ML18018B099
| ML18018B099 | |
| Person / Time | |
|---|---|
| Site: | Nine Mile Point  |
| Issue date: | 12/31/1999 |
| From: | Niagara Mohawk Power Corp |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| Download: ML18018B099 (56) | |
Text
Page 1 of 2 NINEMILEPOINT NUCLEARSTATION - UNIT2 SEMI-ANNUALRADIOACTIVEEFFLUENT RELEASE REPORT JULY - DECEMBER 1999 SUPPLEMENTAL INFORMATION
~Faeilit:
Nine Mie Point Unit 42 Licensee:
Niagara Mohawk Power Corporation 1.
TECHNICALSPECIFICATION LIMITS A)
FISSION AND ACTIVATIONGASES 1.
The dose rate limitof noble gases released in gaseous effluents from the site to areas at or beyond
, the site boundary shall be less than or equal to 500 mrem/year to the whole body and less than or equal to 3000 mrem/year to the skin.
2.
The air dose from noble gases released in gaseous effluents from Nine Mile Point Unit 2 to areas at or beyond the site boundary shall be limited during any calendar quarter to less than or equal to 5 mrad for gamma radiatien and less than or equal to 10 mrad for beta radiation, and during any calendar year to less than or equal to 10 mrad for gamma radiation and less than or equal to 20 mrad for beta radiation.
B&C) TRITIUM,IODINES AND PARTICULATES, HALFLIVES ) 8 DAYS 1.
The dose rate limitof Iodine-131, Iodine-133, Tritium and all radionuclides in particulate form with half-lives greater than eight days, released in gaseous effluents from the site to areas at or beyond the site boundary shall be less than or equal to 1500 mrem/year to any organ.
2.
The dose to a member of the public from Iodine-131, Iodine-133, Tritium and all radionuclides in particulate form with half-lives greater than eight days in gaseous effluents released from Nine Mile Point Unit 2 to areas at or beyond the site boundary shall be limited during any calendar quarter to less than or equal to 7.5 mrem to any organ and, during any calendar year to less than or equal to 15 mrem to any organ.
D)
LIQUIDEFFLUENTS 1.
The concentration of radioactive material released in liquid effluents to unrestricted areas shall be limited to the concentrations specified in 10 CFR Part 20, Appendix B, Table II, Column 2 for radionuclides other than dissolved or entrained noble gases. For dissolved or entrained noble
- gases, the concentration shall be limited to 2E-04 microcurie/ml total activity.
2.
The dose or dose commitment to a member of the public from radioactive materials in liquid effluents released from Nine Mile Point Unit 2 to unrestricted areas shall be limited during any calendar quarter to less than or equal to 1.5 mrem to the whole body and to less than or equal to 5 mrem to any organ, and during any calendar year to less than or equal to 3 mrem to the whole body and to less than or equal to 10 mrem to any organ.
Page 2 of 2 2.
MEASUREMENTS AND APPROXIMATIONSOF TOTALRADIOACTIVITY Described below are the methods used to.measure or approximate the total radioactivity and radionuclide composition in effluents.
A)
FISSION ANDACTIVATIONGASES Noble gas effluent activity is determined by on-line gamma spectroscopic monitoring (intrinsic germanium crystal) of an isokinetic sample stream.
B)
IODINES a
Iodine effluent activity is determined by gamma spectroscopic analysis (at least weekly) of charcoal cartridges sampled from an isokinetic sample stream.
C)
PARTICULATES Activityreleased from the main stack and the combined Radwaste/Reactor Building vent is determined by gamma spectroscopic analysis (at least weekly) of particulate filters sampled from an isokinetic sample stream and composite analysis of the filters for non-gamma emitters.
D)
TRITIUM Tritiumeffluent activity is measured by liquid scintillation or gas proportional counting of monthly samples taken with an air sparging/water trap apparatus.
E)
LIQUIDEFFLUENTS Isotopic contents of liquid effluents are determined by isotopic analysis of a representative sample of each batch and composite analysis of non-gamma emitters.
F)
SOLID EFFLUENTS Isotopic contents of waste shipments are determined by gamma spectroscopy analyses of a representative sample of each batch.
Scaling factors established from primary composite sample analyses conducted off-site are applied, where appropriate, to find estimated concentration of non-gamma emitters.
For low activity trash shipments, curie content is estimated by dose rate measurement and application of appropriate scaling factors.
ATTACHMENT 1 Summar Data Page 1 of 2 Unit 1 Unit 2 X
Liquid Effluents Reporting Period Jul - December 1999 10CFR20, Appendix B, Table II, Column 2 Average MPC - pCi/ml (Qtr. 3)
~ 12ZUQ Average MPC - pCi/ml (Qtr. 4)
~ 2 BM Average Energy (Rsslon and Activation gases
- Mev):
Liquid Qtr. 3 Qtr. 4 By
%2Z)&1 Be 19'}
By 5QL Bo a
Number of batch releases Total time period for batch releases (hrs)
Maximum time period for a batch release (hrs)
Average time period for a batch release (hrs)
Minimum time period for a batch release (hrs)
Total volume of water used to dilute the liquid effluent during release period (L)
Total volume of water available to dilute the liquid effluent during reporting period (L)
Gaseous (Emergency Condenser Vent):
Not Applicable.for Unit 2 Number of batch releases Total time period for batch releases (hrs) 3" Qtr 3" Qtr 1H~
N/A N/A 4~ Qtr 1 ZSM+
4~ Qtr Maximum time period for a batch release (hrs):
N/A Average time period for a batch release (hrs)
N/A Minimum time period for a batch release (hrs):
N/A Gaseous (Primary Containment Purge):
Number of batch releases Total time period for batch releases (hrs) 1J)2F~2 Maximum time period for a batch release (hrs)
Average time period for a batch release (hrs)
Minimum time, period for a batch release (hrs)
SJ)Q~
ATTACHMENT1 Summar Data Page 2 of 2 Unit 1 Unit 2 X
Reporting Period Jul - December 1999 Abnormal Releases:
There were no abnormal releases during the reporting period.
A.
Liquids:
Number of releases 0
Total activity released NIA Ci B.
Gaseous:
Number of releases 0
Total activity released N/A Ci
ATTACHMENT2 Unit 1 Unit 2~
Reporting Period GASEOUS EFFLUENTS SUMMATIONOF ALLRELEASES, ELEVATEDAND GROUND LEVEL
~r4 aamm.
QQhBIEB QlhBIEB MB~o v
1 1.
Total release 2.
Average release rate
~I 1.
Total Iodine-131 2.
Average release rate for period G
pG/sec Ci pG/sec 3,81M LE&5 1 LM 2BE5 5.00E+01 3.00E+01 QIItlI;~ta ~~
1.
Particulates with half-lives >8 days 2.
Average release rate for period 3.
Gross alpha radioactivity Ci pG/sec G
XMHli
- iSMZ, 1HM 3.00E+01 2.50E+01 E.
twtlqm'.
Total release 2.
Average release rate for period 1
Percent of Quarterly Gamma AirDose Umit (5 mrad)
Percent of Quarterly Beta AirDose Umit (10 mrad)
Percent of Annual Gamma AirDose Umitto Date (10 mrad)
Percent of Annual Beta AirDose Umitto Date (20 mrad)
Percent of Whole Body Dose Rate Umit (500 mrem/yr)
Percent of Skin Dose Rate Umit (3000 mrem/yr)
G pG/sec
- LEUC, 512',
1&02 19229 LZtUQQ 1 ZGM Q,ZUQ 1*1M 5.00E+01 Percent of Quarterly Dose Umit (7.5 mrem)
Percent of Annual Dose Umit (15 mrem)
Percent of Organ Dose Rate Umit (1500 mrem/yr)
RZQM 1J,QM 2 RE92 292' BM 2'&%
Concentrations less than the lower limitof detection of the counting system used are indicated with a double asterisk.
Tritium, Iron-55 and Strontium 89 and 90 results for the fourth quarter were not received from the off-site vendor at the time of this report. These numbers Include estimates.
Actual numbers willbe provided in the next Semi-Annual Report.
ATfACHMENT3 Unit 1 Unit 2~'eporting Period GASEOUS EFFLUENTS ELEVATED RELEASE Nuclides Released 1 Halg~m Argon-41 Krypton-85 Krypton-85m Krypton-87 Krypton-88 Xenon-127 Xenon-133 Xenon-133m Xenon-135 Xenon-135m Xenon-137 Xenon-138 Ci Ci Ci G
Ci G
G G
G G
Q G
CONTINUOUS MODE
~BI U
VM1 XllM 368~9 44 44 44
- 2. ~l Iodine-131 Iodine-133 Iodine-135 G
Ci Ci Strontium-89 Strontium-90 Cesium-134 Cesium-137 Cobalt-60 Cobalt-58 Manganese-54 Barium-Lanthanum-14 Antimony-125 Niobium-95 Cerium-141 Cerium-144 Iron-59 Cesium-136 Chromium-51 Zinc-65 Iron-55 Molybdenum-99 4,~
G G
G G
G G
Q G
G Q
G Q
Ci G
G Ci Q
Q Ci 44 4 jg 4 lg 9 KHZ 4g
'4 lg Ig 4 4
44 g lg 4W 44 R'ilk'oncentrations less than the lower limitof detection of the counting system used are Indicated viith a double asterisk.
A lower limitof detection of 1.00E-04 qCI/ml for required noble gases, 1.00E-11 pQ/ml for required particulates, 1.00E-12 pCI/ml for required Iodines, and 1.00E-06 pCI/ml forTritium, as required by Technical Specifications, has been verified.
Tritium, Iron-55 and Strontium 89 and 90 results for the fourth quarter were not received from the off-site vendor at the time of this report. 'These numbers Include estimates.
Actual numbers willbe Included In the next Semi-Annual Report.
Contributions from purges are Included.
ATTACHMENT4 Unit 1 Unit 2~
Reporting Period GASEOUS EFFLUENTS - GROUND LEVELRELEASES CONIINUOUS MODE BATCH MODE There were no batch Releases during the Reporting period.
~rL
~th QLlhBIEB QllLiiBIKB Argon-41 Krypton-85 Krypton-85m Krypton-87 Krypton-88 Xenon-133 Xenon-133m Xenon-135 Xenon-135m Xenon-137 Xenon-138 Xenon-127 0
0 Ci Ci0 CI00 CI CI Ci 4t 4W sg 48 g4 g4 s '4 44 4 lit 2.
Iodine-131 Iodine-133 Iodine-135 Ci Ci Ci 3.
Bdbzhte
'trontium-89 Strontium-90 Cesium-134 Cesium-137 Cobalt-60 Cobalt-58 Manganese-54 Barium-Lanthanum-14 Antimony-125 Niobium-95 Cerium-141 Cerium-144 Iron-59 Cesium-136 Chromium-51 Zinc-65 Iron-55 Molybdenum-99 Silver-110m 2
0 Ci0000000 0
0000 Ci CI CI 00 Ci g '4
&2M sg 44 g '4
- IQZUU, ZZM 2'&%
2JNEKi RSEQ%
%~i Concentrations less than the lower limitof detection of the counting system used are indicated with a double asterisk.
A lower limitof detection of 1.00E-04 qG/ml for required noble gases, 1.00E-11 pCI/ml for required particulates, 1.00E-12 pG/ml for required lodlnes, and 1.00E-06 pCI/ml forTritium, as required by Technical Specifications, has been verified.
Tritium, Iron-55 and Strontium 89 and 90 results for the fourth quarter were not received from the off-site vendor at the time of this report. These numbers indude estimates, and actual numbers willbe Induded In the next Semi-Annual Report.
Unit 1 Unit 2~
ATTACHMENT5 Reporting Period Pa eiof2 A.
LIQUIDEFFLUENTS SUMMATIONOF ALLRELEASES ESL QLULI~
Qll$3IKB IQIhL JZEQB 0/
B.
E.
1.
Total release (not including Tritium, gases, alpha) 2.
Average diluted concentration during reporUng period 1
1.
Total release 2.
Average diluted concentration during reporting period a
i 1.
Total release 2.
Average diluted concentration during reporting period I
1.
Total release 1.
Prior to diluUon 2.
Volume of dilution water used during release period 3.
Volume of diluUon water available during reporting period I
Percent of Quarterly Whole Body Dose Umit (1.5 mrem)
Percent of Quarterly Organ Dose Umit (5 mrem)
Percent of Annual Whole Body Dose Umitto Date (3 mrem)
Percent ofAnnual Organ Dose Umitto Date (10 mrem)
Percent of 10CFR20 ConcentraUon Umit Percent of Dissolved or Entrained Noble Gas Umit (2.00E-OW pG/ml)
Ci pG/ml Ci FG/ml Q
pCI/ml Uters Uters Liters 2ZiM 60E+
LZiEL1 1J 9M 129F~+
L!QM 5.00E+01 5.00E+01 5.00E+01 5.00E+01 1.00E+01 5.00E+01 5.00E+01 Iron-55, StronUum 89 and 90 and Tritium results for the fourth quarter were not received from the off-site vendor at the Ume of this report. These numbers include esUmates, and actual numbers willbe included in the next Semi-Annual Report.
The percent of 10CFR20 concentraUon limitis based on the average concentraUon during the quarter.
Concentrations less than the lower limitof detecUon of the counting system used are Indicated with a double astensk.
A iower limitof detection of 5.00E-07 qQ/ml for required gamma emitUng nuclides, 1.00E-05 qQ/ml for required dissolved and entrained noble gases and Tritium, 5.00E-08 pG/ml for Sr-89/90, 1.00E-06 qQ/ml for Fe-55 and 1.00E-07 pG/ml for gross alpha radioactivity, as required by Technical Sped ficaUons, lias been verified.
ATTACHMENT5 Pa e2of2 Unit 1 Unit 2~
Nuclides Released
'trontium-89 Strontium-90 Cesium-134 Cesium-137 Iodine-131 LIQUIDEFFLUENTS RELEASED
~ll QLSKIEB Ci 000 Ci Reporting Period BATCH MODE WS 44 Cobalt-58 Cobalt-60 Iron-59 Zinc-65 Manganese-54 Chromium-51 0
0 Ci Ci Ci Ci 11'?2
.%2M 9~2 ShXSHR Zirconium-Niobium-95 Molybdenum-99 Technetium-99m Barium-Lanthanum-14 Cerium-141 Ci0000 44 44 Tungsten-187 Arsenic-76 Iodine-133 Iron-55 Neptunium-239 Praseodymium-144 Iodine-135 Silver-110m Dissolved or Entrained Gases Ci Ci 00 CI 000 2di229 44 44 44 44 44 Tritium Concentrations less than the lower limitof detection of the counting system used are Indicated with a double asterisk.
A lower limitof detection of 5.00E-07 qCI/mi for required gamma emitting nudides, 1.00E-OS pG/ml for required dissolved and entrained noble gases and Tritium, 5.00E-08 pQ/ml for Sr-89/90, 1.00E-06 pQ/ml for Fe-55 and 1.00E-07 qG/ml for gross alpha radioactivity, as required by Technical Specifications, has been verified.
Iron-55, Strontium 89 and 90 and Tritium results for the fourth quarter were not received from the off-site vendor at the time of this report. These numbeis Indude estimates, and actual numbers willbe induded In the next Semi-Annual Report.
'o continuous mode releases occurred during the reporting period.
ATTACHMENT6 Pa eiof6 Unit 1 Unit 2~
A.1 APE SOLID WASTE AND IRRADIATEDFUEL SHIPMENTS:
Viol m
(m')
C~la Reporting Period 1
(CI)
- 1. Spent Resin Spent Bead Resin (Dewatered)
Filter Sludge Concentrated Waste Evaporator Bottoms Total
- 2. Dry Active Waste (Contaminated Equipment and Compactible Trash)
- 3. Irradiated Components W. Other:
(to vendor for processing or consolidation) a.
Resins (Dewatered) b Dry Active Waste (Compactible and Non-Compactible)
UZI~
MM2 The estimated total error Is 5.00E+01%.
No items from Unit 2 were placed In Interim storage at Unit 2
ATTACHMENT6 Pa e2of6 Unit 1 Unit 2~
A.1
'TYPE Reporting Period SOLID WASTE AND IRRADIATEDFUEL SHIPMENTS Solidilication 1.
Spent Resin Spent Sead Resin (Dewatered)
Rlter Sludge Concentrated Waste 2.
Dry Active Waste (Contaminated Equipment and Compactible Trash) 3.
Irradiated Components:
There were no shipments 4.
Other:
a.
Resins (Dewatered).
b.
Dry Active Waste (Compactible and Non-Cornpactible)
ATTACHMENT6 Pa e3of6 Unit 1 Unit2~
Reporting Period SOLID WASTE AND IRRADIATEDFUEI. SHIPMENTS A.2 ESTIMATEOF MA3OR NUCLIDECOMPOSITION (BY'TYPE OF WASTE) a.
Spent Resins, Filter Sludges, Concentrated Waste:
~I (1) Zn-65 (2) Co-60 (3) Mn-54 (4) Other Pmcnt 7.26E+01 1.80E+01 5.80E+00 3.60E+00 b.
Dry Active Waste (Contaminated Equipement and Com
~lu (1) Co-60 (2) Zn-65 (3) Mn-54 (4) Fe-55 (5) Cr-51 (6) Fe-59 (7) Co-58 (8) Other pactible Waste)
CuuS 3.24E+01 3.16E+01 2.32E+01 3.87E+00 3.83E+00 2.19E+00 1 ~ 13E+00 1.78E+00
- c. Irradiated Components:
'There were no shipments.
d.
Other:
'1
~
Resins (Dewatered)
Hudlde (1) Zn-65 (2) Co-60 (3) Mn-54 (4) Fe-55 (5) C-14 (6) Other Pmuh 4.86E+01 2 42E+01 1.60E+01 6.37E+00 1.29E+00 3.54E+00 2.
Dry Active Waste (Compactible and Non-Compactible)
EaJida (1) Co-60 (2) Zn-65 (3) Mn-54 (4) Cr-51 (5) Fe-55 (6) Fe-59 (7) Co-58 8 Other BmS 3.21E+01 3.15E+01 2.32E+01 4.20E+00 3.84E+00 2.31E+00 1.16E+00 1.69E+00
0
ATTACHMENT6 Pa e4of6 Unit I Unit 2~
Reporting Period SOUD WASTE AND IRRADIATEDFUEL SHIPMENTS A.3.
SOLID WASTE DISPOSmON Barnwell Facility BarnMLN~
CNSI Consolidation Facility fhomuJI~
GTS Duratek QalSEMIIa35 B.
IRRADIATEDFUEL SHIPMENIS (DISPOSITION):
There were no shipments.
ATTACHMENT6 Pa e5of6 Unit 1 Unit 2~
Reporting Period SOLID WASTE AND IRRADIATEDFUEL SHIPMENTS C.
SOLID WASTE SHIPPED OFF.SITE TO VENDORS FOR PROCESSING AND SUBSEQUENT BURIAL Below is a summary of NMP-2 radwaste burled by vendor facilities during
. These totals were reported separately from "10CFR61 Solid Waste Shipped for Burial" since (a) waste dassification and burial was performed by the vendors, and (b) Technical Specification 6.9.1 requires reporting of "information for each dass of solid waste (as defined by 10CFR61) shipped off-site during the reporting period." 'The following data represents the actual shipments made from the off-site vendors of our radwaste (e.g., non-compacted trash, dry non-compactible waste) that was processed and.commingled prior to burial.
C.l.
TYPE OF WASTE - noncompacted trash and/or dry non-compactible waste, spent resins, non-combustible components processed by vendor facilities prior to burial ~
Burial Volume Activity Est. Total ZtmrJh XXK++1 129kUQ RKE~
C.2.
ESTIMATEOF MAIORNUCUDE COMPOSITION (1) Zn-65 (2) Co-60 (3) Mn-54 (4) Fe-55 (5) C-14 (6) Other C.3.
SOLID WASTE DISPOSITION
ATfACHMENT6 Pa e6of6 Unit I Unit 2~
Reporting Period SOLID WASTE AND IRRADIATEDFUEL SHIP MENTS D. SEWAGE WASTES SHIPPED TO ATREATMENTFACILITYFOR PROCESSING AND BURIAL There were no shipments of sewage sludge with detectable quantities of plant-related nuclides from NMP to the treatment facilitydu ing the reporting period.
ATt'ACHMENT7 Unit 1 Unit 2~
Reporting Period
SUMMARY
OF CHANGES TO THE OFF-SITE DOSE CALCULATIONMANUAL The Unit 2 Off-Site Dose Calculation Manual (ODCM) was revised during the reporting period to suppo* the abandonment/retirement of the (LWS) waste evaporator and the floor drain filter and associated equipment.
'The ODCM changes willnot reduce the accuracy or reliabilityof the dose calculations or setpoint determinations in accordance with Technical Spedfications.
A copy of the ODCM, Revision 16 is attached and a summary of the changes presented to and approved by the Station Operations Review Committee in December 1999 is provided below. The summary also includes the justification for the changes.
Old Page ¹ 11 9, 11 80, 11 82-86 New Page ¹
'II 9g II 80g II 82-86 Section ¹ 1.5 Appendix D Diagrams Change Page 11 9 deleted reference to the Waste Evaporator In 1.5.2 and 1.5.3 and the footnote under Section 1.5.
Page II 80 deleted the diagram reference for the "Waste Evaporator" intake to the Waste Collection System.
Reason for Change This change:
1.
Incorporates the abandonment/retirement of the LWS waste evaporator.
2.
'Updates the figures to reflect abandonment/retirement of the floor drain filterand associated equipment.
Pages II82 and 83 deleted multiple references to the "Waste Evap and Waste Evap Dist" Cooler on the diagrams.
Also added "Condensate Demineralizers as an Intake on the header upstream of AOV25 on page 11 83 diagram.
3.
Updates the figures to show that the floor drain collection system takes inputs from the condensate deminerallzer (CND) system.
Page II 84 deleted the 8ody Feed Tank and Pump and the Filter Precoat Tank and Pump sections from the Floor Drain Filter System diagram.
Page 11 85 deleted "Regeneration" from the "Cond Demln" system intake upstream of AOV-3W. Also deleted "Waste Evap" from the valve AOV 92 outlet.
Page II 86 changed the diagram title to "Regenerant Evaporator
.System
ATfACHMENT8 Unit 1 Unit 2~
Reporting Period
SUMMARY
OF CHANGES TO THE PROCESS CONTROL PROGRAM There were no changes to the Unit 2 Process Control Program during the reporting period.
0
ATTACHMENT9 Unit I Unit 2~
Reporting Period
SUMMARY
OF INOPERABLE MONITORS There were no inoperable monitors for a period greater than 30 days during the reporting period.
ATTACHMENT10 Page 1 of 4 SEMI-ANNUALRADIOACTIVEEFFLUENT RELEASE REPORT (1999)
NINEMILEPOINT NUCLEARSTATION UNIT2 DOSES TO MEMBERS OF THE PUBLIC DUE TO THEIR ACTIVITIES INSIDE THE SITE BOUNDARY JANUARY-DECEMBER 1999 Doses to members of the public (as defined by the Technical Specifications) from the operation of the NMP2 facility as a result of activity inside the site boundary are based on activities at the Energy Center located approximately one quarter mile west of NMP1. This facility is open to the public and offers educational information, summer picnicking activities and fishing. Any possible doses received by a member of the public by utilizing the private road that transverses the east and west site boundaries are not considered here since it takes a matter of minutes to travel the distance.
The activity at the Energy Center that is used for the dose analysis is fishing near the shoreline adjacent to the NMP site.
Dose pathways considered for this activity include direct radiation, inhalation and external ground (shoreline sediment or soil) doses.
Other pathways, such as ingestion pathways, are not considered because they are either not applicable, insignificant, or are considered as part of the evaluation of the total dose to a member of the public located off-site. In addition, only releases from the NMP2 stack and vent were evaluated for the inhalation pathway.
The direct radiation pathway is evaluated in accordance with the methodology found in the Off-Site Dose Calculation Manual (ODCM). This pathway considers three components: direct radiation from the generating facilities, direct radiation from any possible overhead plume and direct radiation from plume submersion.
The direct radiation pathway is evaluated by the use of high sensitivity environmental Thermoluminescent Dosimeters (TLDs). Since any significant fishing activity near the Energy Center occurs between Aprilthrough December, environmental TLD data for the approximate period of April 1 - December 31, 1999 were considered.. Data from environmental TLDs from the approximate area where the fishing occurs were compared to control environmental TLD locations for the same time period.
The average fishing area TLD dose rate was 7.8E-03 mRem per hour for the period.
The average control TLD dose rate was 6.5E-03 mRem per hour for the period (approximate second, third and fourth calendar quarters of the year).
The average increase in dose as a result of fishing in this area at a conservative frequency of eight hours per week for thirty-nine weeks is 4.0E-01 mRem from direct radiation for the period in question.
The majority of the dose from this pathway is from the NMP1 facility because of its proximity to the fishing area.
A small portion may be due to the NMP2 facility.
ATTACHMENT10 Page 2 of 4 SEMI-ANNUALRADIOACTIVEEFFLUENT RELEASE REPORT (1999)
NINE MILEPOINT NUCLEARSTATION UNIT2 DOSES TO MEMBERS OF THE PUBLIC DUE TO THEIR ACTIVITIES INSIDE THE SITE BOUNDARY JANUARY-DECEMBER 1999 The inhalation dose pathway is evaluated by utilizing the inhalation equation in the ODCM, as adapted from Regulatory Guide 1.109.
The equation basically gives a total inhalation dose in niRem for the time period in question (Aprii-December).
The total dose equals the sum, for all applicable radionuclides, of the NMP2 stack and vent release concentrations, times the average NMP2 stack and vent flowrate, times the applicable five-year average calculated X/Q, times the inhalation dose factors from Regulatory Guide 1.109, Table E-7, times the Regulatory Guide 1.109 annual air intake, times the fractional portion of the year in question.
In order to be slightly conservative, no radiological decay is assumed.
1999 calculation utilized the following information:
NMP2 Stack:
Unit 2 average stack flowrate = 5.25+01 m'/sec X/Q value = 9.60E-07 (annual NWN sector, historical average)
Inhalation dose factor = Table E-7 of Regulatory Guide 1.109 Annual air intake = 8000 m'er year (adult)
Fractional portion of the year = 0.0356 (312 hours0.00361 days <br />0.0867 hours <br />5.15873e-4 weeks <br />1.18716e-4 months <br />)
I-131 = 1.35E-01 pCi/m'-133
= 1.17E+00 pCi/m'e-55
= 3.57E-02 pCi/m'r-89
= 1.77E-01 pCi/m'-3
= 1.04E+04 pCi/m'o-60
= 7.36E-03 pCi/m'n-65
= 6.77E-02 pCi/m'r-90
= 4.03E-04 pCi/m's-134
= 3.19E-02 pCi/m'n-54
= 1.51E-02 pCi/m'
ATTACHMENT10 Page 3 of 4 SEMI-ANNUALRADIOACTIVEEFFLUENT RELEASE REPORT (1999)
NINE MILEPOINT NUCLEARSTATIONUNIT2 DOSES TO MEMBERS OF THE PUBLIC DUE TO THEIR ACTIVITIES INSIDE THE SITE HO~i'DARY JANUARY-DECEMBER 1999 NMP2 Vent:
~
Unit 2 average vent flowrate = 1.02E+02m'/sec
~
X/Q value = 2.8E-06 (annual historical average)
~
Irhalation dose factor = Table E-7 of Regulatory Guide 1.109
~
Annual Airintake = 8000 m'er year (adult)
~
Fractional portion of the year = 0.0356 (312 hours0.00361 days <br />0.0867 hours <br />5.15873e-4 weeks <br />1.18716e-4 months <br />)
~
Zn-65 = 2.51E-01 pCi/m' H-3 = 8.46E+02 pCi/m' Sr-89 = 3.08E-03 pCi/m' Sr-90 = 4.06E-04 pCi/m' Fe-55 = 8.05E-02 pCi/m' Co-60 = 1.27E-01 pCi/m' Mn-54 = 9.47E-02 pCi/m' Cr-51 = 1.56E-02 pCi/m'he inhalation dose to a member of the public from NMP2 as a result of activities inside the site boundary is 4.6E-05 mRem to the lung (maximum organ dose) and 3.5E-05 mRem to the whole body.
The dose from standing on the shoreline while fishing is based on the methodology in the ODCM, as adapted from Regulatory Guide 1.109.
During 1999, it was noted that fishing was peiformed from the shoreline on many occasions although waders were also utilized. In order to be conservative, it is assumed that the maximum exposed individual fished from the shoreline at all times.
The use of waders, of course, would result in a dose of zero from this pathway.
The ODCM equation gives the total dose to the whole body and skin from the sum of all plant-related radionuclides detected in shoreline sediment samples.
The plant-related radionuclide concentration is adjusted for background sample results, as applicable.
The equation, therefore, yields the whole body and skin dose by multiplying the radionuclide concentration adjusted for any background data (as applicable), times a usage factor, times the sediment or soil density in grams per square meter (to a depth of one centimeter), times the applicable shore width factor, times the regulatory guide dose factor, times the fractional portion of the year over which the dose is applicable.
In order to be conservative and to simplify the equation, no radiological decay is assumed since the applicable radionuclides are usually long lived.
ATTACHMENT10 Page 4 of 4 SEMI-ANNUALRADIOACTIVEEFFLUENT RELEASE REPORT (1999)
NINEMILEPOINT NUCLEARSTATION UNIT2 DOSES TO MEMBERS OF THE PUBLIC DUE TO THEIR ACTIVITIES INSIDE THE SITE BOUNDARY JANUARY-DECEMBER 1999 The calculation utilized the following information:
e Usage factor = 312 hours0.00361 days <br />0.0867 hours <br />5.15873e-4 weeks <br />1.18716e-4 months <br />
~
Density in grams per square meter = 40,000
~
Shore width factor = 0.3
~
Whole body and skin dose factor for each radionuclide = Regulatory Guide 1.109, Table E-6
~
Fractional portion of the year =
1 (used average radionuclide concentration over total time period)
'k
~
Average Cs-137 concentration = 0.21 pCi/g The total whole body and skin dose from standing on the shoreline to fish is 3.3E-03 mRem whole body and 3.8E-03 mRem skin dose for the period.
Doses to members of the public relative to activities inside the site boundary from aquatic pathways other than ground dose from shoreline sediment/soil are not applicable.
In summary, the total dose to a member of the public as a result of activ'ities inside the site boundary from the direct radiation, inhalation and shoreline dose pathways is 4.0E-01 mRem to the whole body and 4.6E-05 mRem to the maximum exposed internal organ (lung). The dose to the skin of an adult is 3.8E-03 mRem.
These doses are generally a result of the operation of NMP2. However, a portion of these doses for the direct radiation pathway may be attributable to the NMP1 facility.
ATTACHMENT11 Page 1 of 4 SEMI-ANNUALRADIOACTIVEEFFLUENT RELEASE REPORT (1999)
NINE MILEPOINT NUCLEARSTATIONUNIT2 DOSES TO MEMBERS OF THE PUBLIC DUE TO THEIR ACTIVITIES OUTSIDE THE SITE BOUiiBARY JANUARY-DECEMBER 1999 Radiation doses to the likely most exposed member of the public outside of the site boundary are evaluated relative to 40CFR190 requirements.
The dose limits of 40CFR190 are 25 mRem (whole body or organ) per calendar year and 75 inRein (thyroid) per calendar year.
The intent of 40CFR190 also requires that the effluents of NMP2, as well as other nearby uranium fuel cycle facilities, be considered.
In this case, the effluents of NMP1, NMP2 and the James A.
FitzPatrick (JAF) facilities must be considered.
Doses to the likely most exposed member of the public as a result of effluents from the site can be evaluated by using calculated dose modeling based on the accepted methodologies of the facilities'ff-Site Dose Calculation Manuals (ODCMs) or may, in some cases, be calculated from the analysis results of actual environmental samples.
Acceptable methods of calculating doses from environmental samples are also found in the facilities'DCMs.
These methods are based on Regulatory Guide 1.109 methodology.
Dose calculations from actual environmental samples are, at times, difficultto perform for some pathways.
Some pathway doses should be estimated using calculational dose modeling.
These pathways include noble gas air dose, inhalation dose, etc.
Other pathway doses may be calculated directly from environmental sample concentrations using Regulatory Guide 1.109 methodology.
Since the effluents from the generating facilities are low, the resultant gaseous and liquid effluent doses are anticipated to be low. In view of this, doses can be based on calculated data.
Doses are not based on actual environmental data for 1999 with the exception of doses from direct radiation, fish consumption and shoreline sediment.
In addition, in order to be conservative and for the sake of simplicity, it is assumed in the dose calculations that the likely most exposed member of the public is positioned in the maximum receptor location for each pathway at the same time. This approach is utilized because the doses are very low and the computations are greatly simplified.
0
Page 2 of 4 ATTACHMENT11 SEMI-ANNUALRADIOACTIVEEFFLUENT RELEASE REPORT (1999)
NINEMILEPOINT NUCLEARSTATIONUNIT2 DOSES TO MEMBERS OF THE>> PUBLIC DUE TO THEIR ACTIVITIES OUTSIDE THE SITE BOUNDARY JANUARY-DECEMBER 1999 The following pathways are considered:
1.
The inhalation dose is calculated at the critical residence because of the high occupancy factor. In order to be conservative, the maximum whole body and organ dose assumes no correction for residing inside a residence.
2.
The milk ingestion dose is calculated utilizing the critical milk cow location.
As noted previously, in order to be conservative and for the sake of simplicity, the likely most exposed member of the public is assumed to be at all critical receptors at one time. In this case, the member of the public at the critical residence is assumed to consume milk from the critical milk location.
3.
The maximum dose from the milk ingestion pathway as a result of consuming goat's milk is based on the same criteria established for item "2", above (ingestion of cow's milk).
4.
The maximum dose associated from consuming meat is based on the critical meat animal.
The likely most exposed member at the critical residence is assumed to consume meat from the critical meat animal location.
5.
The maximum site dose associated with the consumption of vegetables is calculated from the critical vegetable garden location.
As noted previously, the likely most exposed member of the public is assumed to be located at the critical residence and is assumed to consume vegetables from the critical garden location.
The dose, as a result of direct gamma radiation from the site, encompasses doses from direct "shine" from the generating facilities, direct radiation from any overhead gaseous plumes, plume submersion and from ground deposition.
This total dose is measured by environmental TLDs. The critical location is based on the closest year-round residence from the generating facilities as well as the closest residence in the critical downwind sector in order to evaluate both direct radiation from the generating facilities and gaseous plumes as determined by the local meteorology.
During 1999, the closest residence and the critical downwind residence were at the same location.
Page 3 of 4 ATTACHMENT11 SEMI-ANNUALRADIOACTIVEEFFLUENT RELEASE REPORT (1999)
NINE MILEPOINT NUCLEARSTATION UNIT2 DOSES TO MEMBERS OF THE PUBLIC DUE TO THEIR ACTIVITIES OUTSIDE THE SITE BOUNDARY JANUARY-DECEMBER 1999 7.
The measured average dose rate for 1999 at the critical residence was 13.9 mRem/qtr.
The average control dose rate was also 13.9 mRem/qtr.
The dose at the critical residence can be considered representative of the background dose since the control location dose rate and the critical residence dose rate were the same, Therefore, no net dose was calculated and was assumed to be zero for this pathway.
The dose, as a result of fish consumption, is considered as part of the aquatic pathway.
The dose for 1999 is calculated from actual results of the analysis of environmental fish samples.
For the sake of being conservative, the average plant-related radionuclide concentrations were utilized from fish samples taken near the site discharge points.
The only plant-related radionuclide detected in fish samples was Cs-137.
This nuclide was detected in one sample taken from Nine Mile Point. Utilizing the methodology given in the ODCMs, as adapted from Regulatory Guide 1.109, doses were calculated.
The calculations yielded doses of 3.7E-02 mRem to the liver and 2,4E-02 mRem to the whole body.
The shoreline sediment pathway is considered relative to recreational activities.
The dose due to recreational activities from shoreline sediment is based on the methodology in the ODCM, as adapted from Regulatory Guide 1 ~ 109.
The ODCM gives the total dose to the whole body and skin from the sum of plant-related radionuclides detected in actual shoreline sediment samples.
The plant-related radionuclide concentration is adjusted for background sample results, as applicable. The total whole body and skin dose from shoreline recreational activities are 2.5E-04 mRem whole body and 2.9E-04 mRem skin dose for the period.
In summary, the maximum dose to the likely most exposed member of the public is 4.2E-02 mRem to the thyroid (maximum organ dose) and 4.2E-02 mRem to the whole body. It should be noted that the maximum organ dose and maximum whole body doses are based on the sum of the maximum doses observed for all three facilities regardless of age group.
This results in some conservatism.
The maximum organ and whole body doses were a result of gaseous effluents.
0
ATTACHMENT11 Page 4 of 4 SEMI-ANNUALRADIOACTIVEEFFLUENT RELEASE REPORT (1999)
NINE MILEPOINT NUCLEARSTATION UNIT2 DOSES TO MEi>IBERS OF THE PUBLIC DUE TO THEIR ACTIVITIES OUTSIDE THE SITE BOUNDARY Doses as a result of liquid effluents were secondary.
The total whole body and skin dose from shoreline recreational activities are 2.5E-04 mRem whole body and 2.9E-04 mRem skin dose for the period.
The direct radiation dose to the critical residence from the generating facilities was insignificant or zero.
The dose to an individual as a result of fish consumption was 3.7E-02 mRem to the liver and 2.4E-02 mRem to the whole body.
These maximum total doses are a result of operations at the NMP1, NMP2 and the JAF facilities. The maximum organ dose and whole body dose are below the 40CFR190 criteria of 25 mRem per calendar year to the maximum exposed organ or the whole body, and below 75 mRem per calendar year to the thyroid.
ATTACKI4ENT12 Update of Actual Data for the Second Quarter 1999
't1 U 't2~
Reporting Period UPDATE OF RELEASE AND DOSE DATAFOR GASEOUS (ELEVATEDAND GROUND LEVEL)AND LIQUIDEFFLUENTS Update of data using actual results from the off~ite vendors for Strontium, Tritium, and Iron-55 for the second quarter 1999.
nJ GASEOUS LIQUID Sr-89 Sr-90 H-3 Fe.55
- 1. Particulates viith half-lives >8 days
- 2. Average release rate (gaseous) or diluted concentration (liquid) for reporting period
- 1. Total release
- 2. Average release rate for period (gaseous) or diluted concentration (liquids) for the reporting period pCi/sec (gaseous) pG/ml (liqu!d)
Cl pCl/sec (gaseous) pCl/ml (liquid) 22&H 2'~i
, MM WiM 2 'ilEQZ
- 1. Percent of Quarterly~ Dose Umit
- 2. Percent of Annual'ose Umit to Date
- 3. Percent of Organ-Dose Rate Umit (Gaseous) (Quarterly)
- Dose Umit (Uquid)
(Quarterly &Annual
- 4. Percent of 10CFR20~
Concentration Umit (Uquld),
- 5. Percent of Dissolved or Entrained Noble Gas (Uquid)
'k&Q (Quarterly) 2dHIUQ (Annual)
LDM (Quarterly)
HLh (Annual)
Hlh M1KM (Quarterly) 2 21&91 (Annual)
XIHEJ?1 (Quarterly) 28Ml (Annual)
Concentrations less than the lower limitof detection, as required by Technical Specifications are indicated with a double asterisk.
The dose is to the whole body for liquid eNuents and to the maximally exposed organ for gaseous eNuents.
The percent of the 10CFR20 concentration limitis based on the average concentration during the quarter.