ML20216B307
| ML20216B307 | |
| Person / Time | |
|---|---|
| Site: | Haddam Neck File:Connecticut Yankee Atomic Power Co icon.png |
| Issue date: | 02/28/1997 |
| From: | CONNECTICUT YANKEE ATOMIC POWER CO. |
| To: | |
| Shared Package | |
| ML20216B297 | List: |
| References | |
| PROC-970228, NUDOCS 9805180029 | |
| Download: ML20216B307 (120) | |
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SECTION 11 OFFSITE DOSE i
CALCULATION MANUAL l
FOR THE HADDAM NECK Pl. ANT ]
DOCKET NO,50 213 l
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9805180029 980430 1 PDR ADOCK 05000213 R PDR February 1997 wuwm Revision 8
l 2/28/97 Revision 8 f-'
HADDAM NECK PLANT OFFSITE DOSE CALCULATION MANUAL TABLELOF CONTENTS !
jfC_TipN P & Q g NO., REV. NO. DATE A. INTRODUC1JON A-1 2 12/31/94 l
S. RESPONSIBILITIES B-1 2 12/31/94 C. LIQUID DOSE CALCULATIONS l
C.1 QUARTERLY DOSE CALCULATIONS
- a. Whole Dody Dose C-1 2 12/31/94
- b. Maximum Organ Dose C-1 2 12/31/94 C.2 ANNUAL DOSE CALCULATIONS
- a. Whole Body Dose C-2 2 12/31/94
- b. Maximum Organ Dose C-2 2 12/31/94 C.3 MONTHLY DOSE PROJECTIONS C-3 2 12/31/94 C-4 2 12/31/94 I C.4 QUARTERLY DOSE CALCULATIONS FOR ANNUAL RADIOACTIVE EFFLUENT REPORT C-4 2 12/31/94 i D .. GASEOUS DOSE CALCULATIONS D.1 10CFR20 LIMITS (" INSTANTANEOUS")
- a. Noble Gas Release Rate Umit D1 2 12/31/94
- b. lodine & Particulate Release Rate Umit D-2 3 4/15/95 D-3 3 4/15/95 D.2 10CFR50 APPENDIX l- NOBLE GAS LIMITS
- a. Quarterly Air Dose Umit Due to Noble Gases D-4 2 12/31/94 D-5 2 12/31/94
- b. Annual Air Dose Umit Due to Noble Gases D-5 2 12/31/94
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2/28/97 Rsvision 8
( HADDAM NECK PLANT OFFSITE DOSE CALCULATION MANUAL TABLE OF CONTENTS (Continued)
SECTION PAGE NO. REV. NO. E D.3 10CFR50 APPENDIXl-IODINE AND PARTICULATE DOSES
- a. Quarterly Organ Dose Limit D-6 2 2/1/93 D-7 2 2/1/93
- b. Annual Organ Dose Limit D-7 2 2/1/93 DA GASEOUS EFFLUENT MONTHLY DOSE PROJECTIONS
- a. Gaseous Radwaste Treatment System D-8 1 1/1/90
- b. Ventilation Releases D8 1 1/1/90 D-9 2 12/31/94 D.5 QUARTERLY DOSE CALCULATIONS FOR i ANNUAL RADIOACTIVE EFFLUENT REPORT D-9 2 12/31/94 D.6 COMPLIANCE WITH 40CFR190 LIMITS D-9 2 12/31/94 E. LIQUID MONITOR SETPOINTS E.1 TEST TANK DISCHARGE LINE MONITOR E-1 2 12/15/95 E.2 STEAM GENERATOR BLOWDOWN MONITOR E-2 1 1/1/90 E.3 SERVICE WATER RADIATION MONITOR E-2 1 1/1/90 E-3 1 1/1/90 F. GASEOUS MONITOR SETPOINTS F.1 STACK NOBLE GAS ACTIVITY MONITOR F-1 1 1/1/90 i
o4sixwast T of C - 2
2/28/97 Revision 8
(- HADDAM NECK PLANT OFFSITE DOSE CALCULATION MANUAL LIST OF TABLES AND FIGURES i
TABLE NO. TABLE NAME FAGE NO. REV. NO. QAIg 1 DOSE FACTORS FOR NOBLE GASES D-10 1 1/1/90 2 DOSE FACTORS ?OR IODINE &
PARTICULATES D-11 1 1/1/90 FIGURE NO. FIGURE NAME PAGE NO. REV. NO. A QATE G-1 INNER TERRESTRIAL MONITORING STATIONS APP. G-3 3 8/31/94 G-2 AQUATIC AND WELL WATER SAMPLING STATIONS APP, G-4 1 1/1/90 G-3 ACCIDENT TLD SAMPLING LOCATIONS APP. G-5 1 1/1/90 l l
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- 2/28/97 Revision 8 HADDAM NECK PLANT
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OFFSITE DOSE CALCULATION MANUAL APPENDICES l
REV. NO. A QATE j APPENDIX A DERIVATION OF FACTORS FOR SECTION C.1.a 1 1/1/90 APPENDIX B DERIVATION OF FACTORS FOR SECTION C.1.b 1 1/1/90 APPENDIX C LIQUID DOSE CALCULATIONS - LADTAP 1 1/1/90 l APPENDIX D DERIVATION OF FACTORS FOR SECTION D.1 3 4/15/95 APPENDIX E GASEOUS DOSE CALCULATIONS - GASPAR 1 1/1/90 APPENDIX F DERIVATION OF FACTORS FOR SECTIONS D.2 & D.3 2 2/1/93 APPENDIX G ENVIRONMENTAL MONITORING PROGRAM-SAMPLING LOCATIONS 5 2/28/97 I 1
i APPENDIX H DERIVATION OF FACTORS FOR TABLE 2 1 1/1/90 l
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2/28/97 Ravision 5 APPEPDIX G
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ENVIRONMENTAL MONITORING PROGRAM Samplina Locations The following lists the environmental sampling locations and the types of samples obtained at each location. Sampling locations are also shown on Figures G-1, and G-2,.
! Location Direction & Distance
! Number From Nams Sample Tvoes l Release Point *"
1 -l* On-site-Mouth of Discharge Canal 1.1 Mi, ESE TLD 21 Haddam-Park Rd. 0.8 Mi,S TLD 3-1 Haddam-Jail Hill Rd. 0.8 Mi, WSW TLD 4-1 Haddam-Ranger Rd. 1.8 Mi, SW TLD, Air Particulate 5-1 On-site-Injun Hollow Rd. 0.4 Mi, NW TLD, Air Particulate
, 6-1 On-srte-Substation 0.5 Mi, NE TLD, Air Particulate, Vegetation
! 7-1 Haddam 1.8 Mi, SE TLD, Air Particulate l 8-l East Haddam 3.1 Mi, ESE TLD, Air Particulate 91 Higganum 4.3 Mi, WNW TLD, Air Particulate 10-f Hurd Park Rd. 2.8 Mi, NNW TLD 11-C" Middletown 9.0 Mi, NW TLD 12-C Deep River 7.1 Mi, SSE TLD 13-C North Madison 12.5 MI, SW TLD, Air Particulate l l 4 14-C Colchester 10.5 Mi, NE TLD 15-1 On-site Wells 0.5 MI, ESE"" WellWater 16-C Well-State Highway Dept. E. Haddam 2.8 Mi, SE Well Water 17 C Fruits & Vegetables Beyond 10 Miles Vegetation 18-l Site Boundary 0.4 MI, NW Vegetation 19-1 Cow Location #1 5.5 Mi, ENE Milk 20-1 Cow Location #2 6.9 Mi, NW Milk 21-1 Cow Location #3 8.0 Mi, WNW Milk 22-C Cow Location #4 11.0 Mi, ENE Milk l 23-C Goat Location #1 12.0 MI, S Milk l l 24-1 Goat Location #2 4.5 Mi, N Milk i 25-1 Fruits & Vegetables Within 10 Miles Vegetation
- 26-1 Conn. River-Near intake 1.0 Mi, WNW Fish l 27-C . Conn. River Higganum Light 4.0 Mi, WNW Shellfish 1.8 Mi, SE ]
28-l Conn. River-E. Haddam Bridge Bottom Sediment, River Water 1 29-1 Vicinity of Discharge _ _ _ _ , _
Bottom Sediment, Fish l l 30-C Conn. River-Middletown 9.0 Mi, NW River Water, Bottom Sediment ;
7.6 Mi, NW Fish ;
l 31-1 Mouth of Salmon River 0.8 Mi, ESE Shellfish ,
l *l = Indicator "C = Control I
- "*The release points are the stack for terrestial locations and the end of the discharge canal for aquatic locations..
""Naw wells at 0.4 miles SE may be used as a replacement for this location.
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_ RADIOLOGICAL ENVIRONMENTAL REVIEW for ODCM Change 97-9 CY Offsite Dose Calculation Manual (Section II, REMODCM)
The proposed changes to the CY ODCM are to Appendix G, EnvironmentalMonitoring Program Sampling Locations. The following changes are being made:
- 1. Prior to this change. Figures G-1, G-2 and G 3 did not contain the ODCM revision date or revision number. Each was updated.
- 2. The Accident TLD Sampling Locations were updated to reflect current locations. Two REMP stations were incorrectly listed as accident sampling stations and were removed from the list.
- 3. The distances and directions to existing cow and goat farm sampling locations 19 and 24 were updated with new estimates from a current reevaluation and review.
- 4. Two indicator cow farms and one control goat farm listed as locations 20,21 and 24C went out of business and were replaced with appropriate alternate farms. These replacement farms were chosen by reviewing the most recent 1996 bnd Use Census and satisfying the sampling criteria as specified in the REMM. 1 Changes 1-3 satisfy NRC and QAS audit recommendations.
The two replacement cow milk locations, locations 20 and 21, are located 8 miles Northeast and 11 miles Southeast, respectively. The latest three year averaged D/Q data was reviewed in
{ conjunction with all possible alternate farms to determine the best farm locations to sample as indicators of plant activities and releases.
The new replacement goat milk farm used as a control location in the Haddam Neck Radiological Environmental Monitoring Program, location 23C, is located 16 miles North-Northeast. This location satisfies the criteria for a control station.
The proposed changes do not constitute an unreviewed radiological enviro.tmental impact. A determination has been made that the change will maintain the level of re.dioactive effluent l
control required by 10CFR20.106,40CFR190,10CFR50.36a, and Appendix I to 10CFR50 and l not adversely impact the accuracy or reliability of effluent, dose, or setpoint calculations.
Prepared by: -
f/#[97 g W. J Eakin, Sr. Eng.
R diological Engineering Reviewed by:
j ukbSk/n R. A. Crandall, Supervis'or Radiological Engineering I
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I SECBDR11 l
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OFFSITE DOSE CALCULATION MANUAL FOR THE j HADDAM NECK PLANT DOCKET NO. 50 213 l
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- May 1997 c4eimoet.coe Revision 9
5/30/97 Rsvision 9 g_ HADDAM NECK PLANT OFFSITE DOSE CALCULATION MANUAL TABLE OF CONTENTS SECTION PAGE NO. REV.NO. Q6.IE A. INTRODUCTION A-1 2 12/31/94 B. RESPONSIBILITIES B-1 2 12/31/94 C. LIQUID DOSE CALCULATIONS C.1 QUARTERLY DOSE CALCULATIONS
- a. Whole Body Dose C-1 2 12/31/94
- b. Maximum Organ Dose C-1 2 12/31/94 C.2 ANNUAL DOSE CALCULATIONS
- a. Whole Body Dose C-2 2 12/31/94
- b. Maximum Organ Dose C-2 2 12/31/94 C.3 MONTHLY DOSE PROJECTIONS C-3 2 12/31/94 C-4 2 12/31/94 C.4 QUARTERLY DOSE CALCULATIONS FOR e WUAL RADJOACTIVE EFFLUu.NT REPC/AT C-4 2 12/31/94 D. GASEOUS DOSE CALCULATIONS D.1 10CFR20 LIMITS (" INSTANTANEOUS")
l a. Noble Gas Release Rate Umit D-1 2 12/31/94 l b. lodine & Particulate Release l
Rate Limit D-2 3 4/15/95 l D-3 3 4/15/95 l D.2 10CFR50 APPENDIX l- NOBLE GAS LIMITS l
- a. Quarterly Air Dose Limit Due to Noble Gases D-4 2 12/31/94 D-5 2 12/31/94
- b. Annual Air Dose Limit Due to Noble Gases D-5 2 12/31/94 i
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5/30/97 Rsvision 9 HADDAM NECK P.'. ANT OFFSITE DOSE CALCULATION MANUAL TABLE OF CONTENTS (Continued)
SECTION PAGE NO. REV. NO. DAIG D.3 10CFR50 APPENDIX l-IODINE AND l PARTICULATE DOSES
- a. Quarterly Organ Dose Limit D-6 2 2/1/93 D-7 2 2/1/93 l b. Annual Organ Dose Limit D-7 2 2/1/93 D.4 GASEOUS EFFLUENT MONTHLY DOSE PROJECTIONS
- a. Gaseous Radwaste Treatment System D-8 1 1/1/90
- b. Ventilation Releases D-8 1 1/1/90 D-9 2 12/31/94 L'.5 QUARTERLY DOSE CALCULATIONS FOR ANNUAL RADIOACTIVE EFFLUENT REPORT D-9 2 12/31/94 D.6 COMPLIANCE WITH 40CFR190 LIMITS D9 2 12/31/94 E. LIQUID MONITOR SETPOINTS i
E.1 TEST TANK DISCHARGE LINE MONITOR E-1 2 12/15/95 E.2 STEAM GENERATOR BLOWDOWN MONITOR E-2 1 1/1/90 E.3 SERVICE WATER RADIATION MONITOR E2 1 1/1/90 E3 1 1/1/90 F. GASEOUS MONITOR SETPOINTS I F.1 STACK NOBLE GAS ACTIVITY MONITOR F-1 1 1/1/90 l
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5/30/97 Rsvision 9
_ HADDAM NECK PLANT OFFSITE DOSE CALCULATION MANUAL 1
LIST OF TABLES AND FIGURES
.!i BLE NO. TABLE NAME PAGE NO. REV. NO. DATE l DOSE FACTORS FOR NOBLE GASES D-10
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1 1 1/1/90 l
2 DOSE FACTORS FOR IODINE &
PARTICULATES D-11 1 1/1/90 1
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FIGURE NO. FIGURE NAME PAGE NO. REV. NO. DATE G-1 INNER TERRESTRIAL MONITORING STATIONS APP. G-3 4 5/30/97 I l
G-2 AQUATIC AND WELL WATER SAMPLING STATIONS APP. G-4 2 5/30/97 G-3 ACCIDENT TLD SAMPLING LOCATIONS APP. G-5 2 5/30/97 l
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r 5/30/97 Rsvision 9 HADDAM NECK PLANT OFFSITE DOSE CALCULATION MANUAL APPENDICES l
REV. NO. DAI,g 1
APPENDIX A DERIVATION OF FACTORS FOR SECTION C.1.a 1 1/1/90 l APPENDIX B DERIVATION OF FACTORS FOR SECTION C.1.b 1 1/1/90 l APPENDIX C LIQUID DOSE CALCULATIONS - LADTAP 1 1/1/90 APPENDIX D DERtVATION OF FACTORS FOR SECTION D.1 3 4/15/95 APPENDIX E GASEOUS DOSE CALCULATIONS - GASPAR 1 1/1/90 APPENDIX F DERIVATION OF FACTORS FOR SECTIONS D.2 & O.3 2 2/1/93 l APPENDIX G ENVIRONMENTAL MONITORING PROGRAM-SAMPLING LOCATIONS 6 5/30/97 APPENDIX H DERIVATION OF FACTORS FOR TABLE 2 1 1/1/90 i
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1 l APPENDIX G l (--
ENVIRONMENTAL MONITORING PROGRAM l
l Samolina Locations
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The following lists the environmental sampling locations and the types of samples obtained at each location, Sampling locations are also shown on Figures G 1, and G-2,.
Location Direction & Distance Number Name From Samole Tvoes Release Point ***
1 -l* On site-Mouth of Discharge Canal 1.1 Mi, ESE TLD 2-1 Haddam-Park Rd. 0.8 Mi,S TLD 3-1 Haddam-Jail Hill Rd. 0 9 Mi. WSW TLD 41 Haddam-Ranger Rd. 1.8 Mi, SW TLD, Air Particulate 51 On site Injun Hollow Rd. 0.4 Mi, NW TLD, Air Particulate 6-1 On-site Substation 0.5 MI, NE TLD, Air Particulate, Vegetation 7l Haddam 1.8 Mi, SE TLD, Air Particulate 8-l East Haddam 3.1 Mi, ESE TLD, Air Particulate 91 Higganum 4.3 Mi, WNW TLD, Air Particulate 10-1 Hurd Park Rd. 2.8 Ml, NNW TLD 11 C" Middletown 9.0 Mi, NW TLD 12-C Deep River 7.1 Mi, SSE TLD 13 C North Madison 12.5 Mi, SW TLD, Air Particulate 14 C Colchester 10.5 Mi, NE TLD 15-1 On-site Wells 0.5 MI, ESE"" WellWater 16-C Well-State Highway Dept. E. Haddam 2.8 Mi, SE WellWater 17-C Fruits & Vegetables Beyond 10 Miles Vegetation 18 1 Site Boundary 0.4 Mi, NW Vegetation 191 Cow Location #1 6.5 Mi, ENE Milk 20 1 Cow Location #2 8.0 MI, NE Milk 21 1 Cow Location #3 11.0 Mi, SE Milk 22 C Cow Location #4 11.0 Mi, ENE Milk 23-C Goat Location #1 16.0 MI, NNE Milk 24 1 Goat Location #2 3.6 Mi, SSE Milk 251 Fruns & Vegetables Within 10 Miles Vegetation 26 1 Conn. River Near intake 1.0 Mi, WNW Fish 27 C Conn. River Higganum Light 4.0 MI, WNW Shellfish 28l Conn. River E. Haddam Bridge 1.8 Mi, SE Bottom Sediment, River Water 20-1 Vicinity of Discharge ______
Bottom Sediment, Fish 30-C Conn. River Middletown 9.0 Mi, NW River Water, Bottom Sediment 7.6 Mi, NW Fish 31 1 Mouth of Salmon River 0.8 Mi, ESE Shellfish
- l = Indicator "C = Control
'"The release points are the stack for terrestiallocations and the end of the discharge canal for aquatic locations..
""New wells at 0.4 miles SE may be used as a replacement for this location.
l APP. G-1 om xwoetooc E
5/30/97 Revision 6 The following lists the accident TLD sampling locations. Sampling locations are shown on
- ~
Figure G-3.
ACCIDENT TLD SAMPLING LOCATIONS Direction and Distance Location Description (Town and Street) l l 0.8 Mi,N Haddam Neck, Cove Road j 4.0 Mi, N East Haddam, Quitewood Road and Route 196 0.7 Mi, NNE Haddam Neck, Jtinks Hill Road 2.6 Mi, NNE Leesville Substation, Intersection of 151 and 196 l 4.8 Mi, NE Colchester, Waterhele Road 0.3 Mi, ENE Haddam Neck, Jenks Hill Road 4.4 Mi, ENE East Haddam, Falls Bashen Road 0.3 Mi, E Haddam Neck, Road to Canal 4.4 Mi, E East Haddam, Smith Road 2.8 Mi, SE East Haddam, Creamery Road (off Route 82) 0.9 Mi, SSE Haddata, Route 9A, Comer of Plains Road 3.2 Mi, SSE Haddam, Old Chester Road 3.1 Mi, S Haddam, int. Turkey Hill and Dickinson Road 0.7 Mi, SSW Haddam, Route 9A, Parking Lot Agr. Building 5.2 Mi, SSW Killingworth, Parker Hill Road 0.7 Mi, SW Haddam, Route 9A, Quarry Hill Road 4.0 Mi, SW Haddam, Route 81, North of Woods Road 3.2 Mi, WSW Haddam, Route 81, after Route 9 Underpass 0.9 Mi, W Haddam, Route 9A, South End of Walkely Hill 1.1 Mi, W Haddam, Island Dock Road ,
4.6 Mi, W Haddam, Spencer Road l 1.2 Mi, WNW Haddam, Route 9A, North of Town Dump 0.7 Mi, NW Haddam Neck, injun Hollow Road j i
4.6 Mi, NW Middletown, Maromas Meteorological Tower l
l 1.0 Mi, NNW Haddam Neck, Ague Spring Road l
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RADIOLOGICAL ENVIRONMENTAL REVIEW 4 l
l For Haddam Neck ODCM Change #97-5 {
Section E.1, " Test Tank Discharge Line Monitor" Section E.3, " Service Water Radiation Monitor" DESCRIPTION OF CHANGES The following revisions to Section II.E of the Haddam Neck Radiological Effluent Monitoring and Offsite Dose Calculation Manual have been made:
- 1. Subsection E.1," Test Tank Discharge Line Monitor"
- a. Corrected typographical errors.
- b. In Step 1 reformatted the equation for the required reduction factor, R.
- c. In Step 1 added an asterisk note that the 10CFR20 version prior to January 1,1992 applies.
- d. Notes in Steps 2,3, and 5 were numbered and moved to the end of Subsection E.1. ,
- e. In Step 3 the word " maximum" was added.
- f. In Step 4 the subscript "y" was added to show that only gamma emitters are considered for monitor setpoint. Also in Step 4, wording was added to describe the parameters Ay and Cg.
- g. Note 3 was added for Step 4. The note explains that the purpose of the setpoint is to verify Chemistry sample representativeness and that the allowed discharge flow prevents exceedance of non-gamma emitter MPCs.
- h. In Step 5 the current monitor efficiency, E, is used instead of the latest monitor i calibration curve to determine a monitor response corresponding to two times the Chemistry sample results.
- i. In Step 5 a formula was added for determining altemate setpoint based on two times the Chemistry sample. The alternate setpoint based on 3.7 x 10" Ci/ml was taken from Step 5 and put in a new Step 6 and a formula added to determine it.
- j. The fimal action for setpoint determination of background addition was removed from Step 5 and put in a new Step 7.
- k. In Step 7 instead of forcing the setpoint to the higher of the two altematives an option is given to use either setpoint.
- 1. Controls required when using the setpoint based on 3.7 x 10" pCi/ml were moved from the first paragraph and Note 2 in Step 5 to the end of Step 7.
- m. In Note 2 of Step 5 the value of I x 10'7 Ci/mi was changed to 3 x 10 pCi/ml and the words " Unidentified MPC" were changed to " Footnote 3.a, Appendix B, '
10CFR20."
- n. Step 6 was deleted.
- o. A required action when the monitor exceeds a specified background was added in Step 7.
I
- 2. Subsection E.3," Service Water Radiation Monitor"
- a. In Step I the factor of 0.7 for service water flow was removed. This increased '
credited flow from 4,200 to 6,000 gpm.
- b. In Step 3 added an asterisk note that the 10CFR20 version prior to January 1,1992 applies.
- c. In Step 3 the word " unidentified" was changed to " worst case" and Note I was added referencing Footnote 3.a, Appendix B,10CFR20. The value of I x 10'7 pCi/ml was changed to 3 x 10 pCi/ml (and in Step 4).
l d. Step 4 was changed from calculating the alarm setpoint to calculating the maximum
! allowable concentration (A) at the monitor. The process for determining the setpoint in Step 5 was expanded by first calculating the maximum allowable i
monitor response, R., and then, in a new Step 6, adding the background of the monitor,
- e. In Step 5 the current monitor efficiency, E, is used instead of the latest monitor calibration curve to determine the maximum allowable monitor response,
- f. In Step 6 two setpoints are now specified, one when performing a radwaste discharge with circulating water and one for all other times, t
- g. Note 2 was added to discuss safety margins against MPC limits.
- h. A required action when the monitor exceeds a specified background was added in Step 6 for times of discharging with circulating water and for all other times. Note 3 explains the maximum allowable background during times of no discharges.
PURPOSE OF CHANGES
- 1. Subsection E.1 changes:
- a. Typographic errors were corrected for clarity.
- b. Equation in Step I was reformatted for clarity.
- c. The NRC on January 1,1992 revised the regulations in 10CFR20," Standards for Protection Against Radiation" including the permissible concentrations for release to the environment in Appendix B of 10CFR20. These new regulations were never implemented for the instantaneous release rate limit by the NRC. j
- d. Notes were numbered and moved to the end of the section to make the whole i section easier to read.
- e. The word " maximum" was added to emphasize that the discharge flow must be limited to the value calculated in the ODCM. 1
- f. This change only clarifies that the radiation monitor responds only to gamma j emitters. There is no change to plant operations.
- g. This change only explains the purpose of the setpoint and that Chemistry sampling I ensures that non gamma emitter MPCs are satisfied. There is no change to plant l operations or procedures, j
- h. A calibration curve is not needed because the monitor efficiency is constant !
thrcughout it's operational range. This ODCM change only reflects the current !
method for converting monitor output of cpm to Ci/ml.
l
- i. Formulas and new steps were added to make the requirements easier to follow. '
f 2
l -- J. Background subtraction was put in a new step for ease of use.
- k. Allowing the option of using the lower setpoint makes the requirement more conservative. The option may be used ifit is desired to avoid the operational l requirements at the end of Step 7. l
- 1. Required operational controls were placed together at the end of Step 7 to make the requirements easier to read. i
- m. Footnote 3.a, Appendix B,10CFR20 (prior to 1992) reads:
"If the identity of each radionuclide in the mixture is known but the concentration '
of one or more of the radionuclides in the mixture is not know the concentration limit for the mixture is the limit in Appendix "B" for the radionuclide in the mixture having the lowest concentration limit."
The waste streams radionuclides are well characterized but concentrations for non-gamma emitters in each batch release are not known exactly. Therefore the limiting MPC is that for Sr-90, a non-gamma emitter, of 3 x 10 Ci/ml.
- n. The provisions of Step 6 (old) were never used and there is no need for the provisions during defueled conditions,
- o. Background of the radiation monitor needs to be limited to maintain sufficient sensitivity.
- 2. Subsection E.3 changes:
- a. Revision to FSAR Section 9.2 removed thejustification for using a 0.7 factor on the service water flow. Going from a 4,200 gpm credited flow to a 6,000 gpm l I
credited flow makes the setpoint more conservative (lower).
- b. The NRC on January 1,1992 revised the regulations in 10CFR20," Standards for Protection Against Radiation" including the permissible concentrations for release to the envircament in Appendix B of 10CFR20. These new regulations were never implemented for the instantaneous release rate limit by the NRC. j
- c. Footnote 3.a, Appendix B,10CFR20 (prior to 1992) reads:
"If the identity of each radionuclide in the mixture is known but the concentration of one or more of the radionuclides in the mixture is not know the concentration limit for the mixture is the limit in Appendix "B" for the radionuclide in the mixture having the lowest concentration limit."
The waste streams radionuclides are well characterized but concentrations for non-gamma emitters in each batch release are not known exactly. Therefore the limiting MPC is that for Sr-90, a non-gamma emitter, of 3 x 10 pCi/ml.
- d. Formulas and new steps were added and background subtraction was put in a new step to make the requirements easier to follow.
- e. A calibration curve is not needed because the monitor efficiency is constant throughout it's operational range. This ODCM change only reflects the current method for converting monitor output of cpm to Ci/ml.
- f. Two different setpoints, one during discharging and one at all other times, are needed because of different operating conditions which would make either setpoint I
incompatible during the opposing operating conditions. During discharge higher i know concentrations with a much higher circulating water dilution flow are present.
l
At all other times lower, but unknown, concentrations with only service water flow available for dilution are present.
- g. Because of a lack of circulating water flow the setpoint and monitor background have to be limited to ensure MPCs are not exceeded. This note was added to show the importance of setting the required setpoint and limiting background.
- h. Background of the radiation monitor needs to be limited to maintain suflicient sensitivity.
RADIONUCLIDES OF CONCERN !
The expected radionuclides shown in the table below. These radionuclides, except for H-3, are for secondary system liquid taken from Table 1.2.1-4 of" Demonstration of Compliance with 10CFR50, Appendix I (Part 2)" dated November 1,1976 (Ref.1).
Half-lives and Maximum Permissible Concentrations (MPCs) from 10CFR20 are listed ,
for each radionuclide. Because Haddam Neck is shutdown only radionuclides with half- !
lives of two years or greater will remain in any significant amount. Therefore only Cs-134, Cs-137, Fe-55, Co-60, Sr 90, and H 3 need to be considered.
ISOTOPE HALF-LIFE MPC (uCi/ml)
Cs-134 2 years 9-6 I Cs-137 30 years 2E-5 Mn-54 312 days 1E-4 Fe-55
- 2.7 years 8E-4 ,
Co-58 71 days 9E-5 {
- 12 years 3E-3
- beta emitters only Activity in the service water would be due to in leakage from other interfacing systems or, during times of discharge form radwaste tanks. Therefore the radionuclide concentration in the interfacing system or radwaste tank would be diluted in the service water inventory. The service water monitor would response to the gamma emitters of Cs-134, Cs-137, and Co-60. This allows the setpoint to be set to avoid MPC concentrations of gamma emitters. For the beta emitters of Fe-55, Sr-90, and H-3 asuitably conservative setpoint based on ratios of beta emitting radionuclide to gamma emitting radionuclide is needed. Of these non gamma (beta) emitters only tritium (H-3) is present in sufficient concentrations to approach it's MPC before a monitor alarm. As
( shown below the present concentrations of tritium are not high enough to cause the tritium MPC to be exceeded even without circulating water dilution flow.
4
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! !-~
! RADIOLOGICAL CONSEOUENCES OF CHANGES l Most of the changes are editorial and formatting changes designed to make the ODCM l
easier to read or to add basis information about ODCM requirements prior to this l revision. The only changes which are not editorial, a format change, or basis information l prior to revision are the following:
A. Monitor efficiency used instead of calibration change (1.h and 2.e).
B. Option allowed of using either one of two setpoints instead of requiring use of higher
, setpoint (l.k).
C. Setpoint for worst case condition is now based on 3 x 10 pCi/ml instead of I x 10
pCi/ml (1.m and 2.c).
D. Deletion of Step 6 (1.n).
E. Actions were added when monitor background exceeds a cenain value (l.o and 2.h).
F. Factor of 0.7 was removed for credited service water flow (2.a).
G. Different service water monitor setpoints for discharge and non-discharge modes of operation (2.f).
H. Note added for safety margin between setpoint and MPC limits (2.g).
Only A above does not have a potential affect on radiological discussion. Each of the other changes are discussed below.
I B. Option of using one of two setpoints Because the change allows the use of a lower setpoint when the previous revision required use of the higher setpoint the change is more conservative. The setpoint based on Chemistry sample is still the same. The setpoint based on worst case conditions is now slightly higher because it is based on 3 x 10 Ci/ml rather than of I x 10 Ci/ml.
See discussion for Change C below.
C. Setpoint now based on 3 x 10 Ci/ml This change is based on regulatory requirements in the footnotes to Appendix B of 10CFR20. The unidentified radionuclide MPC of I x 10 pCi/ml was from Footnote 3.b where the radionuclides being discharged are unknown but it is known that I-129, Ra-226, and Ra-228 are not present. Footnote 3.a is for the condition where all the radionuclides are known and the most restrictive MPC is used. With defueled conditions i
the radionuclides known to be in the radwaste streams will not change. The lowest MPC (for Sr-90) of all the known radionuclides of 3 x 10 Ci/mi can now be used. Using this MPC as the basis for Test Tank Discharge Line Monitor and the Service Water Monitor during discharges will limit discharges to below MPC for all radionuclides except for tritium under certain conditions (see consequences for Change H below).
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D. Deletion of Step 6 There is a safety margin of a factor of five between the radiation monitor setpoint and the MPC limit. Step 6 allowed the plant the flexibility ofreducing that margin ifneeded. If the step had been used and the whole margin taken away there still would have been a safety margin of a factor of two between allowed discharge flow and the MPC limit.
Because the plant never used this provision and there will be no need for it with the plant defueled the step has been deleted.
E. Actions for high background Limitations on background will ensure that the monitors will be sensitive enough to detect increased activity well before gamma emitter MPCs are exceeded. During discharges a larger background may be tolerated on the monitors because of the large dilution flow available from circulating water. Therefore a background as high as the monitor response used to determine the setpoint can be tolerated. During non-discharge conditions the service water monitor is expected to guard against a major leak into service water or an inadvertent discharge of a radwaste tank. With a setpoint of three times 7
background, a current background of 80 cpm, and a monitor efficiency of 9.45 x 10 cpm / Ci/mi the service water monitor would alarm on an increase of 1.7 x 10 Ci/ml. !
This is a factor of ten below the most restrictive gamma emitter MPC Cs-137. A background limit of 400 cpm would then ensure that the margin of safety between the alarm and the Cs-137 MPC is at least a factor of two. For consideration of tritium MFC see discussion for Change H below, F. Removal of 0.7 factor for credited service water flow The consequence of this change is to make the service water monitor setpoint during discharges lower which is more conservative. Moreover, using 6,000 gpm for service water flow makes Section E.3 consistent with Section E.1.
G. Discharge and non-discharge setpoints for service water monitor With present plant opeational configuration the circulating water pumps are not run except for radwaste discharges. This would have forced the service water monitor l setpoint to a epm corresponding to 1.7 x 10 pCi/ml. The monitor is not sensitive enough to see this level. Therefore during non-discharge conditions without circulating water the monitor setpoint is set as low as possible at three times background. For gamma emitting radionuclides this provides a safety margin of at least a factor of two, if the background is limited, and up to a safety margin of a factor of ten (see discussion for Change E above).
H. Safety margin between setpoints and MPC limits Tritium concentrations in the Spent Fuel Pool, the RCS, and the RWST are less than 0.1 Ci/ml. A leakage of 180 gpm in the service water flow of 6,000 gpm would be needed to cause the tritium MPC to be exceeded. This large of a leakage is not possible. The waste test tanks have tritium concentrations up to 0.01 Ci/ml and the recycle test tanks 1
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.. up to 0.2 pCi/ml. An inadvertent release of a radwaste tank without recirculating water would cause tritium concentrations of I x 10" and 2 x 10'3 Ci/ml for a release of a waste test tank and a recycle test tank, respectively. At present tritium concentration levels in the radwaste tanks the tritium MPC would not be exceeded. Although gamma emitter concentrations in the radwaste tanks could increase with system decontamination the tritium concentrations should decay away with the half-life of tritium and as tritium is lost through diffusion. System decontamination will not increase tritium concentrations as tritium is in solution and does not adhere to surfaces. See discussion of Change E above for consideration of gamme emitting radionuclides' MPCs.
CONCLUSIONS The proposed changes do not constitute an unreviewed radiological environmental impact. A determination has been made that the changes will maintain the level of radioactive effluent control required by 10CFR20.106,40CFR190,10CFR50.36a, and Appendix I to 10CFR50 and not adversely impact the accuracy or reliability of effluent, dose, or setpoint determinations.
l Prepared by: [/A4[4 Claulie Flory, Senior Scientiff b/M77 Approved by: dM4 2./f7 Ray Crandall, Supervisor, / '
Radiological Engineering l
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SECTION 11 l
I OFFSITE DOSE CALCULATION MANUAL FOR THE l I HADDAM NECK PLANT l
DOCKET NO. 50-213 l
June 1997 Revision 10
6/27/97 Revision 10
'( HADDAM NECK PLANT OFFSITE DOSE CALCULATION MANUAL IABLE OF CONTENTS SECTION PAGE NO. REV. NO2 DATE l
A. INTRODUCTION A-1 2 12/31/94 I I
B. RESPONSlRILITIES B-1 2 12/31/94 I C. LIQUID DOSE CA'LCULATIONS C.1 QUARTERLY DOSE CALCULATIONS l
- a. Whole Body D'ose C-1 2 12/31/94
- b. Maximum Organ Dose C-1 2 12/31/94 l C.2 ANNUAL DOSE CALCULATIONS l
- a. Whole Body Dose C-2 2 12/31/94 l( b. Maximum Organ Dose C-2 2 12/31/94 C.3 MONTHLY DOSE PROJECTIONS C-3 2 12/31/94 C-4 2 12/31/94 C.4 QUARTERLY DOSE CALCULATIONS FOR ANNUAL RADIOACTIVE EFFLUENT REPORT C-4 2 12/31/94 D. GASEOUS DOSE CALCULATIONS D.1 10CFR20 LIMITS (*lNSTANTANEOUS')
! a. Noble Gas Release Rate Limit D-1 2 12/31/94 l b. lodine & Particulate Release Rate Limit D-2 3 4/15/95 D-3 3 4/15/95 l D.2 10CFR50 APPENDIX l- NOBLE GAS LIMITS
- a. Quarterly Air Dose Limit Due to Noble Gases D-4 2 12/31/94 D-5 2 12/31/94
. b. Annual Air Dose Limit Due to i Noble Gases D-5 12/31/94 2
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6/27/97 RQuision 10
( HADDAM NECK PLANT OFFSITE DOSE CALCULATION MANUAL TABLE OF CONTENTS (Continued)
SEQILQN PA.GE NO. REV. NO. DAIG D.3 10CFR50 APPENDIX l-IODINE AND PARTICULATE DOSES
- a. Quarterly Organ Dose Limit D-6 2 2/1/93 D-7 2 2/1/93
- b. Annual Organ Dose Limit 0-7 2 2/1/93 D.4 GASEOUS EFFLUENT MONTHLY DOSE PROJECTIONS
- a. Gaseous Radwaste Treatment System D-8 1 1/1/90
- b. Ventilation Releases D-8 1 1/1/90 D-9 2 12/31/94 D.5 QUARTERLY DOSE CALCULATIONS FOR ANNUAL RADIOACTIVE EFFLUENT REPORT D-9 2 12/31/04 D.6 COMPLIANCE WITH 40CFR190 LIMITS D-9 2 12/31/94 E. LIQUID MONITOR SEI'PO1NTS E.1 TEST TANK DISCHARGE LINE MONITOR E-1 3 6/27/97 E-2 2 6/27/97 E2 STEAM GENERATOR BLOWDOWN MONITOR E-3 2 6/27/97 E.3 SERVICE WATER RADIATION MONITOR E-3 2 6/27/97 E-4 0 6/27/97 F. GASEOUS MONITOR SETPOINTS F.1 STACK NOBLE GAS ACTIVITY MONITOR F-1 1 1/1/90 l
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l 6/27/97 l R9 vision 10 HADDAM NECK PLANT OFFSITE DOSE CALCULATION MANUAL LIST OF TABLES AND FIGDBES TABLEtiQ TABLE NAME PAGE NO. REV. NO. DATE 1 DOSE FACTORS FOR NOBLE GASES D-10 1 1/1/90 2 DOSE FACTORS FOR IODINE &
PARTICULATES D-11 1 1/1/90 l
FIGURE NO. FIGURE NAME PAGE NO. REElla DATE G-1 INNER TERRESTRIAL MONITORING STATIONS APP. G-3 4 5/30/97
,( G-2 AQUATIC AND WELL WATER l SAMPLING STATIONS APP. G-4 2 5/30/97 G-3 ACCIDENT TLD SAMPLING LOCATIONS APP.G-5 2 5/30/97 l
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1 6/27/97 Revision 10
( HADDAM NECK PLANT l
OFFSITE DOSE CALCULATION MANUAL APPENDICGS ^
REV. NO. A PATE APPENDIX A DERIVATION OF FACTORS FOR SECTION C.1.a 1 1/1/90 APPENDIX B DERIVATION OF FACTORS FOR SECTION C.1.b 1 1/1/90 i
APPENDIX C LlOUID DOSE CALCULATIONS - LADTAP 1 1/1/90
! APPENDIX D DERIVATION OF FACTORS FOR SECTION D.1 3 4/15/95 l
APPENDIX E GASEOUS DOSE CALCULATIONS - GASPAR 1 1/1/90 l APPENDIX F DERIVATION OF FACTOR 3 FOR SECTIONS l D.2 & D.3 2 2/1/93 I APPENDIX G ENVIRONMENTAL MONITORING l PROGRAM SAMPLING LOCATIONS 6 5/30/97 APPENDIX H DERIVATION OF FACTORS FOR TABLE 2 1 1/1/90 l
nocu,m T of C - 4
06/27/97 Rev.3 l E. LIQUID MONITOR SETPOINTS i
E.1 Test Tank Discharae Line Monitor l The trip / alarm setting on the test tank discharge line monitor depends on dilution water flow, I
test tank discharge flow, the isotopic composition of the liquid to be discharged, the background count rate of the monitor and the efficiency of the monitor. Due to the variability l of these parameters, an alarm / trip setpoint will be determined prior to the release of each l batch. The following method will be used:
I Step i From the tank isotopic analysis and the MPC values for each identified nuclide, l determine the required reduction factor: )
i 1
R" (C,I MPC,)
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l R = required reduction factor
~
C, = concentration of nuclide I(pCi/ml)
, MPC, = MPC value (10CFR20*, AppendixB, Table 2, Column 2 for all nuclides except I
noble gases. For noble gases, use 2 x 10" pCi/mi) for nuclide i (pCi/ml)
- 10CFR20 version prior to January 1,1992.
(
Step 2 Determine the existing dilution flow, D:
D = # of Cire. Pumps running x 93,000 gpm + # of service water pumps x 0,000 gpm D = existing dilution flow 93,000 gpm = flow from 1 circulating water pump 6,000 gpm = flow from i service water pump (Note 1) l Step 3 Determine the maximum allowable discharge flow, F:
F = 0.1 x R x D (Note 2)
Step 4 Determine the total gamma concentration (A,) in the tank in pCl/ml:
A,(pCi/ml) = ICj Where A, is the total concentration of gamma emitters in the tank and C)s the concentration of gamma emitteri(Note 3).
3.13 9.5 Detennine the monitor response, R. in cpm corresponding to y a times the total concentration determined in Step 4 (Note 4):
i Rm = E x 2 x A, Where E is the current monitor efficiency in cpm per pCi/ml.
E-1
06/27/97 Rev.2
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Steo 6 Determine the monitor response for worst case conditions, R., in cpm (Note 5):
R. = E x (1 x 10)
Stoo 7 Determine the alarm trip setpoint, S, in cpm:
IF Rm > R :
S=R+B IF R > R. use either Option (1) or Option (2):
(1) S = Rm + B, or (2) *S = R, + B Where B = background of the monitor in epm. If background exceeds the monitor response (Rmor R.) calculated prior to discharge, the monitor must be decontaminated prior to use.
- If option (2) is used for alarm trip setpoint, perform the following:
- 1. independent valve verification;
- 2. controls to ensure that the allowable discharge flow is not exceeded, and
- 3. controls .o ensure that the dilution flow is maintained.
( Hg131:
- 1. The maximum capacity of the Service Water System is about 10,000 gpm for 2 or more pumps running. Although this could result in a potential non-conservative estimate of dilution flow, this is justified since there is a factor of five conservatism in the overall calculation methdology.
- 2. Discharging at this flow rate would yield a discharge concentration corresponding to 10%
of the Technical Specification limit due to the safety factor of 0.1.
- 3. Monitor response to gamma emitters is used to verify representativeness of Chemistry sample. Compliance with 10CFR20 limits on non-gamma emitters is ensured with Chemistry sample results and the maximum discharge flow of Step 3.
- 4. If discharging at the allowable discharge rate as determined in Step 3, this would yield a discharge concentration corresponding to 20% of the Technical Specification limit.
- 5. This value is based upon worst case conditions, assuming a maximum discharge flow (50 gpm), minimum dilution flow (186,000 gpm) and an assumed worst case mix of 4
nuclides (3 x 10 pCi/mi- Footnote 3.a Appendix B,10CFR20). If necessary, this value may be increased by factors to account for the actual discharge flow and actual dilution flow, Use of this value will assure that low level releases are not terminated due to small fluctuations in activity.
1 E- 2
C3/27/97 Rov. a l C -- E.2 Steam Generator Blowdown Monitor Assumptions used in determining the Al. ARM setpoint for this monitor are:
- a. Maximum possible liquid discharge rate = 43 GPM (maximum blowdown rate = 61 GPM of which 30% flashes to steam).
- b. Minimum possible dilution flow rate = 279,000 GPM (minimum of 3 cire. pumps during periods of blowdown).
l c. Unidentified MPC for unrestricted area (from Appendix B,10CFR20) = 1 x 10#pCl/ml. i l
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Therefore, alarm /setpoint should be:
)
279,000 S (pCI/ ml) = 1 x 10-' x = 6.5 x 10" pCl/ml 43 Using the monitor calibration curve, determine the CPM corresponding to 6.5 x 10" Cl/m!. The monitor alarm setpoint should be set at less than this corresponding value plus the background count rate.
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( E.3 Service Water Radiation Monitor Stoo i Maxim.um possible service water flow, F., from potentially contaminated areas flowing past monitor =
6,000 GPM x # of service water pumps on.
F. = 6,000 GPM x # service water pumps on.
i Steo 2 Dilution flow Fo = # Cire. Pumps x 93,000 Step 3 Worst case MPC* for unrestricted area = 3 x 10 pCi/ml (Note 1)
- 10CFR20 version prior to January 1,1992.
Step 4 Therefore, the maximum allowable concentration (A) at the monitor should be:
"+ #
A( C/ / ml) = 3 x 10-7 x l Fs E- 3
f 06/27/97 Rw. O l
Stoo 5 Determine the maximum allowable monitor response, R., in epm:
R,= E x A ( Ci/ml) I l
Where E is the current monitor efficiency in cpm per pCl/ml.
Steo 6 Determine the alarm trip setpoint, S, in cpm:
IF cire water and service water systems are both in operation for tank discharges:
S = R,,+ B At all other times: _
S = 3 x B (Note 2) l Where B = background of the monitor in cpm. For tank discharges, if the background
- l. exceeds the monitor response (R.) calculated, the monitor must be decontaminated.
!I For all other times, if the background exceeds 400 cpm (Note 3) the monitor must be decontaminated.
fielta:
- 2. This setpoint will provide a margin of a factor of ten below MPC for gamma emitters with a background of 80 cpm. A worst case release (inadvertent Recycle Test Tank release) would cause tritium concentrations at 70% of the tritium MPC.
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4.0 Inoperable Effluent Monitors During the period January 1 through December 31, 1997, the following effluent monitors were inoperable for more than 30 consecutive days:
4.1 Main Stack Monitor (RMS-14A) Inoperable: 2/6/97- 6/20/97(134 days)
Wide Range Gas Monitor (RMS 14B) Inoperable: 2/6/97- 8/5/97 (180 days)
Service Water Effluent Monitor (RMS 18) Inoperable: 2/6/97-6/17/97(131 days)
Test Tank Release Monitor (RMS-22) Inoperable: 2/6/97- 7/15/97(159 days)
During a routine NRC safety inspection in February 1997, severa! weaknesses were identified in the calibration and implementation processes for selected plar? radiation monitors. In part, the weaknesses were due to lost and misunderstood information that linked secondary cal brations to primary calibrations. As a result, a RMS corrective action plan was instituted to recalibrate and establish a baseline of information for the RMS monitors in question. Effected
- detectors were removed from service until the recalibration process was completed. During
- the period of inoperability, Technical Specification compensatory sampling and independent verification were performed. These effluent monitors were not restored to operability within 30 days because extra time was needed to develop updated calibration procedures and perform the calibrations.
l l 1 l 4.2 RMS Monitoring Computer (ScanRad) l The RMS Monitoring Computer (ScanRad)was declared inoperable for the period 2/6/97-6/20/97 l (134 days) due to ScanRad computer software and hardware problemss The vendor troubleshot j the system and replaced all necessary system components to include the ScanRad computer and software. Procedures were revised to reflect the associated changes. During this period, ;
l the applicable effluent monitor Technical Specification requirements were performed. These I effluent monitors were not restored to operability within 30 days because extra time was needed to: coordinate vendor troubleshootirig/ repairs and implement the associated procedure
)
revisions. i Based on NRC inspections in August and October 1997, NRC Report No 50-213/97/12 concluded:
(1) revised calibration procedures contained necessary steps to perform meaningful cahbration of effluent / process RMS, (2) cahbration results were within our acceptance criteria and were well defined in revised cakbration procedures, (3) calibration data reduction techr%que was sufficient to demonstrate validity and reliability of RMS, (4) necessary hardware basi been installed and I effluent / process RMS were operable at time of inspection, and (5) evaluation of historical calibration results indicated no significant releases because of less than optimum instrument sensitivities.
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S.0 Errata Enclosed are errata for the 1996 Annual Radioactive Effluent Report:
- 1. Table 1-11996 Off-Site Dose Commitments from Airborne Effluents and Table 1-3 1996 Off-Site Dose Summary were both corrected to reflect corrected met data for the second quarterof 1996. An Oversight Audit determined that the met data recovery rate was less than 90% for the quarter; and, therefore,it was reviewed and backup data replaced missing data whenever possible.
- 2. Table 2-5 Liquid Effluents - Release Summary, E. Volume,2. Dilution Volume During Releases were not available in time for the 1996 report. These volumes are included in the errata. '
- 3. Table 2-81996 Solid Waste and Irradiated Fuel Shipments, C. Offsite Processing did not include ]
processing performed by FW Hake. Tha FW Hake figures are included in the errata.
- 4. Section .t inoperable Effluent Monitors for the 1996 report was cited in an Oversight Audit as not specifying why effluent monitors were not restored to operability within 30 days, as required by Technical Specifications. The errata specifically states why effluent monitors were not restored to operabilitywithin 30 days.
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Table 1-1 l 1996 Off Site Dose Commitments from Airborne Effluents 1
Connecticut Yankee l 1 l l
l CY 1st Quarter l 2nd Quarter 3rd Quarter 4tn Quarter ?
hex Al" (mrad) Imred) (mrad) (mrad)
Beta 9 03E-03 0 0 3 mi NNW 5.38E-02 0 0 3 mi NNw 5.50E-01 0 0 3 ms NNw 5 27E-05 0 0 3 mi NNW Gamma 5 77E-03 o 0 3 mi NNw 2.84E 02 0 0 3 mi NNw 219E-01 0 0 3 mi NNw 4 65E-07 0 0 3 mi NNw Max individual (mremi (rr em) (mremi imremi i
mole Body 5 32E-02 0 0 3 me Nw 7.19E-02 0 0 3 ma NW 1.63E-01 0 0 3 mi NNW 3 81E-02 0 0 3 mi NW {
Thyroid 8 35E-04 0 0 3 mi NNWm 1.74E-02 0 0 3 mi NNW(t) 2 40E-02 0 0 3 mi NNW(t) !
1.67E-02 o 0 3 mi NNW (t)
Skin 6 59E-02 0 0 3 me Nw 9.71E-02 @ 0 3 mi Nw 417E-01 a 0 3 ma NNw 4 47E-02 @ 0 3 mi NW P:pulation (perswom) (person <em- (person <em) (perswomi mole Body 2.98E-02 1.08E-01 3 27E-01 1 13E-01 Thyroid 2 96E-02 1.04E 01 3.24E-01 1.09E-01 Skin 5 33E 02 1.73E 01 8 94E-01 1 12E-01 ,
Avg individual (mrom) (mrom) (mrom) (mrom) I m ole Body 7.97E-06 2.89E-05 8 74E-05 3 02E-05 Thyroid 7.91 E-06 2.78E-05 8.66E-05 2.91 E-05 Skin 143E-05 4.63E-05 2 39E 04 2.99E-05 (s)= Adult. (c)=Chdd (i)= Infant. (t)= Teen j I
Table 1-2 l 1996 Off Site Dose Commitments from Liquid Effluents Connecticut Yankee CY 1st Quarter 2nd Quarter 3rd Quarter 4th Quarter Max Individual (mrem) (mrems (mrem) (mrern) male Body 6 91E-04 9 69E-04 (a) 5 42E-02 (el 1.01 E-02 (a)
Thyroid 4 46E-04 tai 1.35E-03 (a) 3.66E-03 (a) 2.06E-04 (a)
Max Organ 7 85E-04 (suki 1.35E-03 (numi 7 52E-02 (t> m 146E-02 nuh)
Population (perswom) <persorwom) (pws w om) (person rom)
Mole Body 5 66E-04 8 30E-04 4.10E-02 7.72E-03 Thyroid 3.75E 04 9 06E-04 2.07E-03 1.55E-04 Max Organ 6 92E-04 m 9 06E-04 nni 6 69E-02 (h) 130E-02 m Avg Individual (mrom) (mrem; (mrom) (mremn mole Body 1.51 E-07 2.22E 07 1.10E-05 2 06E-06 Thyroid 1.00E-07 2.42E-07 5 53E-07 4.14E-08 Max Organ 1.85E-07 m 2 42E-07 im) 1.79E-05 m 3 48E-06 m (a)s/,dult. (c)=Chdd. (i)= Infant. (t)= Teen (bo)= Bone. (gi)=GI-LU. (su)= Kidney. (h)=Lrver. (lu)= Lung. (th)= Thyroid l
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Table 1-3 l
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1996 Off Site Dose Summary
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Connecticut Yankee !
l Population Dose Committments (person-rem) l Airborne Liquid Whole Body l Thyro 64 l Skin Whole Body l Thyroid l Max Organ l Station 0.5778 0.5666 1.2323 0 0501 0 0035 0 0815 Max Individual Doses vs Umits Whole Body Thyroid Max Organ Skin Air Airborne l Liquid Airborne l Liquid Liquid Airborne Beta l Gamma (mrem) (mrem) (mrom) (mrom) (mrad)
Unit Limit
- 5 1 3 15 l 10 10 15 20 l 10 Unit Actual 0.3262 l 00660 0.0589 l 00057 0 0919 0.6247 0.6129 l 0.2532 Station Limit " 25 15 25 Statlan Actual 0.3922 0.0646 0 0919 Connecticut Resident Average Whole Body Doses (mrem)
Cosme i 27 Cosmogenc j 1 Terrestial (Atlante and Gulf Coastal Plain) l 16 ,
inhaied 200 l l
In the Body l 40 i Average CT Resdent Whole Body Dose from Background *" 264 l
Average CT Resident (within 50 mdes) Whole Body Dose from Connectcut Yankee Stat <m Radoactive Effluents 0.0002
- 10CFR50 Appendix 1
" 40CFR190
~ NCRP94 l
ERRATA 1996
l Tcbla 2-5 Haddam Neck Liquid Effluents - Release Summary l
l 1996 Units 1st Qtr l 2nd Qtr l 3rd Qtr l 4th Qtr l Total A. Fission and Activation Products
- 1. Total Actmty i Ci : 1.70E-03 ; 2.34E-03 : 9.37E 3.71 E-04 ! 1.38E-02 Released ! i
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- 2. Average Penod ! uCi/mi 8.97E-12 l 1.21 E-11 j 9.39E-11 1.5TE-11 i 2.72E-11 .'
Diluted Activdy i I l l
i B. Tritium
- 1. Total Actmty ! Ci i 1.64E+02 l 2.60E+02 i 1.08E+02 l 7.78E+00 5.40E+02 l
Released l . l f g
- 2. Average Penod
{ uCi/mi ! 8.63E 677 1.35E-06 j 1.09E-06 ! 3.17E-07 l 1.07E-06 Diluted Actmty ! l ! l
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C. Dissolved and Entrained Gases
- 1. Total Actmty j Ci ; 5.74E-03 ; 6.58E-03 l 2.99E-03 I N/D 1.53E-02 Released l
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- 2. Average Penod i uCi/mi I 3.02E-11 l 3.41 E-11 ! 2.595 11 -
3.02E 11 ;
Dduted Actmty i ! ! !
D. Gross Alpha l
- 1. Total Actmty j ci N/D N/D N/D Released !
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4.66E-05 l 4.66E-05 i !
t E. Volume
- 1. Released Waste Liters . 8.94E+06 8.57E+06 1 3.16E+06 l 1.38E+06 2.21E+07 I Volume i l ! i
- 2. Ddution volume ' uters 3.72E+09 1.50E+10 j 4.65E+0s l 5.32E+09 l 1.35E+09 i
Dunng Releases j i !
3 Ddution volume i Uters 1.90E+11 - 1.93E+11 , 9.98E+10 i 2.45E+10 5.07E+11 Dunng Penod l N/D = Not Detected I I t
Table 2-8 Haddam Neck 1996 Solid Waste and Irradiated Fuel Shipments l
, A. .olid waste shipped offsite for burial or disposal (not irradiated fuel)
I 12-Month Est Total
- 1. Type of Waste Units Pened Total Error %
- a. Spent Resins, Filter Sludges, m3 3.75E+01 100E+01 Evaporator Bottom, etc. Ci 120E+03 m3 _
- b. Dry Compressible Waste, 101 E+01 1.00E+01 j Contaminated Equipment, etc. Ci 9 00E-01
- c. Irradiated Components m3--- -
1.00E+01 Ci -
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2- Estirnate of major nuclide composition (by type of waste)(% of total)
Type of Waste Nuchde a. b. c.
l C 14 6 29E-02 6.79E-01 -
Cm-242 6 82E-04 4 51 E-04 -
Cm-243 2 84E-04 2.13E 03 -
1 Cm-244 2.84E-04 2.13E-03 -
Co-58 1.28E+00 1.14E +00 -
Co-60 8 35E+00 414E +00 -
Cs-134 1.92E+01 1.63E+01 -
Cs 137 5.01E+01 5 05E+01 -
Fe-55 1.56E+01 6 34E+00 -
I-129 5 87E-05 1.50E 01 -
Mn-54 1.92E +00 - -
Ni-63 3 24E+00 1.35E +00 -
Np-237 1.01 E-07 3 70E-04 -
Pu-238 2 84E 03 6 52E-03 -
Pu-240 3 72E 04 122E-03 -
- Pu-241 6 35E-02 2.15E-01 -
Pu-242 1.27E-05 3 05E 04 -
Sr.90 7.20E-02 1 19E-01 -
- 3. Solid waste disposition No. Shipments Mode of Transportation Destination 11 Truck Bamwell, NC B. f rradiated fuel shipments (Disposition) None C. Offsite Processing l Vendor No. St.ipments Volume (m') Activity (Ci)
! SEG incorporated d 6 21 E+01 9 00E-01
'ERC 7 235ET02 5.17sT60 FW Hake 16 190E+01 4 59E+04
i 3.0 REMODCM Changes in 1996, there were no changes to the REMODCM.
4.0 Inoperable Effluent Monitors j l
During the period January 1 through December 31, 1996, the following effluent monitors were l inoperable for more than 30 consecutive days- 1 l
4.1 Service Water (R-18) and Primary Stack (R 14A) Effluent Monitors j These effluent monitors were declared inoperable for the period 8/30/96-12/16/96 due to lockup problems associated with the new RMS ScanRad computer which were caused by l' incompatibilities between the ScanRad software and the UNIX operating system. The vendor was notified and assisted in troubleshooting the computer and software problems. These effluent monitors were not restomd to operability within 30 days because of the extra time required for vendor support b troubleshooting software issues and subsequent procedure revisions. During this period, Chemistry followed Technical Specification action statements '
that required sampling and ana'yzing the service water every twelve hours while R 18 was out of service. Also during this period, another stack monitor, R-148, was used to monitor stack effluents while R-14A was out of service. !
5.0 Errata Enclosed is an errata to the solid waste disposition section of the 1993 Annual Radioactive Effluent j Report. The errata provides information for 8 additionaloff-site shipments that were previously omitted. '
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Docket No. 50-213 CY-98-063 1
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l Attachment 2 Haddam Neck Plant Radiological Effluents Monitoring Offsite Dose Calculation Manual l
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Northeast
\\ Utilities
\_. c RADIOLOGICAL EFFLUENT MONITORING l OFFSITE DOSE CALCULATION MAhTAL REMODCM s
CGNNECTICUT YANKEE ATOMIC POWER COMPANY ' l HADDAFi NECK PLANT finddam, Cr=narriad
. DOCKET ND.50213
/ LICENSE NO.DPR41 e
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l $E(JQU RADIOLOGICAL EFFLUENT MONITORING MANUAL FOR THE HADDAM NECK PLANT CJCKET NO. 50 213 May 1997 Revision 10 0482XW#1 DOC
5/30/97 R0 vision 10
(- HADDAM NECK PLANT RADIOLOGICAL EFFLUENT MONITORING MANUAL TABLE OF CONTENTS SECTION PAGE NO. REV.NO. DAIR A. INTRODUCTION A1 3 12/31/94 B. RESPONSliDILITIES B-1 3 12/31/94 C. LIQUID EFFLUENTS C.1 LIQUID EFFLUENTS SAMPLING AND ANALYSIS PROGRAM C-1 4 2/1/93 C2 4 2/1/93 C-3 4 2/1/93 C-4 4 2/1/93 C.2 LIQUID RADIOACTIVE WASTE TREATMENT C-5 4 2/1/93 D. GASEOUS EFFLUENTS D.1 GASEOUS EFFLUENTS SAMPLING AND ANALYSIS PROGRAM D-1 4 12/31/94 D2 4 12/31/94 D3 4 12/31/94 D.2 GASEOUS RADIOACTIVE WASTE TREATMENT D4 3 2/1/92 E. RADIOLOGICAL ENVIRONMENTAL MONITORING E.1 SAMPLING AND ANALYSIS E1 6 5/30/97 E2 5 5/30/97 1 E-3 6 2/28/97 j E-4 4 8/31/94 !
E-5 4 8/31/94 E6 4 8/31/94 E.2 1.AND USE CENSUS E-7 5 2/28/97 <
E.3 INTERLABORATORY COMPARISON l PROGRAM E-8 5 5/30/97 F. REPORT CONTENT F.1 ANNUAL RADIOLOGICAL ENVIRONMENTAL f i
- OPERATING REPORT F-1 3 10/15/95 F.2 ANNUAL RADIOACTIVE EFFLUENT REPORT F-2 3 8/31/94 omaxwant
12/31/94 Revision 3 A. INTRODUCTION j _
k The purpose of this manual is to provide the sampling and analysis programs which provide input to the ODCM for calculating liquid and gaseous effluent concentrations and i offsite doses. Guidelines are provided for operating radioactive waste treatment systems in order that offsite doses are kept As-Low-As-Reasonably Achievable (ALARA).
l The Radiological Environmental Monitoring Pmgram outlined within this manual provides confirmation that the measurable concentrations of radioactive material released as a result of operations at the Haddam Neck Plant are not higher than expected.
In addition, this manual outlines the information required to be submitted to the NRC in both the Annual Radiological Envimnmental Operating Report and the Annual Radioactive Effluent Report. l l
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12/31/94 Revision 3 B. RESPONSIBILITIES l
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N All changes to this manual shall be reviewed by the Plant Operations Review Committee s prior to implementation.
All changes and their rationale shall be documented in the Annual Radioactim Effluent Report. l ,
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l It shall be the responsibility of the Station Vice President to ensure that this manualis l used in performance of the surveillince requirements and administrative controls of the Technical Specifications.
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B-1 D482XW.001 1
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02/1/93 Revision 4 C. LIQUID EFFLUENTS C.1 Liould Effluent Samolino and Analysis Prooram Radioactive liquid wastes shall be sampled and analyzed in accordance with the program specified in Table C-f for the Haddam Neck Plant. The results of the radioactive analyses shall be input to the methodology of the ODCM to assure that the concentrations at the point of release are maintained within the limits of the TechnicalSpecification.
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02/1/93 Revbi::n 4 Table C-1 RADIOACTIVE LIQUID WASTE SAMPLING AND ANAL.YSIS PROGRAM l Lower Limit of Minimum Detection Sampling Analysis Type of Activity (LLD)*
Liquid Release Type Frequency Frequency Analysis (pCl/ml)
A. Batch Release
- Prior to Prior to Principal Gamma 5 x 10
Each Batch Each Batch Emitters'
- 1. Waste Test 1131, Mo-99, 1h104 Tanks and Zn 65, Cr 51, Recycle Test Ru 106 Tanks Co 141, Ce-144 5 x 104 Kr 85 1 x 10 d One Patch Monthly Other Dissolved 1 x 10 4 per Month and Entrained Gases
- 2. Waste Prior to Monthly H 3' 1 x 10 4 Neutralization Each Batch Composite **
Tank" and Gross alphal 1 x 10
NPDES Turbine Building Sump" Sr-891, Sr 901 5 x 10*
Prior to Quarterly Fe 551 1 x 10 4 Each Batch Composite **
- 8. Continuous Daily' Grab Weekly Principal Gamma 5 x 10
Release Sample Composite' Emitters
- l 131, Mo 99, 1 x 10 4 Zn-65, CR 51, Ru 106
- 1. Steam Co 141, Co-144 5x10*
Generater Blowdown d
Monthly Monthly Kr 85 1 x 10 Grab Other Dissolved Sample and Entrained Gases 1 x 104
- 2. Service Water Weekly Monthly H3 1 x 104 Effluent Grab Composite
- Sample Gross alpha' 1 x 10
Weekly Quarterly Sr 89e, Sr 908 5 x 10 4 4
- Grab Composite
- Fe 55 1 x 10 (
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o.mxem C-2
02/1/93 Revision 4 TABLE NOTATIONS
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- a. The LLD is the smallest concentration of radioactive materialin a sample that will be detected with 95% probability with 5% probability of falsely concluding that a blank observation represents a "real" signal.
For a particular measurement system (which may include radiochemical separation):
g, 4.66s, E V 2.22 x 105 Y exp(-AAf) where: l
{
LLD is the lower limit of detection as defined above (as pCI per unit mass or volume)
S. is the standard deviation of the background counting rate or of the counting rate of a blank sample as appropriate (as counts per minute)
E is the counting efficiency (as counts per transformation)
V is the sample size (in units of mass or volume) 2.22 x 10' is the number of transformations per minute per microcurie g Y is the fractional radiochemical yleid (when applicable)
A is the radioactivity decay constant for the particular radionuclide at is the elapsed time between midpoint of sample collection and midpoint of counting time.
1 it should be recognized th, ' the LLD is defined as an a orlori (before the fact) limit I representing the capability of a measurement system and not as an a posteriori (after the fact) limit for a particular measurement.
Analyses shall be performed in such a manner that the stated LLDs will be achieved under routine conditions. Occasionally background fluctuations, unavoidably small sample sizes, the presence of interfering nuclides, or other uncontrollable circumstances may render these LLDs unachievable. In such cases, the contributing factors will be identified and recorded on the analysis sheet for that particular sample,
- b. A composite sample is one in which the quantity of liquid sampled is proportional to the quantity of liquid waste discharged and in which the method of sampling employed results in a specimen which is representative of the liquid released,
- c. Prior to analysis, all samples taken for the composite shall be thoroughly mixed in order for the composite sample to be representative of the effluents released.
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02/1/93 Revision 4
- d. One batch per month means one batch from a waste test tank and one from a recycle
! test tank if they are discharged that month.
- e. The principal gamma emitters for which the LLD specification will apply are exclusively l the following radionuclider: Mn 54, Fe 59, Co 58, Co-60, Cs 134, and Cs 137. This list does not mean that only these nuclides are to be detected and reported. Other peaks l which are measurable and identifiable, together with the above nuclides, shall be l identified and reported. Nuclides which are below the LLD for the analyses should not ;
l be reported as being present at the LLD level. When unusual circumstances result in a orlori LLDs higher than required, the reasons shall be documented in the Annual Radioactive Effluent Report.
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- f. At least 5 days per week.
g.
For Service Water, these analyses are only required if a weekly gamma analysis indicates a gamma activity greater than 5 x 10' Cl/ml.
i h. Each batch should be sampled and analyzed for principal gamma emitters only if the t
steam generator gamma activity is greater than 5 x 104 pCi/ml.
J. Only required for the turbine building sumps and waste neutralization tank if the gamma activity of the batch is greater than 5 x 104 Ci/ml.
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- k. A batch release is the discharge of liquid waste of a discrete volume. Prior to sampling, each batch shall be isolated and at least two tank / sump volumes shall be recirculated or equivalent mixing provided.
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02/1/93 Revision 4 C.2 Liauld Radioactive Waste Treatment All applicable liquid radioactive waste treatment systems will be operated when the projected dose due to liquid effluents averaged over 31 days exceeds 0.06 mrem to the total body or 0.2 mrem to any organ.
The term "all applicable liquid radioactive waste treatment"is defined as that equipment applicable to a waste stream responsible for greater than ten percent (10%) of the total projected dose. The liquid radioactive waste treatment system equipment at the Haddam Neck Plant consists of the following:
portable mixed bed domineralizer and either evaporator or mixed bed polishing demineralizer;
- degasifier; and letdown system mixed bed domineralizer and either evaporator or boron recovery mixed bed polishing domineralizer.
With radioactive liquid waste being discharged without treatment and in excess of the above limits, prepare and submit to the Commission a report that included 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 inog 3rability;
- 2. action (s) taken to restore the inoperable equipment to OPERABLE status; and
- 3. summary description of action (s) taken to prevent a recurrence.
tf the above treatment systems are not routinely operating, doses due to liquid effluents to UNRESTRICTED AREAS shall be projected at least once per 31 days in accordance with the methodology and parameters in the ODCM.
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12/31/94 Revision 4 D. GASEOUS EFFLUENTS
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D.1 Gaseous Effluents Samolina and Analvsis Proaram Radioactive gaseous wastes shall be sampled and analyzed in accordance with the program specified in Table D-1 for the Haddam Neck Plant. The results of the radioactive analyses shall be input to the methodology of the ODCM to assure that the offsite dose rates are maintained within the limits of the Technical Speci-fication.
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. TABLE.Q:1
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RADIOACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS PROGRAM Lower Limit Minimum of Detection l Sampling Analysis Type of Activity Gaseous Release Type (LLD)*
l Frequency Frequency Analysis (nCl/cc) l I
l l A. Waste Gas Decay Grab Sample Prior to Principal Gamma 1 x 10" l l
l Tank Prior to Each Tank Emitters
- Each Tank H-3 1 x 10 d
Discharge Xe-138 3 x 10" B. Containment Purge Grab Sample Prior to Principal Gamma 1 x 10" Prior to Each Purge Emitters
- i Each Purge H-3' 1 x 10 4
7 Xe-138 3 x 10 d Monthly
- Monthly
- Principal Gamma 1 x 10" Gaseous Emitters
- l Grab Samples H-3 1 x 104 Xe-138 3 x 10" Continuous' Weekly" 1-131 1 x 10a2 Charcoal I i Sample 1-133 1 x 10"'
I Continuous' Weekly" Principal Particu- 1 x 10'"
Particulate late Gamma Sample Emitters' (1-131, others with
' half lives > 8 days)
C. Main Stack Continuous' Monthly Gross Alpha 1 x 10'"
l Composite l Particulate Sample Continugus' Quarteriy Sr-83, Sr 90 1 x 10'"
Composite Particulate l
Sample Continuous' Noble Gas Noble Gases 1 x 10 d
Monitor Gross Activity I
D-2 D482XW 001
1 12/31/94 Revision 4 TABLE D-1 (Cont'd.)
TABLE NOTATIONS a.
The lower limit of detection (LLD) is defined in Table Notations of Table C-1.
- b. Samples shall be changed at least once per 7 days and analyses shall be comr. :
within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> after changing. Special sampling and analysis of iodine and partic 4 filters shall also be performed whenever reactor coolant 1-131 samples taken 2-6 hurs following a THERMAL POWER change exceeding 15 percent of RATED THERMAL POWER in one hour show an increase of greater than a factor of 5. These filters shall be changed following such a five-fold increase in coolant activity and every 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> thereafter until the reactor coolant 1-131 levels are less than a factor of 5 greater than 4 the original coolant levels or until seven days have passed, whichever is shorter.
Sample analyses shall be completed within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> of changing. The LLDs may be increased by a factor of 10 for these samples.
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- c. Sampling and analysis of principal gamns .aitters shall also bu performed within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> following shutdown, startup, or a TH IRMAL POWER change exceeding 15 percent of RATED THERMAL POWER within one hour unless (1) analysis shows that the DOSE EQUIVALENT l-131 concentration in the primary coolant has not increased more than a factor of 3 and (2) the noble gas activity monitor shows that effluent activity l has not increased by more than a factor of 3.
- d. The ratio of the sample flow rate to the sampled stream flow rate shall be known for the i
time period covered by each dose or dose rate calculation made in accordance with Technical Specifications.
- e. The principal gamma emitters for which 1.le LLD specification will apply are exclusively the following radionuclides: Kr-87, Kr 88, Xe-133, Xe-133m, and Xe-135. The list does not mean that only these nuclides are to be detected and reponed. Other peaks which are measurable and identifiable, together with the above nuclides, shall be icientified and reported. Nuclides which are below the LLD for the analyses should not be reported as being present at the LLD level for that nuclide. When unusual circumstances result in LLDs higher than required, the reasons shall be documented in the Annual Radioactive Effluent Report.
- f. When the refueling cavity is flooded and purging is in progress, samples shall be taken at least once every 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> from the charging floor (refueling floor) and analyzed for tritium. The results shall be used along with containment purge flow rates to determine tritium releases.
g.
The principa! gamma emitters for which the LLD specification will apply are exclusively the following radionuclides: Mn-54, Fe 59, Co 58, Co-60, Zn-65, Mo 99, Cs-134, Cs-137, Co-141, and Co-144. The list does not mean that only thase nuclides are to be detected and reported. Other peaks which are measurable and identifiable, together with the above nuclides, shall be identified and reported. Nuclides which are below the LLD for the analyses should not be reported as being present at the LLD level for that
( nuclide. When unusual circumstances result in LLDs higher than required, the reasons shall be documented in the Annual Radioactive Etlluent Report. l o arxw m
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D.2 Gaseous Radioactive Waste Treatment All applicable when the proj, gaseous radioactive waste treatment systems shall b exceeds 0.2 mrad for gamma radiation,0.4 mrad for beta radiation or 0.3 mrem to any organ due to gaseous particulate effluents.
The term all applicable gaseous radioactive treatment is defined as that equipment applicable to a waste stream responsible for greater than ten percent (10%) of the total projected dose. The gaseous radioactive waste treatment systems equipment at the Haddam Neck Plant consists of the following:
e Waste Gas Surge Tank, Waste Gas Compressor A or B and at least one Waste Gas Decay Tank e Ventilation System HEPA Filter and Charcoal Filter With gaseous waste being discharged without treatment and in excess of the above limits, prepare and submit to the Commission a report that includes the following information:
- 1. Explanation of why gaseous radwaste was being discharged without treatment, identification of any inoperable equipment or subsystems, and the reasons for the inoperability, t
- 2. Action (s) taken to restore the inoperable equipment to OPERABLE status, and
- 3. Summary description of action'i)taken to prevent a recurrence.
If the above. treatment systems are not routinely operating, coses due to gaseous effluents to UNRESTRICT ED AREAS shall be projected at least once per 31 days in accordance with the methodology and parameters in the ODCM.
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5/30/97 Rsvision 6 E. RADIOLOGICAL ENVIRONMENTAL MONITORING
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E.1 Sameline and Analvala l
The radiological sampling and analyses provide measurements of radiation and of radioactive materials in those exposure pathways and for those radionuclides which lead to the highest potential radiation exposures of individuals resuiting from plant operation. This monitoring program thereby supplements the radiological effluent monitoring program by verifying that the measurable concentrations of radioactive materials and levels of radiation are not higher than expected on the bwsis of the affluent measurements and modeling of the environmental exposure pathways. Program changes may be made based on operational experience.
The sampling and analyses shall be conducted as specified in Table E-1 for the locations shown in Appendix G of the ODCM. Deviations are permitted from the required sampling schedule if specimens are unobtainable due to hazardous conditions, seasonal unavailability, malfunction of automatic sampling equipment or other legitimate reasons. If specimens are unobtainable due to sampling equipment malfunction, every effort shall be made to complete corrective action prior to the end of the next s'mpling period.
All deviations from the sampling schedule shall be documented in the Annual Radiological Environmental Operating Report pursuant to Section F.1. It is recognized that, at times, it may not be possible or practicable to continue to obtain samples of the media of choice (excluding milk) at the most desired focation l or time. In these instances suitable sitemative media and locations may be chosen for the particular pathways in questions and appropriate substitutions made within 30 days in the radiological environmental monitoring program, if milk samples are temporarily unavailable from any one or more of the milk r, ample locations required by Table E-1, a grass sample shall be substituted during the growing season (Apr. - Dec.) and ana'yzed for gamma isotopes until milk is again available. Upon notification that milk samples will be unavailable for a prolonged period (>g months) from any one or more of the milk sample locations required by Table E-1, a suitable replacement milk location shall be evaluated and appropriate changes made in the radiological environmental monitoring program.
Reasonable attempts shall be made to sample the replacement milk location prior to the end of the next sampling period. Any of the above occurrences shall be documented in the Annual Radiological Environmental Operating Report which is submitted to the U.S. Nuclear Regulatory Commission prior to May 1 of each year.
Changes to sampling locations shall be identified in a revised table and figure (s) in Appendix G of the ODCM.
If the level of radioactivity in an environmental sampling medium at one or more of the locations specified in Table E-1 exceeds the report levels of Table E-2 when i
cesaxw ,.coe E-1 )
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averaged over any calendar quarter, prepare and submit to the Commission within 30 days from the end of the affectori calendar quarter, a Special Report which includes an evaluation of any release conditions, environmental factors or other aspects which caused the limits of I
Table E 2 to be exceeded. When more than one of the radionuclides in Table E 2 are detected in the samplir.g medium, this report shall be submitted if:
concentration (l) concentration (2) + 2 3.9 b reporting level (1) reporting level (2)
When radionuclides other than those in Table E-2 are detected and are the result of plant effluents, this report shall be submitted if the potential annual dose to an individual is equal to or greater than the appropriate calendar year limit of the Technical SpecIlication. This report is not required if the measured level of condition shall be reported and desenbod in the Annual l Radiological Environmental Operating Report. ]
The detection capabilities required by Table E 3 are state of the art for routine envircnmental measurements in industrial laboratories. It should be recognized that the LLD is defined as .
an Biri.grir (before the fact) limit representing the capability of 6 measurement system and not I as an a costerior (after the fact) limit for a particular measurement. All analyses shall be performed in such a manner that the stated LLDs will be achieved under routine conditions.
Occasionally background fluctuations, unavoidably small sample sizes, the presen:e of interfering nuclides, or other uncoritrollable circumstances may render these LLDs unachievable. In such cases, the contributing factors will be identified and describixi in the
, Annual Radiological Environmental Operating Report l
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7128/97 Revision 6
(-o M HADDAM NECK RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Exposure Pathway Number of Sampling and Type and Frequency of and/or Sample Locations Collection Frequency Analysis 1a. Gamma Dose - 14 Monthly Gamma Dose - Monthly Environmental TLD 1t: Gamma Dose - 27 Quarteriy") N/A")
Accident TLD
- 2. Airt>ome 7 Continuous sampler- Gross Beta - Weekly
. F articulate weekly filter change Gamma Spectrum - Quan erly ,
on composite (by location), I and on individual sample if '
gross beta is greater than 10 times the mean of the weekly control station's gross beta results
- 3. Vegetation 4 One sample near middle Gamma Isotopic on each and one near er.d of- sample growing season
- 4. Milk 5 Monthly Gamma isotopic on each sample Monthly Sr-89 and Sr Quarteriy t
4a. Pasture Grass 6 Sample as necessary to Gamma Isotopic substitute for unavailable milk
- 5. Well Water 2 Quarterly Gamma Isotopic, and Tritium on each composite
- 8) . Bottom Sediment 3 Semlannual Gamma Isotopic
- 7. River Water 2 Quarterly Sample - Quarterly - Gamma isotopic Indicator is continuous and Tritium Composite; Background is Composite of Six Weekly Gram Samples
- 8. Fish bullheads 3 Quarterty Gamma Isotopic- Quarterly and,when available, Perch or
' other edible fish
- 9. Shellfish 2 Quarterly Gamma isotopic- Quarterly (a) Accident monitoring TLDs to be dedosed at least quarterty.
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l 08/31/94 I Reeision 4 TABLE E 2
? REPORTING LEVELS FOR RADIOACTIVITY CONCENTRATIONS IN ENVIRONMENTAL SAMPLES Reporting Levels Airborne Particulate Fish Vegetables Shellfish Water or Gases (pCilkg, Milk (pCLig, (pCl/kg.
Analysis (pCl/l) (pCl/m*) wet) (pCl/l) wet) wet)
H3 2 x 10' Mn-54 1 x 10' 3 x 10' 1.4 x 10' Fe 59 4 x 102 1 x 10' 6.0 x 10' 5
Co 58 1 x 10 3 x 10' 1.3 x 10' Co-60 3 x 10 8 1 x 10' 5.0 x 10' Zn-65 3 x 10' 2 x 10' 8.0 x 10' Zr-95 4 x 10 8 Nb 95 4 x 10 8 l131 (a) 0.9 2 x 10 2 3 1 x 10 1 x 10' Cs 134 30 10 1 x 10' 60 1 x 10' 5 x 10' Cs 137 50 20 2 x 10' 70 2 x 10 5 8 x 10 2 Ba 140 2 x 10 2 3 x 10 3 La 140 2 x 10 2 3 x 10' (a) Level for 1131 not included since no radioactivity discharged to any drinking water pathways; other reporting levels are included for trending of long-lived isotopes only.
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08/31/94 Revision 4 TABLE E-3
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s MAXIMUM VALUES FOR LOWER LIMITS OF DETECTION (LLDt l
l Alttpome Food Particulate Fish Products Sediment Water or Gas (pCilkg, Milk (pct /kg, (pCl/kg, Analysis (pCl/I) (pCl/m*) wet) (pct /I) wet) dry) gross beta 1 x 10'8 l
l H3 2000 l Mn-54 15 130 Fe 59 30 260 Co 58,60 15 130 Zn 65 30 260 Zr 95 30 Nb-95 15 l l131 c 7 x 10'8 1 60' j l Cs 134 15 5 x 10 130 15 60 150 Cs 137 18 6 x 10 150 18 80 180 lt Ba 140 60 70 i La 140 15 25 1
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08/31/94 Reeision 4 TABLE E-3 (Cont'd)
TABLE NOTATIONS
, a. The LLD is the smallest concentration of radioactive materialin a sample that will be detected with 95% probability with 5% probability of falsely concluding that a blank observation represents a real" signal.
For a particular measurement system (which may include radiochemical separation):
4.66s, tto ,, M .22 Y exp(-Aat) where:
LLD is the lower limit of detection as defined above (as pCi per unit mass or volume)
S,is the standard devicton of the background counting rate or of the counting rate of a blank sample as appropriate (as counts per minute)
E is the counting efficiency (as counts per transformation)
V is the sample size (in units of mass or volume) 2.22 is the number of transformations per minute per picoeurie Y is the fractional raciochemical yield (when applicable)
A is the radioactivity decay coasant for the particular radionuclide At is the elapsed time between midpoint of sample collection and midpoint of counting time, it should be recognized that the LLD is defined as an a orlori (before the fact) limit representing the capability of a measurement system and not as an a costeriori (after the fact) limit for a particular measurement.
Analyses shall be performed in such a manner that the stated LLDs will be achieved under routine conditions. Occasionally background fluctuations, unavoidably small sample sizes, the presence of interfering nuclides, or other uncontrollab!e circumstances may render these LLDs unachievable. In sudi cases, the contributing factors will be 1
identified and descrtbed in the Annual Radiological Environmental Operating Report.
- b. LLD for leafy vegetables.
- c. Background and onsite well water will not contain the short lived 1-131 isotope. River water is not used as offsite potable water supply and need not be analyzed for 1-131.
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2/28/97 Revision 5 l
( -o E.2 Land Use Census l The land use census sase,ss that changes in the use of unrestricted areas are identified and that modificatioris to the monitoring program are made if required '
l by the results of this census. This census satisfies the requirements of j
Section IV.B.3 of Appendix I to 10CFR Part 50. The land use census shall be maintained and shallidentify the location of the milk animals in each of the 16 meteorological sectors within a distance of five miles.*
The validity of the land use census shall be vedfied at least once per calendar year by either a door-to-door survey, serial survey, consulting local agriculture l
authorities, or any combination of these methods.*
With a land use census identifying a location (s) which yields a calculated dose or dose commitment greater than the doses currently being calculated in the off site dose models, make the appropriate changes in the sample locations used.
1 With a land use census identifying a location (s) which has a higher D/Q than a current indicator location the following shall apply:
(1) If the D/Q is at least 20% greater than the previously highest D/Q, replace one of the present sample locations with the new one within 30 days if milk is available, i (2) If the D/Q is not 20% greater than the previously highest D/Q, consider direction, distance, availability of milk, and D/Q in deciding whether to l replace one of the existing sample locations, if applicable, replacement should be within 30 days. If no replacement is made, sufficient justification should be given in the annual report.
Sample location changes shall be noted in the AnnualRadiologicalEnvironmental Operating Report.
- Broad leaf vegetation (a composite of at least 3 different kinds of vegetation) may l
be sampled at the site boundary in each of 2 different direction sectors with high D/Q in lieu of a garden census. -
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5/30/g7 Revision 5
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E.3 Intertaboratory comearison Prooram
. The Interfaboratory Comparison Program is provided to ensure that independent checks on the precision and accuracy of the measurements of radioactive materialin l
environmental sample matrices are performed as part of a quality assurance program for environmental monitoring in order to demonstrate that the results are reasonably i valid. l l
Analyses shall be performed on radioactive materials supplied as part of an l
interlaboratory Comparison Program. A summary of the results obtained as part of the l above required interlaboratory Comparison Program shall be included in the Annual l Radiological Environmental Operating Report. !
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.
t E-8 D442XW-1. Doc
10/15/95 Rsvision 3 F. REPORT CONTENT F.1 Annual Radioloaical Environmental Ooeratino Report
(---
The Annual Radiological Environmental Operating Report shall include summaries, interpretations, and statistical evaluation of the results of the radiological environmental surveillance activities for the report period, including a comparison with previous i environmental surveillance reports and an assessment of the observed impacts of the plant operation on the environment. The report shall also include the results of the land use census required by Section E.2 of this manual. If levels of radioactivity are I detected that result in calculated doses greater than 10 CFR 50 Appendix i Guidelines, the report shall provide an analysis of the cause and a planned course to action of alleviate the cause, ,
j i
The report shallinclude a summary table of all radiological environmental samples 1 which shall include the following information for each pathway sampled and each type !
of analysis: i I
(1) Total number of analyses performed at indicator locations. '
(2) Total number of analyses performed at controllocations.
(3) Lowerlimit of detection (LLD).
(4) Mean and range of allindicator locations together.
i (5) Mean and range of all controllocations together.
(6) Name, distance, and direction from discharge, mean and range for the location with the highest annual mean (indicator or control).
(7) Number of nonroutine reported measurements as defined in these specifications.
In the event that somt results are not avai!able 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 in the next annual report, The report shall also include a map of sampling locations keyed to a table giving distances and directions from the discharge; the report shall also include a summary of the interlaboratory Comparison Data required by Section E.3 of this manual.
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08/31/94 Revision 3 F.2 Annual Radioactive Effluent Report I The Annual Radioactive EMuenf Report (ARER) shall include quarteriy quantitles of and an annual summary of radioactive liquid and gaseous effluents ;alsased from the unit in the Regulatory Guide f.21 (Rev. f,06/74) format. Rad!ation dose assessments for these affluents shall be provided in accordance with 10CFR 50.36a and the Radiological EMuent TechnicalSpecMcations. An annual assessment of the radiation doses from the site to the most likely exposed REAL MEMBER OF THE PUBLIC shall be included to demonstrate conformance with 40 CFR 790. Gaseous pathway doses shall use meteorological conditions concurrent with the time of radioactive gaseous effluent, releases. Doses shall be calculated in accordance with the Offsite Dose Calculation Manual. The licensee shall maintain an annual summary of the hourly meteorological data (i.e., wind speed, wind direction, and atmospheric stability) either in the form of an hour-by hour listing on a magnetic medium or in the form of a joint frequency distribu-tion. The licensee has the option of submitting this annual meteorological summary with the ARER, or retalning it and providing it to the NRC upon request. The ARER shall be submitted by May 1 of each year for the period covering the previous calendar year.
The ARER shall include a summary of each type of solid radioactive waste shipped o'fsite for burial or final disposal during the report period and shall include the following information for each type:
- a. type of waste (e.g., spent resin, compacted dry waste, irradiated components, etc.);
- b. solidification agent (e.g., cerr.ent);
- c. total curies;
- d. total volume and typical container volumes;
- e. principal radionuclides (those greater than 10% of total activity); and
- f. types of containers used (e.g., LSA, Type A, etc.).
The ARER shall include the following information for all abnormal releases of radinactive gaseous and liquid effluents (i.e., exceeding Techn/ cal SpecMcation instantaneous release limits) from the site to unrestricted areas:
- a. a description of the event and equipment involved;
- b. cause(s) for the abnormal release;
- c. actions taken to prevent recurrence; and
- d. consequences of the abnormal release.
Changes to the RADIOLOGICAL EFFLUENT MONITORING and OFFSITE DOSE CALCULATION MANUAL (REMODCM) shall be submitted to the NRC as approprf.e, as a part of or concurrent with the ARER for the period in which the changes were made.
o.am F-2
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- OFFSITE DOSE CALCULATION MANUAL FOR THE HADDAM NECK PLANT DOCKET NO. 50 213 l
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June 1997
- * * *
- Revision 10 l
6/27/97 R:visi:n 10 MADDAM NECK PLANT OFFSITE DOSE CALCULATION MANUAL TABLE OF CONTENTS 1
SECJ1Q.N PAGE NO. REVJO. DAIE A. INTRODUCTION A-1 2 12/31/94 B. RESPONSIBILITIES B-1 2 12/31/94 1
C. LIQUID DOSE CALCULATIONS. I C.1 QUARTERLY DOSE CALCULATIONS
- a. Whole Body D'ose C-1 2 12/31/94
- b. Maximum Organ Dose C-1 2 12/31/94 C.2 ANNUAL DOSE CALCULATIONS
- a. Whole Body Dose C-2 2 12/31/94
- b. Maximum Organ Dose C-2 2 12/31/94 C.3 MONTHLY DOSE PROJECTIONS C-3 2 12/31/94 C-4 2 12/31/94 C.4 QUARTERLY DOSE CALCULATIONS FOR ANNUAL RADIOACTIVE EFFLUENT REPORT C-4 2 12/31/94 D. GASEOUS DOSE CALCULATIONS D.1 10CFR20 LIMITS (* INSTANTANEOUS *)
- a. Noble Gas Release Rate Limit D-1 2 12/31/94
- b. lodine & Particulate Release i Rate Limit D-2 3 4/15/95 l D-3 3 4/15/95 ,
l D.2 10CFR50 APPENDIX l-NOBLE GAS LIMITS
- a. Quarterly Air Dose Limit Due to Noble Gases D4 2 12/31/94 D5 2 12/31/94
- b. Annual Air Dose Limit Due to k Noble Gases D5 2 12/31/94 oeuwooe T of C - 1
6/37/97 Ravision 10
( -
HACDAM NECK PLANT '
OFFSITE DOSE CALCULATION MANUAL TABLE OF CONTENTS (Continued)
SECTION PAGE NO. REV.No. DAIE D.3 10CFR50 APPENDIX l-LODINE AND PARTICULATE DOSES
- a. Quarterly Organ Dose Limit D-6 2 2/1/93 D-7 2 2/1/93
- b. Annual Organ Dose Limit D-7 2 2/1/93 D.4 GASEOUS EFFLUENT MONTHLY DOSE PROJECTIONS
- a. Gaseous Radweste Treatment System D-8 1 1/1/90 .
- b. Ventilation Releases D-8 1 1/1/90 D9 2 12/31/94 1 l
D.5 QUARTERLY DOSE CALCUl.ATIONS FOR ,
ANNUAL RADIOACTIVE i EFFLUENT REPORT D-9 2 12/31/94 D.6 COMPLlANCE WITH 40CFR190 LIMITS D-9 2 12/31/94 E. LIQUID MONITOR SETPOINTS E.1 TEST TANK DISCHARGE LINE MONITOR E1 3 6/27/97 E-2 2 6/27/97 E.2 STEAM GENERATOR BLOWDOWN MONITOR E 3 2 6/27/97 E.3 SERVICE WATER RADIATION MONITOR E-3 2 6/27/97 E-4 0 6/27/97 F. GASEOUS MONITOR SETPOINTS F.1 STACK NOBLE GAS ACTIVITY MONITOR F1 1 1/1/90 o . = ooc T of C - 2
6/27/97 !
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Rtvision 10
(_ HADDAM NECK PLANT OFFSITE DOSE CALCULATION MANUAL LIST OF TABLES AND FM l
TABLE NO. IMET '!MdE PAGE NO. REV.NO. M j 1 DOSE FACTORS FOR NOBLE GASES D-10 1 1/1/90 2 DOSE FACTORS FOR IODINE & ,
PARTICULATES D-11 1 1/1/90 ;
FIGURE NO. FIGURE NAME PAGE NO. REV. NO. M G1 INNER TERRESTRIAL MONITORING STATIONS APP. G 3 4 5/30/97 G-2 AQUATIC AND WELL WATER SAMPLING STATIONS APP. G 4 2 5/30/97 G-3 ACCIDENT TLD SAMPLING LOCATIONS APP. G 5 2 5/30/97 l
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6/37/97 Revision 10
_. HADDAM NECK PLANT OFrSITE DOSE CALCULATIONNANUAL dM l l
M D&H
, APPENDIX A DERIVATION OF FACTORS FOR SECTION C.1.a 1 1/1/90 APPENDIX B DERIVATION OF FACTORS FOR SECTION C.1.b i 1/1/90 APPENDIX C LIQUID DOSE CALCULATIONS-LADTAP 1 1/1/90 APPENDIX D DERIVATION OF FACTORS FOR SECTION D.1 3 4/15/95 APPENDiXE GASEOUS DOSE CALCULATIONS - GASPAR 1 1/1/90 APPENDIX F DERIVATION OF FACTORS FOR SECTIONS D.2 & D.3 2 2/1/93 APPENDIX G ENVIRONMENTAL MONITOR!NG PROGRAM SAMPLING LOC #flONS 6 5/30/97 APPENDIX .: DERIVATION OF FACTORS FOR TABLE 2 1 1/1/90 1
1 m,,n T of C -4
12/31/94 Rsvision 2 A INTRODUCTION
( --
The purpose on tnis manualis to provide the parameters and methods to be used in calculating offsite doses and affluent monitor setpoints at the Haddam Neck Plant.
Included are methods for determining maximum individual whole body and organ doses due to liquid and gaseous effluents to assure compliance with the dose limitations in the TechnicalSpecifications. Also included are methods for performing dose projections to assure compliance with the liquid and gaseous treatment system operability sections of the Radiological Effluent Monitoring Manual. The manual also includes the methods used for determining quarterly individual and population doses for inclusion in the ,
Annual Radioactive Effluent Report. I j J
Another section of this manual discusses the methods to be used in determining effluent monitor alarm / trip setpoints to be used to ensure compliance with the instantaneous ~
release rate limits in the TechnicalSpecifications.
The bases for some of the factors used in this manual are included as appendices to this manual. Supplementalinformation on environm6atal sarnple locations is provided in an appendix.
This manual does not include surveillance procedures and forms required to document compliance with the surveillance requirements in the TechnicalSpecifications. All that is included here are the methods to be used in performance of the surveillance requirements.
i Most of the calculations in this manual have two or three methods given for the calculation of the same parameter, Thess methods are arranged in order of simplicity, Method 1, being the easiest but more conservative method. As long as releases remain low, one should be able to use Method f as a simple estimate of the dose, if release calculations approach the limit, however, more detailed and hence more realistic calculations may be used.
At any time, a more detailed calculation may be used in lieu of a simple calculation.
i A-1 De41XW.001
12/31/94 Revisisn 2 B. RESPONSIBILITIES All changes to this manual shall be reviewed by the Plant Operations Review Committee prior to implementation.
All changes and their rationale shall be documented in the subsequent Annual Radioactive Effluent Report. l It shall be the responsibility of the Station Vice President to ensure that this manual is used in performance of the surveillance requirements specified in the TechnicalSpecification.
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12/31/94 C. Rsvision 2 LIQUID DOSE CALCULATIONS C.1 Quarterly Dose Calculations
- a. Whole Body Dosa (1) AteltlagU This method may be used until the calculated total body dose exceeds 0.5 mrom for the calendar t'ry.ter. ,
E1ML1 l Determine C, which is the total curies of fission and activation products, oxcluding tritium and dissolved noble gases released during the calendar quarter.
E189.2 Determine C7 which is the total curies of tritium released during the calendar quarter.
E1ML1 Determine Dow which is the quarterly dose to the whole body in mrem:
Dow = 5.4
- C, + 1
- 10-'
- C7 [See Appendix A) 2119.4 If Dow > 0.5 mrem, go to Method 2.
(2) Method 2 If the calculated dose using Method 1 is greater than 0.5 mrom, use the methodology of NRC Regulatory Gukte 1.109, Rev.1 to calculate the liquid doses. The use of this model and the input parameters discussed in Appendix C are given in RadWW Assessment Branch Procedure, LiquidDose Calculabians -I.ADTAPll.
- b. Maximum Ornan Does (1) geltlgt.1 This method 2 be used until the calculated dose to the maximum organ exceeds 2 millirem for the calendar quarter.
E189.1 Determine C,- as in C.1.a(1) Step 1 C-1 o401XW.001
12/31/94 Revision 2 11tlL2 Determine Cr - as in C.1.a(1)- Step 2 1183LI l
Determine Doo which is the quarterty dose to the maximum organ i in mrom Doo = 8.0
- C, + 1'10-'
- Cy [See Appendix B] i Etta(
if Doo > 2 mrom, go to Method 2 (2) Method 2 l
If the calculated dose using Method f is greater than 2 mrom, use the methodology of NRC Regulatory Guide 1.109 Rev.1 to calculate the liquW doses. The use of this model and the Input parameters are discussed in Appendix C and also g;ven in Radiological Assessment Branch Procedure, LiquW Dose Calculations - LADTAP 11.
C.2 Annual Dose Calculations
- a. Ehgjt.gody Dpse Determine Dyw which is the dose to the whole body for the calendar year as follows:
Dyw - I Dow, where the sum is over the first quarter through the present quarter whole body doses The following should be used as Dow:
(f) if the detailed quarterly dose calculations required per Sectbn C.4 for the Annual Radioactive Ettluent Report are complete for any calendar l quarter, use that result.
(2) If the detailed calculations are not complete for a particular quarter, use the results as determined in Secton C.f.a.
(3) if Dyw > 3 mrom and any Dow determined as in Sectbn C.7.a was not calculated using Method 2 of that section, recalculate Dow using Method 2.
- b. Maximum Oman Dose Determine Dvo which is the dose to the maximum organ for the calendar year as follows:
Dvo -I Doo The sum is over the first quarter through present quarter dose.
D481XW.001 C2
12/31/94 Revision 2 The following guidelines should be used:
(1)
I ~' If the detailed quarterly dose calculations required per Section C.4 for the Annual Radioactive Effluent Report are complete for any calendar l quarter, use that result.
(2) If the deta, led calculations are not complete for a particular quarter, use the results as determinad in Sectkm C.f.b.
(3) If different organs are the maximum for different quarters, they may be summed together and Dvo can be recorded as a less than value as long as the value is less than 10 mrom.
(4) If Dvo > 10 mrom and any value used in its determination was calculated as in Section C.f.b but not with Method 2, recalculate that value using Method 2.
C.3. Monthly Dose Protections This method ratios a previously calculated total body and maximum organ monthly dose based upon liquid release volumes, concentration, and fraction of release due to blowdown to project a monthly dose,
- s. Monthly Dose Projections to the Total Body and Maximum Oraan Elta.1
. Determine Duw which is the whole body dose from the previously completed month
- as calculated per the method in Secton C.f.a.
Etta.2 Determine Duo which is the maximum organ dose from the previously completed month
- as calculated per the methods in Seebon C.f.b.
Ettita Estimate Ri which equals the ratio of the total estimated volume of liquid batched to be released in the present month to the volume released in the past month.
218R.4 Estimate R which equals the ratio of the total estimated volume of steam generator blowdown to be released in the present month to the volume released in the past month.
EltR.E Estimate F which equals the fraction of curies released last month i
coming from steam generator blowdown, l.a.:
curies fromblowdown
,1, curies from blowdown + curies from batch tanks o481XW.001 C-3 i
12/31/94 Revisien 2 StD f l~ Estimate R3 which is the ratio of estimated secondary coolant activity for the present month to that for the past month.
ailtD.I Estimate R4 which is the ratio of estimated primary coolant activity for the present month to that for the past month, ailta.E Determine F, which is the factor to be applied to estimate ratio of final curie release if there are expected differences in treatment of liquid waste for the present month as opposed to the past month. NUREG-0017 or past experience should be used to determine the effect of each form of treatment. Set F,- 1 if there are no expected differences.
ERA.E Determine DL which is the estimated monthly whole body dose as follows:
8 DL = D. '(1 - F, ) R, R F, + F, R, R, alltD.19 Determined'm which is the estimated monthly maximum organ dose as follows:
D m' = D (1 - F, ) R, R. F, + F, R, R ,
'if the past month is not typical of expected operations in the present month, go back to the last typical month. For example, if the plant was down for refueling the entire month of February and start up is scheduled for March, use the last month of c,peration as the base month to estimate March's dose.
if the last typical month's doses were calculated using LADTAPll (or similar methodology), also multiply last typical month's doses by Rs where Rs = last typical month's total dilution flow / estimated total dilution flow.
C.4. Quarterty Dose Calculations for Annual Radioactive Effluent Rooort l Detailed quarterfy dose calculations required for the Annual Radbactive Effluent Report shall be done using the NRC computer code LADTAP 11.
The use of thH exie and the input parameters are given in Madologica/
l Assessment Brexh Procedure, Liquid Dose Calculations LADTAP II.
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o441XW.001
12/31/94 Revision 2 D. GASEOUS DOSECALCULATIONS f
{
D.1. 10CFR20 Limits (" Instantaneous")
I ~~ a. Noble Gas Release Rate Limit Limit For Total Body:
0.39
- 1.9 x 10
- K
- Qu < 500 mrem /yr Limit ForSkin:
1.9 x 10
- S
- Qu < 3000 mrem /yr Where:
0.39 - gamma exposure rate finite cloud correction at 0.51 Km (nearest land site boundary) based upon 5 year joint frequency distribution average l
weighted stability class for 19751979 (See Appendix D). i 1.9 x 10 = average of the quarterly average maximum X/Q, sec/m* for a continuous mixed mode release (See Appendix D).
K = weighted average total body dose factor due to gamma emissions, mrem /yr per Cl/m*, as determined below.
S = weighted average skin dose factor due to beta and gamma emissions, mrem /yr per pCi/m*, as determined below.
Ou = release rate of noble gases in Ci/sec.
Ett3L1 Obtain results of the last analysis of the flashec gases from primary coolant, decay corrected to sample time. (In certain instances, e.g., high failed fuel fractions, the release rate may be based upon actual gas mixes present within the stack and not prompt flashed gas analyses. In these cases, the flashed gases analysis should only be calculated to determine the release rate limit for a prompt gas mixture release - Appendix D.)
1183L2 For each noble gas radionuclide identified in Step f, determine Fi. fraction nuclide i is of the total noble gas activity.
11R9.2 For each noble gas radionuclide identified in Step f, determine Ki (total body dose factor for noble gases) and Si (skin dose factor for noble gases) from Table f.
11tILi Determine K = I Fy K; i
D-1 D401XW.001
1 10/15/95 I Rcvision 3 ft.ttR !
- - Determine S = I F; Sg i
1112.1 Determine the release rate limit.
Qu ( Ci/sec) < 500 ,
0.39 x 1.9 x 104 x K Qu ( Ci/sec) < 3000 1.9 x 104*S whichever is lower.
N p.lt - See Appendix D forjustification of the method for determination of S and K (b) lodine and Particulate Release Rate Limit N.gte - See Appendix D for derivation of the following limits. All I release rates are in pCi/sec. l (1) Method 1 The dose rate to the maximum organ will be less than 1500 mrom/yr provided:
(a) Release 4 rate of I-131 + (2.4 x 10 x Release rate of I 133) + 8.5 x 10 x Release Rate of H 3 s 5 4
(b) Release rate of particulates + 8.2 x 10 x Release rate of H-3 <E 4.9 ff limits are exceeded, go to Method 2.
(2) Method 2 Above method assumes a conservative nuclide mix, if necessary, utilize the GASPAR code to determine the maximum organ dose. For the Special Location, enter 1.9 x 10* for the X/Qs, 6.6 x 10* for the resident D/Q and 4.5 x 10* for the milk D/Q (or use actual X/Q and D/Q data for each critical location). Note that only the ventilation pathway needs consideration.
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12/31/94 D.2 10CFR50 Anoendir I- Noble n== Limita l
- a. Quarterly Air Dose Limit Due to Noble nr 1 I~ (1) Method _1 stana Determine Cu which equals the total curies from all sources of noble gases released during the calendar quarter.
31293 Determine Dao which is the quarterly air gamma dose (mrad):
l DQAG = 9.8 x 10#*CN [See AppendixF) l II n.a Determine Das which is the quarterly air beta dose (mrad):
DOAB = 3.0 x 104*CN [See Appendix F)
EtRD (
If Due exceeds 3 mrad, go to Method 2.
(2) Method 2 This method to be used until the calculated gamma air dose exceeds 2.5 mrads or the beta air dose exceeds 5 mrads.
11921 Determine Ci which equals the total curies of each identified noble gas nuclide i released during the quarter from all sources, both continuous and batch.
E1891 Determine M which is the gamma air dose factor for each noble gas nuclide identified above. Values are given in Table 1.
1182 3 Determine M which is the beta air dose factor for each noble gas nuclide identified above. Values are given in Table 1.
3189.1 l
Determine Dma which equals the quarterly air gamma dose (mrad):
D-4 Dd81xW.001
12/31/94 Rsvision 2 DOAG = 2.7 x 104 *J Mg C;(See AppendxF]
( -- atana Determine Das which equals the quarterly air beta dose (mrad):
)
l Dag = 2.7 x 10 4 * { N C;[See g Appendix F) l 11aDJ If Do4a > 2.5 mrad or Doas > 5 mrad, go to Methods.
(3) Method 3 Use the GASPAR computer code to determine the critical site boundary air doses. For the Special Location, enter the following worst casa quarterly average meteorology:
X/O = 3.2 x 10sec/m*
D/Q = 1.1 x 10 m
If the calculated air dose exceeds one half the Technical Specification limit, use real time meteorology.
- b. Annual Air Dose Limit Due to Noble G====
Determine Dy4o and Dy4s which equals the gamma air dose and beta air dose for the calendar year as follows:
Dy4o = [ Do,o and Dy4s =1 Do s where the sum is over the first quarter through the present quarter doses.
The following should be used as Do4o and Do4s:
(f) If the detailed quarterly dose calculations required per Section D.5 for the Annual Radioactive Effluent Report are complete for any calendar quarter, use those results.
(2) If the detailed calculations are not complete for a particular quarter, use the results as determined above in Section D.2.a.
(3) If Dy4a > 10 mrad or Dy4 > 20 mrad and any corresponding quarterly dose was not calculated using Method 3 of Section D.2.a., recalculate the quarterly dose using Method 3 if this could reduce the annual dose below the allowablelimits.
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D.3.10CFR50 Aooendix l - lodine and Particulate Doses
- a. Quarterly Oraan Dose Limit (1) Method 1
) i This method to be used until the calculated maximum organ dose i exceeds 2.5 mrem.
=
Determine Cpt3s which equals the curies of I 131 and Ci.133 which equals the curies of I 133 released during the calendar quarter.
1tqg2 Determine CH which equals the curies of H-3 released during the I calendar quarter. '
M (
Determine Cp which equals the curies of all particulates with half-lives greater than 8 days released during the calendar quarter.
Steo 4 i
Determine DgT which is the quarterly thyroid dose as follows:
dot = 2.3 x 103 Cpt31 + 7.4 C.133 + 1.0 x 10 2 CH (See AppendixF)
Steo 5 Determine Doo which is the quarterly dose to maximum organ otherthan the thyroid:
Dqo = 805 Cp + 1.0 x 10-2 Cu (See Appendix F) 2 12.1 Maximum organ dose (Douo) equals the greater of D Q T or Doo. If either is greater than 2.5 mrem, go to Method 2.
(2) Method 2 Doses from vegetation consumption can be neglected during the 1st and 4th quarters and doses from milk consumption can be neglected during the first quarter. These time frames can be extended for short term releases (batch releases and weekly continuous, if necessary) if it can be '
verified that the milk animals were not on pasture and/or vegetation was not available for harvest. Therefore, calculate doses to the thyroid and maximum or
( when necessary. gan for pathways that actually exist. Sum pathway D-6
2/1/93 Rev.2 b
Perform Steps I through 3 as in Method 1, then:
1t.eg44 (See Appendix F for derivation of following factors)
Doo = 91 Cp + 4.1 x 10-3 CH iii. Milk Pathway Day = 2200 Cp:31 + 2 Ci.133 + 5.0 x 10 3 CH l Doo = 700 Cp + 5.0 x 10-3 CH Sum above athways, as appropriate (Ng.ft: t sum of a18 three pathways is Method 1l 1.1331 and }.13g1 are the same a. Method 1.
(3) Method 3 After reviewing the existing cow and goat farms, if it can be determined
( that the 1983-9987 D/Q data is acceptable (Note: if not, see guidance in Appendix F), then follow Method 2, above, except for lii, where:
Goat Milk Pathway Cow Milk Pathway DQT = 160 C .131 + 1.4 C3133 Dor = 134 C.131 + 1.2 Cpt33 +
+ 5.0 x 10-3 CH 2.4 x 10-3 CH Doo = 51 Cp + 5.0 x 10 3 CH Doo = 17 Cp + 2.4 x 10 3 CH
\
(See Appendix F for deriva tion of above factors.)
Note: During the 2nd and 3rd quarters also add (to the above) the inhalation and Vegetation Pathways from Ste during the 4th quarter add Inhalation pathway. p 4 of Method 2; (4) Method 4 The GASPAP. code can be used to determine the maximum quarterly organ dose. Real time meteorology shMd be used. (if not available, use worst case each lodir t $uarter as discussed in Appendix F.) Specific curies for particulate nuclide should be entered. Only those pathwe exampi ,idwhit are actually in existence at the time should be used (for
'.st use milk pathway in 1st quarter). Vegetation and milk pd%w; y wAes should be calculated only at real locations.
- b. An9ual C ,an Dose t.imit i
Determine Dyo which is the maximum organ dose for the calendar year as follows: -
Dyo = E Douo where the sum is over the first quarter through the present quarterdoses to the maximum organ.
D-1
keu.1
(_ D.4. Gaseous Effluent Monthly Dose Projections ' -
)
- a. Gaseous Radwaste Treatment System l 1
Sten.1 1
Estimate c ' which is the number of curies of gas to be discharged during N
the next month based upon the curies released in the present month assum- I ing typical operation (i.e., not shut down for refueling, long maintenance, etc.).
]
it_te 2 1
E Determine o which is the estimated monthly gamma air dose for process gas:
MAG Dyg = 9.8 z 10"
- C#y(mme Note - Factor from Appendix F, maximum gamma mrad per curie.
Step 3 ,
E Determine o which is the estimated monthly beta air dose for process gas:
MA8 D,,.g = 3.0 x 10-3
- Cy (mme
~
Note - Factor from Appendix F, maximum beta mrad per curie.
- b. Ventilation Releases
- i. Method 1 This methoci ratios a previously calculated organ dose (from D.3.a. -
Method 7 only) based upon primary coolant levels and primary coolant losses due to leakage.
Sten 1 For the last quarter of operation, determine Douo as determined per Section D.3.a.(1). (Note: Use Method 7 only.)
litEl Estimate Ri which is the expected ratio of primary coolant iodine level for the coming month as compared with the average level during the quarter used in Step 1.
D-8
12/31/94 Rsvision 2 ElRIL2 i
Estimate Ra which is the expected ratio of primary leakage rate for the l coming month ac compared with the average leakage rate during the (
quarter used in Step 1.
ElRELA Determine DL which is the estimated monthly dose to the maximum organ:
Dk = 1/ 3 R, R, D e na li. hfeth,0.Q If necessary, estimate curies expected to be released for the next month and applicable method for dose calculation from Section D.S.a.
D.5 Quarterly Dose Calculations for Annual Radim Detailed quarterly dose calculations required for the Annua / Radioactive Effluent Report shall i be done using the computer code GASPAR. The use of this code and required input parameters are given in Radiological Assessment Branch Procedure, Gaseous Dose-Calculations - GASPAR.
D.6 Comollance with 40CFR190 Limits I The following sources should be considered in determining the total dose to a real individual from urartium fuel cycle sources:
- a. CY gaseous doses - as calculated in Section D above.
- b. CY liquid doses - as calculated in Section C tbove.
c.
CY - direct radiation from the site. Since conservative calculations indicate that yearly site boundary dose will be less than 0.026 mrom, dose from this pathway will be at most a very small fraction of the total dose and hence need not be considered.
- d. Since all other uranium fuel cycle sources are greater than 20 miles away, they need not be considered.
(
D-9 Des 1XW.001
l Rev.' 1 TABLE 1 s _ .
DOSE FACTORS FOR NOBLE GASES (mrem /vr per uCi/m31 (mrad /vr per uCi/m31 Gamma Total Skin Gamma Air Beta Air Body Factor Factor Dose Factor Dose Factor Radionuclide Ki * *
- Si'* Mi'** Ni* "
Kr-83m 7.56 (-2)* 2.12 (1) 1.93 (1) 2.88 (2)
Kr-85m 1.17 (3) 2.81 (3) 1.23 (3) 1.97 (3)
Kr-85 1.61 (1) 1.36 (3) 1.72 (1) 1.95 (3)
Kr-87 5.92 (3) 1.65 (4) 6.17 (3) 1.03 (4)
Kr-88 1.47 (4) 1.91 (4) 1.52 (4) 2.93 (3)
Kr-89 1.66 (4) 2.91 (4) 1.73 (4) 1.06 (4)
Kr 90 1.56 (4) 2.52 (4) 1.63 (4) 7.83 (3)
Xe 131m 9.15 (1) 6.48 (2) 1.56 (2) 1.11 (3)
Xe-133m 2.51 (2) 1.35 (3) 3.27 (2) 1.48 (3)
Xe-133 2.94 (2) 6.94 (2) 3.53 (2) 1.05 (3)
Xe-135m 3.12 (3) 4.41 (3) 3.36 (3) 7.39 (2)
Xe-135 1.81 (3) 3.97 (3) 1.92 (3) 2.46 (3)
Xe-137 1.42 (3) 1.39 (4) 1.51 (3) 1.27 (4)
Xe-138 8.83 (3) 1.43 (4) 9.21 (3) 4.75 (3)
Ar-41 8.84 (3) 1.29 (4) 9.30 (3) 3.28 (3) 7.56 (-2) = 7.56 x 10 2
/ i
- Si = L; + 1.1 Mi from NRC proposed specifications, NUREG 0472, dated May 1978 where Li equals Beta Skin Dose Factor and Mi equals Gamma Air Oose factor irom Table 81 of Regulatory Guide 1.109, October 1977, Rev.1.
- " Derived irom Table B-1 of Regulatory Guide 1.109,0ctober 1977, Rev.
1, using appropriate conversion factors.
e i .
D-10
Rev.1 l TABLE 2 t
~~
i DOSE FA CTORS FOR IODINES & PARTICULATES Pi*
(mregr ser _
pg3rPer Radionuclide inhalation Vecetables Goat Milk Cow Milk H-3 1.3(3) 4.0 (3)** 4.9 (3)*
- 2.4 (3)*
- Cr-51 2.1(4) 6.4 (6)
Mn 54 2.0(6) 3.0 (9) i Fe 59 1.5(6) 6.8 (8)
Co-58 1.3(6) 3.8 (8)
Co-60 8.7(6) 2.1 (9)
Zn-65 1.2(6) 2.'2 (9) 1.9(10)
Rb 86 2.0(5)
Sr-89 2.4(6) 3.7 (10) 2.7(10) 1.3(10)
Sr 90 1.1(8) 1.25(12) 2.6(11) 1.2(11)
Y 91 2.9(6)
Zr-95 2.7(6)
Nb-95 7.5(5)
Ru-103 7.8(5)
Ru-106 1.6(7) 1.2(10)
Ag-110m 6.8(6)
Te-127m 1.7(6)
~
Te-129m 2.0(6)
Cs-134 1.1(6) 2.6(10) 2.0(11) 6.8(10)
Cs 136 1.9(5)
Cs-137 9.1(5) 2.4(10) 1.8(11) 6.0(10)
Ba-140 2.0(6) i Ce-141 6.1 (5) .
Ce-144 1.3(7) 1.0(10) 1-131 1.6(7) 2.2(10) 6.3(11) 5.3(11) 1-133 3.9(6) 4.0 (8) 5.6 (9) 4.7 (9)
- Pi are the inhalation and consumption factors derived from NRC Regulatory Guide 1.109, Rev. f. For inhalation, the teen is the critical age group for all nuclides except Rb 86, Cs-137,1-131, and 1-133, which are for the child. For vegetables, th'e child is critical; for milk, the infant. Maximum organs are: whole body for H-3, bone for Sr-90 and thyroid for 1-131,133.
~
- Same units as for Inhalation for H 3, based on NUREG 0133 assumptions.
D 11 h.
06/27/g7 Rev.3
{_ E. LIQUID MONITOR SETPOINTS E.1 Test Tank Discharoe Line Monitor The trip / alarm setting on the test tank discharge line monitor dcpends on dilution water flow, test tenk discharge flow, the isotopic composition of the Ibuid to be discharged, the background count rate of the monitor and the efficiency of the mcnitor. Due to the variability of these parameters, an alarm / trip setpoint will be determined prior to the release of each ;
batch. The following method will be used:
11tg 1 From the tank isotopic analysis and the MPC values for each identified nuclide, determine the required reduction factor:
. 1 R=
(C,I MPC,)
R = required redu: tion factor C, = concentration of nuclide I(pCi/ml)
MPC, = MPC value (10CFR20*, AppendixB, Table 2, Column 2 for all nuclides except d
noble gases. For noble gases, use 2 x 10 pCi/ml) for nuclide I(pCikni)
- *10CFR20 version prior to January 1,1992.
l 1113.2 Determine the existing dilution flow, D:
D = # of Cire. Pumps running x g3,000 gpm + # of service water pumps x 6,000 gpm D = existing dilution flow g3,000 gpm = flow from 1 circulating water pump 6,000 gpm = flow from i service water pump (Note 1) l Stan] Determine the maximum allowable discharge flow, F:
F =
0.1 x R x D (Note 2)
Stan.4 Determine the total gamma concentreben (A,) in the tank in pC1/ml:
A,(pCi/ml) = $
1 Where A, is the total concentration of gamma emitters in the tank and Cp the concentration I of gamma emitterI(Note 3).
Atta_5 Determine the monitor response, R. In epm corresponding to two times the total concentration determined in Step 4 (Note 4):
R. = E x 2 x A, j Where E is the current monitor oflidency kt epm por pCl/ml.
E-1 j l
I 06/27/g7 R:v.2
(_.
3.11 2.1 Determine the monitor response for worst case conditions, R,,, in epm (Note 5):
R,, = E x (1 x 10'8)
Steo7 Determine the alarm trip setpoint, S, in cpm:
IF Rm > R.,:
S = Rm + B IF R.,> Rm use either Option (1) or Option (2):
(1) S = Rm + B, or (2)*S=R,,+B Where B = background of the monitor in cpm. If background exceeds the monitor response (Rmor R,,) calculated prior to discharge, the monitor must be decontaminated prior to use. i
- If option (2) is used for alarm trip setpoint, perform the foliowing:
- 1. independent valve verification;
- 2. controls to ensure that the allowable discharge fichv is not exceeded, and
- 3. controls to ensure that the dilution flow is maintained.
M9.111:
- 1. The maximum capacity of the Service Water System is aWut 10,000 gpm for 2 or more pumps running. Although this could result in a potential non-conservative estimate of dilution flow, this is justified since there is a factor of five conservatism in the overall calculation methdology.
- 2. Discharging at this flow rate would yield a discharge concentration corresponding to 10%
of the Technical Specification limit due to the safety factor of 0.1.
- 3. Monitor response to gamma emitters is used to verify representatnreness of Chemistry sample. Compliane* with 10CFR20 limits on non gamma emitters is ensured with l Chemistry sample r /,utts and the maximum discharge flow of Step 3. '
- 4. If discharging at the allowable discharge rate as determined in Step 3, this would yield a discharge concentration corresponding to 20% of the Technical Specification limit.
- 5. This value is based upon worst case conditions, assuming a maximum discharge flow (50 gpm), minimum oilution flow (166,000 ppm) and an assumed worst case mix of nuc! ides (3 x 10 pCi/mi- Footnote 3.a. Appendix B,10CFR20). If noossaary, this value may be increased by factors to account for the actual discharge flow and actual dilution flow. Use of this value will assure that low level releases are not terminated due to small fluctuations in actMty.
E- 2
06/27/97 Rev. 2
(-
E.2 Steam Generator Blowdown Monitor Assumptions used in determining the ALARM setpoint fer this monitor are:
- a. Maxirnum possible liquid discharge rate = 43 GPM (maximum blowdown rate = 61 GPM of which 30% flashes to steam).
- b. Minimum possible dilution flow rata = 279,000 GPM (minimum of 3 cire. pumps during periods )
of blowdown). !
Therefore, alarm /setpoint should be:
4 279,000 S ( C/ / ml) = 1 x 10 x = 6.5 x 10" pC/ / ml 43 Using the monitor calibration curve, determine the CPM corresponding to 6.5 x 10$Cl/ml. The monitor alarm setpoint should be set at less than this corresponding value plus the background count rate.
E.3 Service Water Radiation MonKor Sten 1 Maximum possible service water flow, F., from potentially contaminated areas flowing past monitor =
6,000 GPM x # of service water pumps on.
F. = 0,000 GPM x # service water pumps on. ,
3.119 1 Dilution flow Fo = # Cire. Pumps x 93,000 SttD1 Worst case MPC* for unrestricted area = 3 x 10#pC1/ml (Note 1) l
- 10CFR20 version prior to January 1,1992.
Alta d Therefore, the maximum allowable corum (A) at the monlior should be:
A (pCf / ml) = 3 x 10-7 xE"+ #
Ps E- 3 i 1
3
06/27/97 Rev.0
(~
nita Determine the maximum allowable monitor response, R., in cpm:
i R = E x A (pCi/m!)
Where E is the current monitor of5ciency in epm per pCl/mt.
1112.1 Determine the alarm trip setpoint, S, in cpm:
IF cire water and service water systems are both in operation for tank discharges:
S = R, + B At all other times:
S = 3 x B (Note 2)
Where B = backg ound of the monitor in cpm. For tank discharges,if the background exceeds the monitor response (R.) calculated, the monitor must be decontaminated.
For all other times, if the background exceeds 400 cpm (Note 3) the monttor must be decontaminated.
fi9.tti:
- 3. 400 cpm is about 20% of the MPC for Co 137 (2 x 10dpCi/ml).
l E-4
Rsv.1
( --
F. GASEOUS MONITOR SETPOINTS l 1
F.1. Stack Neble Gas Activity Monitor '
1!tP1 1
As given in Section D.f.a. of thls manual, determine the noble gas release rate limit On in pCi/sec.
Step 2 Estimate maximum possible stark flow rate (Fs): ,
Fs (crJsec) = 1.2 x # purge fans x 52,000 CFM x 472 cc/sec/CFM.
i Where 52,000 CFM = Flow from one purge flow and 1.2 = conservative factor l for maximum possible flow.
FS = 3 x 107 x # purge fans (cc/sec)'
Step 3 Determine monitor alarm / trip setpoint S = Qs/Fs (pCi/cc) ,
1 Step 4 l
Using the monitor calibration curve, determine the CPM corresponding to S (pCi/cc). The monitor alarm setpoint should be set at less than this corresponding value. j
?
F F-1
Rev.1 APPENDIX A l
(- '
DERIVATION OF LIQUID DOSE FA CTORS FOR SECTION C.1.s
- 1. JUSTIFICATION FOR USING THE LAST FOUR YEARS OF DATA Dose Factors For Liould Releases Curies Dose (mrem)*
- Dose Per Curie Year Released
- Whole Body Max. Oraan Whole Body Max. Oraan 1968 3.9 7.7 5.4 2.0 1.38
& I 1969 12.8 4.1 2.99 0.32 0.23 1970 5.1 0.48 0.73 0.09 0.14 1 1971 5.85 2.7 4.3 0.46 0.74 1972 4.78 2.8 4.4 0.59 0.92 1973 3.04 4.5 7.2 1.48 2.37 1974 2.23 1.0 1.8 0.45 0.81 1975 1.24 0.81 1.2 0.65 0.97 1976 0.13 0.086 0.12 0.66 0.92 1977 1.95 0.56 1.32 0.29 0.68 1978 0.94 2.9 4.2 3.09 4.47 1979 0.87 0.58 '3.1 0.67 3.56 1980 0.28 1.0 1.4 3.57 5.00 ,
1981 0.71 0.61 1.4 0.86 1.97 1982 0.07 0.086 0.14 1.23 2.00 1983 0.48 0.71 1.0 1.48 2.08 1984 0.26 1.3 1.5 F.00 5.77 5 1985 0.08 0.13 0.18 1.62 2.25 1986 0.29 0.59 0.84 2.03 2.90 1987 0.43 0.93 1.28 2.16 2.98
- Calculated using actual nuclide release data and dilution flow rates in the LADTAP computer program.
The worst case year is 1984. Therefore,it is acceptable to evaluate only 1984 - 1987 in detail. .
1
. Rev.1
- 2. METHOD (1) - STEP 3
(_
- a. Whole Body Doces From Fission and Activation Products (Excluding Tritium)
Year Quarter Cg D ggg} Dg /Cg 1 0.010 2.14E-2 2.1
$gg4 2 0.010 2.68E-2 2.7 3 0.100 5.40E-1 5.4 4 0.124 5.09E-1 4.1 1 0.024 2.6E-2 1.1 1985 2 0.007 1.7E 2 2.4 3 '0.016 6.2 E-2 3.9 4 0.038 2.9E-2 0.8 1 0.017 7.46E-2 4.4 2 0.148 2.538-1 1.7 198G 3 0.101 1.06E-1 1.0 4 0.044 1.60E-1 3.6 1 0.057 1.86E-1 3.3 2 0.097 3.25E-1 3.4 1987 3 0.194 1.40E 1 0.7 4 0.079 2.74E 1 3.5 l 1
l CF - Curies of fission and activation products releases during calendar quarter. i l
Dgw(F) - Calculated whole body dose (mrem) to maximum individual due to fission and activation products. Dose calculated using ~
the computer code LADTAP.
Average value of Dow(p)over the period from 1978-1987 = 2.17 mrern/Ci Maximum value cf Dgw(p)/ Cp = 5.4 mrem /Ci Since the maximum is only 2.5 times the average, it is not overly conservative. Therefore, use the maximum value for C.I.a.(f) Step 3.
l
- b. Whole Body Doses FromTritium ,
CT - Curiesof tritium released during calendarquarter.
Ogw(T) - Calculated whole body dose (mrem) to maximum individual due to tritsum.
Since only one nuclide is used here, we can use a method in NRCRegulatory Guide f.109 and estimated conservative dilution flows.
i 2-
Rev.1
( ~~ D qwtTl =-
Dilution Volume x
factorfor H-3 "u""*"*'
. rate
~
Dose conversion I
- faet.orfortritium l l
1 l
1 C7(curies) 012pCi i
= x x 0.9 pCi/Kg x 21Kg V Gitern/ quarter) curie pCi/l yr l
yr i x x 1.05 x 10-7 mmm 1 4 quartem pCi l
C7(curies)
= 4.96 x 10, mrom V Giters)
Assuming only one circulation pump is in operation for the whole quarter (worst case).
4.96 x 10 6 -
D = 1.07 x 10-3 (Cy mrom og,.n = 4.64 x 10 g D ewen
- t. = 1 x 10_s mism / curie C7 4
3 f
Rsv.1 APPENDIX B
{_.
DERIVATION OF LIQUlO DOSE FACTORS FOR SEs~ TION C.1.b
- 1. JUSTlFICATION FOR USING THE LAST FOUR YEARS OF DATA See Appendix A.
- 2. METHOD (1) - STEP 3
- a. Maximum Organ Doses From Fission And Activation Products Maximum l y_e_E ' Quarter Cg Orcan D gg DC2 /Cg 1'
1 0.010 liver 2.89E-2 2.9 1984 2 0.010 liver 3.52 E-2 3.5 3 0.100 liver 7.85E-1 7. 9 4 0.124 liver 6.81 E-1 5.5 1 0.024 liver 3.5E-2 1.5 1985 2 0.007 liver 2.3 E-2 3.3 3 0.016 liver 8.3 E-2 5.2 4 0.038 liver 3.9 E-2 1.0 1 0.017 liver 1.04E-1 6.1 1986 2 0.148 liver 3.55E-1 2.4 ;
3 0.101 liver 1.49 E-1 1.5 ;
4 0.044 liver 2.31 E-1 5.3 l 1 0.057 liver 2.68E-1 4.7 l 1987 2 0.097 liver 4.67E-1 4.8 i 3 0.194 liver 1.94E-1 1.0 1 4 0.079 liver 3.47E-1 4.4 -
CF - Curies of fission and activation produ:ts releases during calendar quarter.
Dgo - Calculated dose (mrem) to the maximum adult organ; dose calculated using the computer code LADTAP.
Average value of Doo/Cp overthe period from 1978-1987 = 3.3 mrem /Ci l
Maximum value of Dgo/ Cp = 8.0 mrem /Ci or 2.4 x Average value j.
Sir ce the maximum is only 2.4 times the average, it is not overly conservative.
Therefore, use the maximum value for C.I.b.(f) Step 3. ,
. b. Maximum Organ Doses FromTritium According to the NRC Regulatory Guide f.fo9, all organs (including whole body) receive the same dose frorn tritium (all dose conversion factors are the same). Therefore, use:
U
. ksv.1 De r) / C T = 1x10-8 mrem / curie
. . 3 As shown in Appendix A. . l Cr - Curies of tritium released during calendar quarter.
i DQo(T) - Calculated dose (mrern to the maximum organ due to tritium).
I l
l i j l
I i
! I l
l l
I I 1 i
l .
l l
1 i
l . 1 a... .
APPENDIX C 1
{-
LIQUlO DOSE CALCULATIONS LADTAP
' The LADTAP code was written by the NRC to compute doses from liquid releases. The actual model used is LADTAP ll which performs calculations in accordance with Regulatory Guide 1.109, Revision 1.
For calculating the maximum individual dose from Haddam Neck, the following options and parameters are used: '
- 1. Real time, measured dilution flow
- 2. Fresh water site, no reconcentration
- 3. Shorewidth factor = 0.1 for discharge canal
- 4. No dilution for maximum individual pathways I
- 5. One hour discharge transit time - approximate time to reach 1/2 canal length
- 6. Regulatory Guide 1.109 usage factors for maximum individual for fish, shoreline, swimming and boating
- 7. Zero usage for shellfish, algae, drinking water, and irrigated food pathways O
w/15/05 Revisi n 3 8EEE.M DERIVATION OF FACTORS FOR SECTION D.1
- 1. SECTION a. - X/O VALUE l
Quarterly Averaae X/O's & D/O's i Nearest Land Nearest Resident Cow or Goat Maximum X/Q Maximum D/Q Maximum D/Q Year /QTR. Continuous galgb Continuous 33tgb Continuous 3.gigh l
1983- 1 1.1 (-5) 1.1 (-5) 6.0 (-8) 6.2 ( 8) 2 3.0 ( 5) 5.8 ( 5) 1.1 ( 7) U.8 (-8) 8.0 (-9) 5.4(9) 3 2.4 ( 5) 3.9 ( 5) 5.1 (-8) 2.7 (-8) 2.9 (-9) 2.7 ( 9) 4 1.1 ( 5) 1.4 (-5) 4.7 (-8) 3.0 (-8) 3.5 ( 9) 3.0 ( 9) 1984- 1 8.5 (-6) 9.6 (-6) 5.1 (-8) 8.6(-8) 2 2.6 ( 5) 9.7 ( 8) 3 7.3 (-9) 2.5 ( 5) 4.8 (-8) 3.9 (-9) 4 1.8 ( 5) 5.2 ( 5) 5.3 (-8) 3.2 (-7) 4.0 (-9) 2.4 ( 8) 1985- 1 1.5 (-5) 8.5 (-5) 6.9 (-8) 1.5 (-7) -
2 2.8 (-5) 9.4 (-8) 3 6.8 (-9) 3.2 ( 5) 7.1 (-8) 5.0 (-9) 4 1.3 (-5) 3.7 (-8) 3.7 ( 9) 1986 - 1 1.3 ( 5) 9.8 (-6) 7.9 (-8) 4.9 (-8) 2 2.0 ( 5) 1.9 (-5) 9.1 (-8) 9.7 (-8) 7.0 ( 9) 4.1 (-10) 3 2.9 ( 5) 1.8 ( 5) 7.3 (-8) 5.7 (-8) 5.6 (-9) 4.0 ( 9) 4 1.2 (-5) 1.2 ( 5) 4.2 (-8) 7.8 (-8) 2.8 ( 9) 4.3 ( 9) 1987 - 1 1.1 ( 5) 7.6 ( 6) 6.3 ( 8) 7.1 (-8) 2 1.7 (-5) 1.1 ( 5) 7.3 (-8) 5.7 (-8) 2.1 ( 9) 1.1 ( 9) 3 2.6 (-5) 4.1 ( 5) 7.1 ( 8) 4 1.2 (-7) 3.0(9) 5.2 (-9) 1.6 ( 5) 4.7 (-8) 1.5 ( 9)
Maximum Quarterly Average X/O - Continuous Releases = 3.2 x 10*
Maximum Resident Quartedy Average D/Q - Continuous Releases = 1.1 x 10 4 Maximum Milk Animal Quartedy Average D/Q - Continuous Releases = 8.0 x 10*
Average Maximum Quarterly Average X/Q - Continuous Releases = 1.9 x 10*
Average Ma::imum Quartedy Average X/Q - Batch Releases = 2.8 x 10 4 Average Maximum Resident Quarterty Average D/Q - Continuous Releases = 6.6 x 10 4 Average Maximum Resident Quarterly Average D/Q - Batch Releases = 9.1 x 10*
Average Maximum Milk Animal Quarterly Average D/Q - Continuous Releases = 4.5 x 10*
Average Maximum Milk Animal Quarterly Average D/Q - Batch Releases = 5.6 x 10*
'(
Dde1XW.001
fo/15/95 Revision 3 Although 10CFR20.106 tilows averaging concentrations of radioactive material over a period not greater than one year, this does not suggest that the worst case year should be p-
- used for release rate determinations. NUREG -0133 recommends that the STS considerl historical annual average atmospheric dispersion conditions. Therefore, average values from above are adequate for release rate c-.culations. This is conservative since the maximum quarterly averages are not typically at the same location.
2.
SECTION a. - JUSTIFICATION FOR METHOD USED TO DETERMINE K & S There are many different sources contributing to the releases from the ventilation stack. j These include releases from the building ventilation, condenser air ejector, containment j purges, flashed gases which occur while obtaining primary coolant samples, and discharges from the waste gas tanks. These sources may exist in any possible combination ar,d each has its own particular, but changing, nuclide mixture. Thus, the ratio of nuclides being released is a constantly changing parameter.
I' it is impractical to change the value of K(S) and thus the release rate limit and monitor setpoints cuh time a source stream is initiated or terminated or an isotopic analysis is performed on any of the source streams. Instead, we can choose a conservative value for K(S) such that whatever combination of source stream exists, the actual value of S or K will
{
be less than that assumed. I I
Table 1 indicates that the highest values of Ki(Sn occur for the shorter half life noble gases. i Therefore, the highest value of K(S) would be obtained with a sample having the least amount of decay. Thus, if we determine K(S) using the gas mixture in the primary coolant, ,
we will be conservative because the mixture from any other source will be decayed from this l value. (An actualisotopic mixture from the stack should be used to determine K and S from i normal releases during periods of high failed fuel fractions to prevent unnecessarily conservative limits. Any prompt releases should be based upon current primary flashed gas analyses however.)
3.
SECTION a. - DERIVATION OF FINITE CLOUD CORRECTION FACTOR N FREQUENCY DISTRIBUTION AT 196 FOOT LEVEL IQlN_T FRACTIONAL STABILITY CLASS M A 1 _Q ,, 1 .l E.&.ft 1975 0.082 0.061 0.065 0.373 0.313 0.100 1976 0.102 0.057 0.066 0.364 0.306 0.102 1977 0.094 0.048 0.060 0.336 0.324 0.119 1976 0.090 0.053 0.057 0.374 0.315 0.105 1979 0.098 0.056 0.066 0.433 0.271 0.074 h g. 0.093 0.055 0.063 0.376 0.306 0.100 t
Od417W.001 1
le /15/95 Rovision 3 i From 'M;t orologyand Atomic Energy,*1968, Figures 7.16 and A.2 with a cloud gamma energy of j 0.1 MeV, the finite cloud correction factors at 0.51 Km (distance to nearest land site boundary) are:
F- Stability Class A B., ,,,Q_ Q.,. _E., F Factor @ 0.51 Km 0.7 0.63 0.50 0.40 0.28 0.21 The weighted correction factoris:
t 0.093(0.70) + 0.55(0.63) + .063(.50) + .376(0.40) + .306(0.28) + .100(0.21) = 0.39. ;
- 4. l SECTION b. - DETERMINATION OF IODINE AND PARTICULATE RELEASE RATE LIMIT Doses are calculated using the methods of NUREG-0133 dated October 1978 and NRC Regulatory Guide 1.109, Revision 1. Note that the equation on page 27 of NUREG-0133 (for all radionuclides, except tritium) has been corrected for the elemental iodine fraction, as l in Regulatory Guide 1.109, Revision 1. For the instantaneous release rate limit, only the '
inhalation pathway needs to be considered. '
Method 1 Dose formula for iodine (both I-131 and 1-133)is:
D 7, . lX / Q x P, x Q,}
Inhalation where: DTi = thyroid dose rate from iodine releases (1 131 and 1-133)
Qi = release rate of each isotope of lodine, p X/O = meteorological dispersion factor, sec/m,Ci/sec P. = values derived from NUREG 0133 and Regulatory Guide 1.109 (see Table 2).
Dose formula for tritium is:
DTu = lXI Q x P x Qu]
inhalation where: DTy= thyroid (or any other organ) dose rate from tritiurn releases Qn = release rate of H-3, pCL/sec other parameters as described above.
Dose formula for particulates is:
DO, = (X / Q . P, . Q,}
where: DO, = maximum organ dose rate from particulate releases Q, = release rate of particulates, pCi/sec other parameters as described for iodine, above.
i 3
0481XW.001
iW15/95 R vision 3
- c. Thyroid Dos:s Method 1 304Quis$ + 74.1Q5,n + 0.025Qs 51500 0.20 Q6,33 + 0.049 Quin + 1.7 x 104 Qw 51 or 4
Quut + 0.24 Quin + 8.5 x 10 Qx5 5
- b. Oroan Doses (other than thyroid) l l
Method 1 3040, + 0.025 Qs 51500 .
0.20, + 1.7 x 10 Qs 51 or '
Q, + 8.2 x 10 Qs 5 4.9 5.
SECTION b. - DETERMINATION OF RELEASE RATE LIMITS - METHOD 2 Method 2, by use of the GASPAR code, eliminates some of this conservatism by calculating <
the dose to each organ using the dose factor for that particular organ for each nuclide, then the critical organ can be determined.
i 1
1 i
4 l
1 l
D401XW.001 9
Hee.1 APPENDIX E .
GASEOUS DOSE CALCULATIONS- GASPAR i
The GASPAR code was written by the NRC to compute doses from gaseous releases using ,
the models given in Regulatory Guide 7.109. The revision date of the code which was !
purchased is February 20,1976. The only changes made to the code were to change the dose factors and inhalation rates from those given in Rev. O of Regulatory Guide 7.709 to those in Rev. f.
For calculating the maximum individual dose from Haddam Neck, the following options and parameters are used:
- 1. Real-time meteorology using a X/Q, D/O model which incorporates the methodology of Regulatory Guide f.7 7 f. Meteorology is determined separately for continuous releases and batch releases 1
2.100% of vegetation grown locally,76% of vegetation intake from garden, harvest season from April through September
- 3. Animals on pasture Aprilthrough December- 100% pasture intake i
- 4. Air water concentration equals 8 g/m3
- 5. Maximum individual dca calculations are performed at the nearest land site boundary with maximum decayed X/Q, and at the nearest vegetable garden W (assumed to be nearest residence) and cow and goat farms with maximum D/Q's l l
i 1-i
Mttv. I 1 l
APPENDlX F DERIVATION OF FACTORS FOR SECTIONS D.2 & D.3**
- 1. SECTION D.2.a (1) -
' Noble Gas Air Doses {
Curies of Air Dose (mrad)* mrad per curie Year Quarter Noble Gas Gamma Beta Gamma Beta 1 825 0.087 0.251 1.1 (-4) 3.0 (-4) 1983 2 48 0.022 0.141 4.6 (-4) 2.9 (-3) 3 359 0.277 0.615 7.7 (-4) 1.7 (-3) 4 1530 0.353 0.866 2.3 (-4) 5.7 (-4) ,
1 1 1210 0.146 0.425 1.2 ( 4) 3.5 (-4) 2 3770 1.51 3.66 4.0 -4) 9.7 (-4) l 3gg4 ;
3 2540 0.893 2.84 3.5 -4) 1.1 (-3) l 4 3 0.002 0.006 6.7 (-4) 2.0 (-3) 1 172 0.169 0.511 9.8 (-4) 3.0 (-3) l 2 1040 ' O.555 1.23 5.3 (-4) 1.2 (-3) 1985 3 752 0.657 1.14 8.7 (-4) 1.5 (-3) 4 799 0.210 0.481 2.6 (-4) 6.0 (-4) 1 1730 0.257 0.788 1.5 (-4) 4.6 (-4) 2 62 0.012 0.044 1.9 (-4) 7.1 (-4) 1986 3 393 0.113 0.333 2.9 (-4) 8.5 (-4) 4 150 .0.026 0.076 1.7 (-4) 5.1 (-4) 1 63 0.007 0.019 1.1 (-4) 3.0 (-4) 1987 2 852 0.134 0.377 1.6 (-4) 4.4 (-4) 3 2670 0.929 2.83 3.5 (-4) 1.1 (-3) ~
4 0.2 5.9 (-6) 1.8 (-4) 3.0 ( 5) 9.0 (-4)
Avg. = 3.6 (-4) 1.1 (-3) .
l
- Calculated maximum air dose (mrad) due to noble gases calculated using NRC computer code GASPAR.
Average value of gamma air dose per curie = 3.6 x 104 mrad /Ci Maximum value of gamma air dose per curie = 9.8 x 104 mrad /Ci Riatio Maximum / Average = 2.7 Average value of beta air dose per curie = 1.1 x 10 3 mrad /Ci Maximum value of beta air dose per curie = 3.0 x 10 3 mrad /Ci Ratio Maximum / Average = 2.7 Therefore, use of the maximum observed values should only be a factor of three conservative on the average.
- All X/O and D/Q values are based upon mixed mode release per Regulatory Guide 1.111.
1
. Rdv.~1 )
l l
l
. 2. SECTION D.2.a (2) -
1 l
Appendix D lists the quarterly X/Q and D/O factors for 1983-1987. However, unlike j the should instantaneous be useo. For the limits where averaging period 1983-1987, is for this occurred acceptable, batch releases dun first quarter 1985 (FJQ = 8.5 x 10 5). -
(1) - STEP 4 DoAsi = Quarterly gamma air dose due to nuclide i
= C, (Ci) z M .* .
x 8.5 x 10-8 sec/m3 x yr pCi 10' pCi/Ci z 3.17 x 10-8 (yr/see)
As indicated above, the same X/Q can be used for both batch and continuous releases.
1 D g3g, a 2.7 x 10-6 M, C, Dq,c = E over all nuclidae = 2.7 x 10**
- M, C, t (2) - STEP S Likewise for the beta air dose, all factors are the same except the dose conversion factor Mi should be replaced by Ni.
Dq, = 2.7 z 10-8 [, N, C,
- 3. DERIVATION OF FACTORS FOR SECTION D.2.a (3)
X/Q = 3.2 x 10-5 sec/m3 D/Q = 1.1 x 10-7 m.2
- 4. DERIVATION OF FACTORS FOR SECTION D.3.a (1)
Doses are calculated using the methods of NUREG-Of 33 dated October 1978 and NRC Regulatory Guide f.109 Revision 1. Note that the equation on page 27 of NUREG-0133 (for all radionuclides, except tritium) has been corrected for the elemental iodine fraction, as in Regulatory Guide 7.109, Revision f. Since the locations of milk producing animals causes significant variations in the dose calculations (substantial variations in D/Q's), use 3 methods when performing these calculations.
Method 1 Assume worst case locations (i.e., milk animals located at maximum resident D/O
! location), vegetables harvested throughout the year, and milk animals on pasture throughout t,e year.
2-
~
2/1/93 Rsv. 2 Method 2 Assume worst case quarterly X/Q and D/Q as above, however:
- 1. If the 1st quarter, neglect vegetation and milk doses.
ii. If the 4th quarter, neglect vegetation doses.
iii. For batch releases (including weekly continuous releases, if necessary) evaluate other periods of time where the above may apply.
Method 3 Determine if the maximum quarterly D/Q data from Appendix D.1 is acceptable to use (i.e., no milk animal likelr to be more critical than the data for 1983-1987). If acceptable, use D/Q for mi k locations, if not, an acceptable D/Q for use is the wosst case quarter of at least the past three years. Also determine if goat or cow dose factors are to be used (N.httg: goat dose factors result in higher doses).
Dose formula foriodineis:
t D EIQ
- 06 . C, + DlQ . O g C, +
QT,
. = curies of each isotope of iodine released Ci
)
X/Q = meteorologicaldispersion factor,sec/m3 D/Q = deposition factor, m 2 Oi = Pi x 3.17 x 10-2*, mrem . m3/Ci . see for inhalation and mrem . m2/Ci . sec for food consumption Pi a values derived from NUREG 0133 and Regulatory Guide 1.109 (see Table 2)
- pCi/sec per Ci/yr conversion factor Dose formula for tritiumis:
D = XIQ
- Og Cy _, + +
QTy XIQ . Og . Cy _, XIQ Og Cy _,
inhalation Vegetation Milk where: Dorg,3 = quarterly thyroid (or any other organ) dose rate from tritium releases CH-3 = curies of tritium released other parameters as described above, except units for 0; and Pi. Since milk and vegetable doses from tritium are related to X/Q and not D/Q, use the units for inhalation (see NUREG-0133 and/or Regulatory Guide 1.109, Revision 1 for details).
( .
3
2/1/93 Rev.2 l
H
\ Dose formula for particulatesis:
D, q
= XIQ P Cpg + DlQ P g* Cp + DIQ P, . C, inhalation Vegetation Milk where: Doop = quarterly maximum organ dose from particulate releases Cp = curiesof particulatesreleased other parameters as described for iodine, above.
- i. Method 1 Using the worst case quarters as explained earlier and Pi s (conservative mix *)
from Table 2 results in:
D erg = 2.29 x 10 + a Cl-m + 24.9 Cl- m Dg,y. = 1.0 z 10 ~8 Cy ,,
D = 805 Cp
.
- For particulate doses use either Ru-106 or Cs-134 Pi values (whichever is greater). Review of the 1978 - 1988 effluent data shows that Sr 90 usually contributes to less than 2% of the total particulate curies (only 1st quarter 1987 exceeded this with 3.1% contribution by Sr-90). Therefore, this will usually result in a conservative calculation.
ii. Method 2 Use same formulas as for Method 7, however, delete vegetation and/or milk when applicable.
iii. Method 3 After review of existing cow and goat farms,if the D/Q for milk animals for the 1983-1987 data is determined to be acceptable, then:
Milk Pathway Doses-Goat:
Der = 160 Cy ,, + 1.4 Cl- m y
D erg; = 6.0 x 10-s C,,,
D = 51 C, i
2/1/93 Rev.2 Milk Pathway Doses-Cow:
DVig= 134 CI-nst + 1.2 CI-nse D = 2.4 s 10"* Cy _,
D !
- 7 =17C # l i
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5/30/97 !
Revision 6
( _. AEEEND'LG ENVIRONMENTAL MONITORING PROGRAM i I
Sampling Locations The following lists the environmental sampling locations and the types of samples obtained at each location. Sampling locations are also shown on Figures G 1, and G 2,.
Location Direction & Distance Number Hamt From Samnia Typen 1 Release Point"*
1 l* On site Mouth of Discharge Canal 1.1 Mi, ESE TLD 21 Haddam-Park Rd. 0.8 MI, S TLD 3-1 Haddam Jail Hill Rd. 0.8 Mi, WSW TLD 41 Haddam-Ranger Rd. 1.8 Mi, SW TLD, Air Particulate 51 On site injun Hollow Rd. 0.4 MI, NW TLD, Air Particulate 61 On stte Substation 0.5 Mi, NE TLD, Air Particulate, Vegetation 71 Haddam 1.8 MI, SE TLD, Air Particulate 81 East Haddam 3.1 Mi, ESE TLD, Air Particulate pl Higganum 4.3 Mi, WNW TLD, Air Particulate 10-1 Hurd Park Ro 2.8 Mi, NNW TLD 11 C" Middletown g.0 M1, NW TLD 12 C Deep River 7.1 Mi, SSE TLD 13-C North Madison 12.5 MI, SW TLD, Air Particulate 14 C Colchester 10.5 MI, NE TLD 15-1 On stte Wells 0.5 MI, ESE"" WellWater 16 C Well State Highway Dept. E. Haddam 2.8 Mi, SE WellWater 17 C Fruits & Vegetables Beyond 10 Miles Vegetation 18-l Site Boundary 0.4 M1, NW Vegetation 101 Cow Location e1 4.5 Mi, ENE Milk 201 Cow Location #2 8.0 M1, NE Mk 21 1 Cow Location e3 11.0 MI, SE idk 22 C Cow Location e4 11.0 Mi, ENE Mk 23-C Goat Location et 18.0 Mi, NNE Mk 24 l Goat Location e2 3.8 MI, SSE Mk 25 1 Fruits & V: 'etables Within to Miles Vegetation 26 1 Conn. Rive: Nest intake 1.0 MI, WNW Fish 27 C Conn. Riva! Higganum Light 4.0 Mi, WNW Shellfish 28 1 Conn. River E. Haddam Bridge 1.8 MI, SE Bottom Sediment, River Water 20-1 Vicinity of Discharge .. Bottom Sedimer t, Fish 30-C Conn. River Middletown g.0 Mi, N W River Water, Bottom Sediment 7.8 Mi, NW Fish 31 1 Mouth of Salmon River 0.8 Mi, ESE Sheafeh
'l = Indicator "C = Control .
"'The release points are the stack for terrestiallocations and the end of the discharge canalfor aquatic bestions..
""New wells at 0.4 miles SE may be used as a replacement for this location.
l APP. G 1 neuwmimoc
5/30/97 Revision 6 i- The following lists the accident TLD sampling locations. Sampling locations are shown on Figure G-3.
ACCIDENT TLD SAMPLING LOCATIONS l
l Direction LqsLQjg1Lqsg Location Description (Town and Street) 0.6 Mi, N Haddam Misck, Cove Road 4.0 Mi, N East H4ddam, Quitewood Road and Route 196 1
0.7 Mi, NNE Haddam Neck, Jenks Hill Road 1.3 Mi, NNE Leesville Substation, intersection of 151 and 196 4.8 Mi, NE Colchester, Waterhole Road 0.3 Mi, ENE Haddam Neck, Jenks Hill Road 4.4 Mi, ENE East Haddam, Falls Bashen Road 0.3 Mi, E Haddam Neck, Road to Canal l
4.4 Mi, E East Haddam, Smith Road 2.8 Mi, SE East Haddam, Creamery Road (off Route 82) 0.9 Mi, SSE Haddam, Route 9A, Comer of Plains Road 3.2 Mi, SSE Haddam, Old Chester Road 3.1 Mi, S Haddam, int. Turkey Hill and Dickinson Road 0.7 Mi, SSW Haddam, Route 9A, Parking Lot Agr. Building 5.2 Mi, SSW Killingworth, Parker Hill Road q
0.7 Mi, SW Haddam, Route 9A, Quarry Hill Road 4.0 Mi, SW Haddam, Route 81, North of Woods Road 3.2 Mi, WSW Haddam, Route 81, after Route 9 Underpass 0.9 Mi, W Haddam, Route SA, South End of Walkely Hill 1.1 Mi, W Haddam, Island Dock Road 4.6 Mi, W Haddam, Spencer Rud 1.2 Mi, WNW Haddam, Route 9A, North of Town Dump 0.7 Mi, NW Haddam Neck,injun Houow Road 4.6 Mi, NW Middletown Maromasith&-$elTower 1.0 Mi, NNW Haddam Neck, Ague Spring Road )
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i
. Rav.1 APPENDIX H DERIVATION OF FACTORS FOR TABLE 2*
\
( .- .
- 1. Vegetation Factors
- a. H 3 -
R, = K3Kit U /, + U f, DFL,, 0.75 (0.5 / H From page 36 of NUREG-0133 KI = 10' DFL y _3 = 2.03 x 10-7 K33 = 108 f, = 1.0 U[ = 26 (forchud) f, = 0.76 U[ = 520 (forchud) H = 8 g/m 8 s 3 3 R, = lo 10 26 (1.0+ 520f.762.03 z 10-7 0.75 x 0.5 / 8 = 4.01 z 10
- b. lodine-131,133 (r) - 1 8' R,Y DlQ = K' DFL, , U (, e O.5 v.(A, + x.)
from page 35 of NUREG Of 33, except last term was deleted since it is negligible for iodine-131 and 133 and accounting for elemental iodine fraction. -
i KI = 108 U, = 26 (child), 64 (adult) ' l r = 1.0 /, = 1.0 1
Y, = 2 A, = 9.97 x 10- 7 l-131 A, = 9.35 x 10-s 1-133 DFL = 5.72 x 10-3 f I-131 l
l DFL = 1.36 x 10-8 l- 133 4, = 8.6 z 10' ase A, = 5.73 x 10 ~7 )
I W .
2 f jA + A, I l
l 1-
I. -
Rev.1 APPENDIX H (Ccnt'd.)
l
'$~ for 1-131: i s I R, = 10 = 2.17 z 10 1 1
2(1.57 z 10-8) z 5.72 x 10-8 f 26 z for 1-133:
l 8 l R, = 10 z 1.36z10-3 26 x 0.4475 2 9.92 x 10-6 (0.5
= 3.99 z 10s = 4.0 x 10s l c. Sr 90 (c) -1
' +U -i.' ,h RY DIQ = K' DFl , , U{ f, e f, e Y, ( A, + A From page 35 of NUREG-0133 l
K' = 10s Uf = 26 (child),64 (adult)
I r = 0.2 U, = 520 (child),520 (adult)
Y, = 2 /, = 1.0
~
A, + A, = 5.738 z 10~7 f, = 0.76 DFL3 ,,, = 1.70 x 10-2 (child) Aj = 7.85 x 10-80 8
= 7.85 x 10-8 (adult) t, = 8.6 z 10 ase s
tg = 5.16 z lo ,,,
e
- 1 ,i = 1=c - 1.' A 8
D/Q = 10 8 1.7 z 10-2 1 x 26 R,P +f.76x520
' 2 f 5.738 x 10-7
= s 2... z lo (2. 3 5.2) = 1.2. z 10 2 2-
1/1/90 Rev.1 APPENDIX H (Cent'd.)
i j m l
\ 2. Milk Factors .
l a. H-3 P, = K' K F, Q, U, DFL, 0.75 (0.5/H)
From page 27 of NUREG-0133 K' = 108 U, = 330 (forin/ ant)
K"' = 103 gm/Kg DFL. = 3.08 x 10-7 l
F, = 0.17 (forgoat) H=8 Q = 6 (forgoat) f l
8 P, = 10 -
10' O.17 6 330 f 3.08 x 10-7 z
= 4860 (forgoat) l
! = 2400 (formw - ase NUREG -0133 )
. l l b. lodine - 131,133 K' Q, U, rF, 1.' 'I l P. = DFL. e
- 8 Y
p A. + A w a
4 t
from page 26'of NUREG 0133, however, multiply this by 0.5 elemental iodine iraction per guidance in NRCRegulatory Guide 1.109, page 26.
1 i Y , = 0.7 F, = 0.06 1
s r = 1.0 for nodme if = 1.73 z l o ,,,
A; = 9.97 z 10-7 for I-131 DFLi-us = 1.39z10-2 A, = 9.35 x 10-s for 1-133 DFL i- m = 3.31 x 10-8
-I A, = 5.73 z 10-7 ase and other factors as shown above.
3-
- U1/90 Rev.1
, APPENDIX H (Cont'd.)
l .
l4 for1131:
i 1
P, = 7.5 x 10** e ~dI = 7.5 x 10** x 0.842 = 6.32 x 1011 l for 1-133: -
~
P, = 2.83 z 10 (e ' 'I) = 2.83 x 10 '(0.198 3
= 5.62 x 10' t Sr 90 l
l Same equation as for iodines, except disregard elemental iodine fraction and:
l A; = 7.85 x 10-I' A, + A, = 5.738 x 10-7 ,
r = 0.2 DFL,_, = 1.85 x 10-*
F, = 0.014 (forgoat) rF "
P.' = 2.83 z 10' e 1' o/
A, + A, DFL i
\
- A t'
= 2.6 x 10 1
= 2.55 x le" z (e l
l l
Comparisons of calculations performed using these values with calculations from GASPAR (NRC computer code) verify these factors.
l 4
e
-