 i i 1- r i i I i; I l I I 4 f i i i I f L !
- BN1-11600-118 3 of 3 Revision 3 - December 1983 l 1 ;
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o M M W t3 M M m Ch W W m W (n W 00 N M CQ M CO e4 N 00 00000000000 O OO C3 L + + + 4 +++++ 1 + + + + + e J 0 WW WWWWWWWWWWW W WW M N *-4 Z - .e- e e me60e Oee=e e eCO e CO e eNee-4 e N CO M. N. N. W. L) eJ lmN 4 e4 N et ed to N M vi 4 N 4 I et i I I i 1 0 0 8 I et e-4 4 in C m LA Ch ** C0 M Ch M tn e 4 O M in N N M O C e-4 CO OO CO OMO ONOOOOO i + + + + + 1 + + + + + + + 1 + 1 I + 1 0 WWWe WW WW WW W W W W W l4J W W W W W C O N ** M nn 0 - NM Ch O - M et l':) N 0) CO e e in e 4 M e4 O e e ow e e * *
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O 0 E EE E O ! E @ t E M in AD O tt m N N Ch Ch e4 N et 40 N m O O N e-4 M ** M en e Ln Ch Ch O O O e-e N N N N N N M M C e=e N M et Ln M M M M st et et et e,t et et c4 e Ch Ch Ch e-4 e-4 e=* e4 e=4 e=4 e-4 M e-4 e-4 c-4 e=e M M M M M M e=e e 4 c-e M c-e e=e M c-e e-4 e- e ew I. U 4- 4 4 4 0 t 8 I I I I I I I I e-4 v=4 M e 4 e=e e-4 4 -1 I I I I I I I 4-I e-o "3 . CD O O D l"3 D 0 CD W LM LM LaJ LM LM IM i 8 I I I I m m m a:C a:C a:t eg La 44 44 Ce z 5 E Z E H C4 EX CW *C m H H H H H 6-- H +=e e-o M *-4 *=e M U U U Co CQ . l J U U U CL CO
,gy,- , e vy --wN---r*rt'rMWF'wW*Td'79 w
SNPS-1 ODCM
' TABLE 3.5-11 (CONT'D)'
Nuclide- Bone Liver T. Body Thyroid Kidney Lung GI-LLI ND-147 2.5E+01 2.0E+01 1.5E+00 - 1.1E+01 - 3.2E+04 W-187 1.7E+03 1.0E+03 4.5E+02 - - - 1.4E+05 NP-239 1.0E+00. 7.2E-02 5.1E-02 - 2.1E-01 - 5.3E+03 (1) The dash (-) indicates insufficient data or that the dose factor *s <1.0E- 20. i I i i 4 j l
- BN1-11600-119 3 of 3 Revision 3 - December 1983 3,
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i p i :. SNPS-1 ODCM i !. .[ l TABLE 3.5-12.(CONT'D) .} !L i i i Nuclide ~ Bone Liver T. Body- Thyroid Kidney LunH GI-LLI l 8 -' i.' ND-147 5.4E+03 4.4E+03 3.4E+02 - 2.4E+03 - 6.9E+06 ! W-187 1.6E-02 9.7E 03- 4.4E-03 - - - 1.4E+00 [ NP-239 2.1E 1.5E-02 1.1E-02' -- 4.4E-02 - 1.1E+03 , I [ I t j' (1) The dash (-) indicates insufficient ' data or that the dose factor is <1.0E- 2C. t i l'; I a t i e i 1 l l l
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1 i 4 I l i i : i BN1-11600-120 3 of 3 Revision 3 - December 1983 ' k' i bN 6
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+ +++++ 1 + + + + s+ i + + + + 4 + + I ++ ++
W WWWW MMOQ WWWWWWWWWWWWWWWWWWWWWWWWWW e e e e e m4W4MNNNMmmOMm4@W4mMNmNMWm
- e o e e e e e- e e e e e o e e e e e e e e e e e e a W MMMN 1 4 1MNN@MmmmmMNWMmmMNMMMNMMM4N O V.
CO MMMmWNNMMMmWNmMMWN4CMONMMM4NWN
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C WW WWWWWWWWWWWWWWWWWWWWWWWWWWWWWW
@@ 'MmmOMMTONNWNON4NNMNmOmMMOMmmNW o e e e e e e e e e e e e o e e e e e e e o e e e e e e e e e e e m -MN IMMMMNNNNMNMMMM@MQ4NMmNNMN4MMM@
M N M 4 O O 0 E EE E E W V - EmmWO4mNNmmMN WWNmOONMMMM M e NmmmOOOMNNNNNNMMOMNM4mMMMM4444444 M
- @mmmMMMMMMMMMMMMMMMMMMMMMMMMMMMMM i U 4 1 6 8 8 1 8 4 4 i l I 4 t i lMMMMMM i l 4 l e 4 l i t t 4 M D NmOUDDDOMWWWWWWW i l I a l lMMM4444WWWE E m
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i SNPS-1 OD0s TABLE 3.5-13 (CONT *D) p. Nuclide Bone' liver T. Body . Thyroid Kidney Lung GI-LLI ND-147 ' 4.1E+02 4.2E+02 2.6E+01 - 1.6E+02 -- 2.6E+05 W-187 2.9E+04 2.1E+04 7.1E+03 - - - 1.2E+06 j NP-239 1.8E+01 1.6E+00 8.9E-01 - 3.1E+00 - 4.6E+04 4 j- ' {1) The dash (-) indicates insufficient data or that the dose factor is <1.0E- 20. p I i-l I l-1 l' i' 1 1 l' is i I a J i l BNI-11600-121 3 of 3 Revision 3'- December 1983 i i
M I CO 01 l
** t
@ En 01 Ln in e-4 et to to N @ O m m in N CO Ch tn e-4 et 40 Ln e 4 m et M N 000000000000000 OOOOOOMOOOOO L e + + ++ 4 + + + ++++ + + ++++ + + 4 + e+ +
.J t
J WWWWWWWWWWWWWWW CO ** N &n CO N LA e-4 4 et 01 M e 4 e=a N WWWWWWWWWWW+W e-4 an 01 N M 4 N m 0) O @ kn : l M e e e e e e e e e e e e e e e e e e o e e -e e e e e e < 0 CO Un e-4 N CO ** N e-4 m e* N N N M 01 1 M N e-4 m Ln an e-4 N m e-4 et N U b , 1 M , C I sn et Ln Ln o CP O OO *c-
+ + + + th C71 W W WW ** f C M M Che CO.
@ 3 e e QJ l N J 4 Ch Iee i IN@ l 1 e i I e e i t i I i i i i i e i e i Ca::
O-wb LA. . Ln ' hi M &n M *t CC M MN E O 000 000 QC i O 0 + ++ 4 + + + + 4 i M C LAJ WWW WWW .WW. m' V e-s NM@ CO @ N Ch O y = e= e e e e e e o e e W M i Ch 4Mme4 I I I e I i M @ et i i i I I I I I I i i Ch et D D W - , W He h - V m O Q M tt W %. C + + e=s . m e= L W W l OU >i M N M O me O .4 .C
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M W Q. -N ew p., J E 7: CO m s.C W W = G t- v et >< Ln in Ch M in et in LA @ N N N M CO N N CO CO O M e-a O N N M e-g N i ON V CI O+ O O O O O O O O O O O O O O Q Q e-40 0 0 00000 - OE o + ++ e+++++ i ++ + 4 ++++ e+ + 4 e+ e l.L to WWWWWWWWWWWWWWWWWWWWWW M e-o tn N at WWWWW e-* @ M *# M D) N CO N ** CO O ** Ch Ch N e-o c) e e e e e e e e e e e e e e e e e e e e e e o e e4 N e Ln e tn. CD.
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; TABLE 3.5-15 P;3 CHILD INHALATION AND INGESTION OF LEAFY AND STORED VEGETABLES DOSE RATE CONVERSION FACTORS (mrem per pCi) i i Nuclide Bone Liver T. Body Thyroid Kidney Luno GI-LLI l-i H-3 -
1.4E-6 1.4E-6 1.4E-6 1.4E-6 1.4E-6 1.4E-6 C-14* 9.6E-4 1.9E-4 1.9E 1.9E-4 1.9E-4 1.9E-4 1.9E-4 l L i . Note: } For short term releases such as from air removal pump or from contain: ant drywell purge vent C-14 values should be multiplied by 2. I f i i i i i } i .. BN1-11600-123 1 of 1 Revision 15 - January 1990 l' i
. .. . . . . _ . . . . _ _ . , , , . . . _ . . . . , . _ _ _ , . . . . _ . . . . , , _ _ _ . , . . . , . . _ _ __ . . _ . . . _.__._..___.-_._..-.I
4 4 } 'SNPS-1 ODCM i . TABLE 3.5-16 1 P ] gj 1 CHILD INGESTION.0F GOAT'S MILK DOSE RATE CONVERSION FACTORS (mrem per pCi) l' 1 l Nuclide Bone Liver T. Body Thyroid Kidney M GI-LLI l H-3 - 8.6E-7 8.6E-7 8.6E-7 8.6E-7 8.6E-7 8.6E-7
- j. C-14* 4.7E-4 8.9E-5 8.9E-5 8.9E-5 8.9E-5 8.9E-5 8.9E-5 i
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- BNI-11600-125 1 of 1 Revision 3 - December 1983 I'
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SNPS-1 ODCM 3.6 [No Longer in Use) I BN1-11600.02-Il2 11.3.6-1 Revision 17 - May 1991
i SNPS 1 ODCM } 3.7 TOTAL DOSL FOR THE URANIUM FUEL CYCLE To cortply with Section 3.11.4 of the REC which implements 40CFR190, radiation doses ; shall be limited as follows: The dose or dose _ commitment to a member of the public, due to releases of radioactivity and radiation, from uranium fuel cycle sources shall be limited to 25 mrem, or less, to the total body and/or any organ (except the thyroid, i which shall be limited to 75 mrem, or less), over any 12 consecutive months. 3./.1 Sources of Radiation and Radioactivity ! lhe uranium fuel cycle is defined in 40CFR190 to include:
- a. operations of milling of uranium ore,
- b. chemical conversion of uranium,
- c. isotopic enrichment of uranium,
- d. fabrication of uranium fuel, e.. generation of electricity by a nuclear power plant using uranium fuel, and-
- f. reprocessing of spent uranium fuel. ;
The_ maximum individual doses due to each of the processing facilities for items a, b, c, d, and f above are required to be less than 10CFR20 limits. _ Therefore, the dose contribution to any person living in the Shoreham service area uue to the above facilities, which are all more than 125 kilometers distance away, is expected to be negligible compared to 40CFR190 limits. - The only radiological source of concern will- be due to item e above. The nearest nuclear power plant using uranium fuel is more than 75 kilometers away. 1 3.7.2 Radiolooical Impact of Generation of Electricity The generation of electricity using a_ nuclear power plant results in radioactivity released in gaseous and liquid effluents. The' dose rate assessment of these is done in Section - 3.3. The radiological impact of direct- radiation (including skyshine) from the -The direct radiation measuring devices TLD-s (plant can- beare determined provided by by measurement. the Radiological Environmental l
~ Monitoring Program (REMP) and areystems) listed in Tables 5-1 and 5-4.-
Dose registered by the TLDs.will be added to tha doses calculated in Sections 3.1.1 (Dose From Liquid Effluent) and 3.5.1 (dose to-maximum individual due to inhalation-
' and ingestion from gaseous effluents) to determine the total body dose due to all sources of radiation in the uranium fuel cycle. l
\
BN1-11600.02-112 11.3.7-1 Revision 16 . July 1990 l
- , a -- - . - . - _ - - _ _ . - . - - _ _ - - . ~ . . - - - . - . = - . _ . ~
SNPS 1 ODCM L SECTION 4 METEOROLOGICAL AND HYDROLOGICAL PARAMETER,5 UflLIZED IN THE CALCULATION Of DO5ES
4.1 INTRODUCTION
This section specifies the liquid pathway dilution factor and the dispersion and deposition factors utilized for atmospheric releases. A description is given of the meteorological methodology and parameters utilized in the com-puterized method for atmospheric release. Critical locations for receptors and their respective dispersion and deposition factors are provided for the backup method for atmospheric releases, for liquid effluent pathways a calculated dilution factor of 8.85 is used if circulation water is utilized, if service water is in use the dilution factor is one (1.0). 4.2 PARAMETERS AND METHODOLOGY USED IN THE COMPUTERIZED METHOD 4.2.1 Meteorological Data Hourly average values (based upon 60 one-minute values) of temperature, wind speed, wind direction and temperature dif ference from the 33- and 150-ft levels of the Shoreham meteorological tower are used in the l computerized method, to determine X/Q and D/Q values at the locations given in Table 3.5.-8. 4.2.2 Long Term X/Q and D/0 Values Sector-average atmospheric cor dispersion factors (x/Q)b^ gamma dispersion factors (x/Q) gntrationand relative deposition factors (D are calculated every hour using 60 one-minute meteorological data values
, obtained from the meteorological tower. The methodology utilized is -l described in the report "Shorehem Nuclear Power Station- EM5P Sof tware (Rev.B.1)"(EntechEngineeringInc.,P104-R3,Section2.0, July 1983,by J. N. Hamawi). General site specific data values that may be required for the calculation of dispersion parameters are given in Table 4-2.
The basic methodology used to.obtain the (x/Q)b^ and D/Q values is the straight-line trajectory model with Gaussian dispersion described in Regulatory Guide 1.111, Rev.1. The list of selected options and varia-tions from the Regulatory Guide is as follows: (a) Plume depletion due to dry and wet depositions, as _ well_ as to enroute radioactive decay is conservatively _ ignored. BN1-11600.02-112 11.4-1 Revision 18 - May 1991
$NPS-1 ODCM (b) Plume recirculation is accounted for by making use of the conservative open terrain recirculation correction factors in Revision 0 of Reg. Guide
. 1.111, which are also used in the X00D0Q computer code (NUREG/CR-2919 August 1982).. (c) The atmospheric dispersion equations employed include terms to account for-the plume eddy reflections between the ground and an inversion layer aloft. The reflection model was based on Turner's ' Workbook of Atmos-pheric Dispersion Estimates', (USEPA, Publication AP-26,1970) and has i the additional capability of predicting the entire range of effects from no reflection to the attainment of uniform vertical concentration result-ing from multiple reflections. (d) According to Regulatory Guide 1.111, Rev.1, effluents can be considered to be ground-level releases, elevated releases, or mixed-modt releases depending on (a) the elevation of the release point above grade relative to the h619 ht of adjacent buildings: and (b) the effluent exit velocity relative to the speed of the prevailing wind during the period of inter- l est. At the Shoreham station, vent releases are assumed to be either at ground level or totally elevated. Conditions leading to a mixed mode ! release under Regulatory Guide 1.111, Rev. I criteria are conservatively assumed to result in a ground level release in the computerized method. (e) The wind speed at the release height is computed by subjecting the wind speed measured at the upper instrument level of the meteoroingical tower to the height dependent wind speed relationship in the X00D00 computer code (NUREG/CR-2919, August 1982); the same relationship is used to replace missing wind speed data at either the lower or upper instrument levels of the meteorological tower. (f) Sector- average (x/Q)SA values are not permitted to exceed the plume centerline values corresponding to the same atmospheric conditions, plume centerline values are computed using the equations in Regulatory Guide 1.145 Rev. I for non-meandering plumes, and the recirculation factor described in item (b) above. (9) Vertical plume standard deviations for Pasquill stability G(a (G)) are computed using the relationship between the stability classes
- F and G given in Reg. Guide 1.145. All o y values are limited to a maximum value of 1000 m.
F l BN1-11600.02-112 !!.4 2 Revision 18 - May 1991
SNPS-1-ODCM
-(h) Site specific, sector-and distance-dependent terrain heights are employed in connection with elevated releases. These terrain heights (as given in Table 3.5-8) represent the maximum heights between the release point and the _-locations where the concentrations are being calculated, in accord-ante with Regulatory Guide 1.111 Rev. 1.
(1) Relative deposition factors (D/Q) are calculated using the relative deposition rates given in Regulatory Gu4de 1.111 Rev.1 in graphical form; the height-dependent curves in the guide are used as follows: Calculated Effeetive Applicability Regulatory Height Range (m) faide1.111Rev.1 Curve 0 - 15 Ground-level releases 15 - 45 30-m releases 45 - 80 60-m releases
> 80 100-m releases In- addition to the atmospheric dispersion factors, the computerizYA method also computes certain " effective gammn dispersion factors" (X /Q) which permit evaluation (J external air and whole body doses from figte clouds of multi-energetic gamma sources. The basic definition of the X/Q was derived by expressing the finite-cloud dose rate equations in Regulatory Guide 1.109 in a fort identical to the standard dose rate equation for semi-infinite clouds. It includes the- 1 f unction of Appendix F of Regulatory Guide 1.109, and for large plume standard deviations its numerical value reduces to that of the standard yjQ. The gamma spectrum is representative of the actual nuclide mir in the effluent. The finite cloud model is employed * ' both ground-level and elevated releases. Recirculation correction and inversion layer reflec-tion are accounted for, and sector-average finite cloud values are not allowed to exceed -corresponding plume center-line values computed in accordance with the three-dimensional-G u sian puff model described by Slade (' Meteorology and Atomic Energy 1968', USAEC TID-24190, 1968, Sec. 7-5.2.2). -
4.3 PARAMETERS AND METHODOLOGY U3ED IN THE BACKUP METHOD For gaseous effluent pathways, Tsble 4-1 lists the critical locations for receptors and their respective dispersion and deposition factors. The
-atmospheric dispersion and deposition factorr, were calculated utilizing ShWham. onsite meteorological data for the 2-3 ear period of October' 1,1973 thiogh _ September 30, 1975, Regulatory Guide 1.111 Rev. O, March 1976, and Rev. 1, July 1977. Several X/Q values weie obtained from the Final Environmental Statement, NUREG-0285, dated October 1977, docket No. 50-322 (See Table 4-1).
BN1-11600-112 11.4-3 Revision 4 - August 1984 c _ _ _ _ - _ - _ _ _ _ _ - _ _ _ _ _ _ _ _
(. 1 1 GXM i l TABLE 4-1 GITICfL EGPim LOCATIG6 FOR GASEDL6 EFF1.tDIT CTLQ1ATIG6 E E E d 3.11.2.2 3.11.2.3 3.11.2.5 REC Section 3.'I.2.1 3.4 3.5 3.6 Sectims in this ibnual 3.3 Dose to any onpn d;e to Instantanew s Dose Rate to Quarterly and Annual Air Quarterly and Amual Limiting Criteria Doses d;e to Gum and Dose due to radioruclides other than Wie Body ard Skin de to Noble Gas and cbse to any orwn Beta radiation radioruclides other than fbble Gas for 31-day d;e to radionuclides other than ftbie Gas p2riod l Ntble Gas ftble Gas: 366 noters, ffE 457 mters, ESE t d reters, ifE 458 meters, ffE Distance and Direction of 1 Receptor frun the Plant 2 Ortyn: 458 neters, ifE Location of Highest Dose Locatim of Highest Dose Location of Highest Dose Location of Highest Dose [bscription of Location Pate Long Term (Annual Average) 3 6.6E-07 sec/m3 8.44E-07 sec/m3 (2) 1. T " sec/m3 (3) ..sJE-OS sec/m3 (3)
)
Atmospheric Dispersion 4 1.33E-06 sec/m3 Factor for Station Ventila-tionExhaustX/Qg i f 1 of 2 Revision 17 - M1y 1991 BN1-11600.02-109 N _ _ _ _ _}}