ML20207T698
| ML20207T698 | |
| Person / Time | |
|---|---|
| Site: | Maine Yankee |
| Issue date: | 12/31/1986 |
| From: | Whittier G Maine Yankee |
| To: | Vollmer R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| References | |
| 7269L-DS, GDW-87-44, MN-87-23, NUDOCS 8703240255 | |
| Download: ML20207T698 (64) | |
Text
{{#Wiki_filter:. f EFFLUEllT AtlD HASTE DISPOSAL SEllIAllflVAL REPORT FOR THIRD Afl0 FOURTil QUARTERS,1986 IllCLUDIl1G AtlNUAL RADIOLOGICAL IllPACT Oft MAtl FOR 1986 Maine Yankee Atomic Power Company flaine Yankee Atomic Power Station lliscasset, Maine 8703240255 861231 9 DR ADOCK 0500 qh
) 2 TABLE OF CONTENTS Pace 1.0 INTR 000CTION..................................................... 1 2.0 M ET EOROLOGI CAL DATA . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3 3.0 DOSE ASSESSMENT.................................................. 4 1
3.1 ' Doses From Liquid Effluents................................ 4 3.2 Doses From Noble Gases..................................... 5 3.3 Doses from Iodine-131 Iodine-133, Tritium, and Radionuclides in Particulate Form Hith Half-Lives
. Greater Than 8 Days........................................ 6-REFERENCES....................................................... 8 TABLES........................................................... 9 APPENDIX A Radioactive Liquid Effluent Monitoring Instrumentation...................................... A-1 7.
APPENDIX B Radioactive Gaseous Effluent Monitoring Instrumentation...................................... B-1 APPENDIX C Radiological Environmental Monitoring Program.,....... C-1 APPENDIX D Unplann,ed Radioactive Effluent Releases............i. D-1 - APPENDIX E Land Use Census.................'...................... E-1 APPENDIX F Liquid Radwaste Treatment System..................... F-1 APPENDIX G Gaseous Radwaste Treatment System.................... G-1 APPENDIX H Off-Site Dose Calculation Manua1..................... H-1 APPENDIX I Lower Limits of Detection for Radiological Analyses................................ I-l APPENDIX J Reactor Coolant System Activity...................... J-l 5143R f b t e-,
i a y LIST OF-TABLES kumb.itt Tit 1e Pa9a a. in. ' 57 N , (; 1A' Gaseous Effluents - Summation Of All Releases 9 U
' ' 1B Gaseous Effluents - Elevated Releases 10
.,i
' 1C-Gaseous Effluents - Routine Ground Level Releases 11 1
2A '_ Liquid Effluents - Summation Of All Releases 12 28 0- Liquid. Effluents - Routine Releases 13
"~ ~ 3 ,7 Solid Haste and Irradiated Fuel Shipments 14 4 '
-Supplemental Information 15 E!'S . Maximum Off-Site Doses and Dose Commitments to Members of-Q c. , ,
, the Public .
18
, 6A to 6H . Upper Level Joint Frequency Distribution -
January - December _1986 19 t y l i : y l i4
~
,\
2 l
'n 4
m., i f. l I l i-i f I
., -111-5143R f:
r.
-y y--
n > MAINE YANKEE ATOMIC POWER STATION SEMIANNUAL EFFLUENT RELEASE REPORT JULY - DECEllBER 1986
1.0 INTRODUCTION
Tables 1 through 4 list the recorded radioactive liquid and gaseous effluents and solid waste for the second six months of the year, with data summarized on a quarterly basis. Table 5 summarizes the estimated radiological dose commitments from all radioactive liquid and gaseous effluents released during the year 1986. Table 6 reports the cumulative joint frequency distributions of wind speed, wind direction, and atmospheric stability for the 12-month period, January to December 1986. Radioactive effluents reported in the Semiannual Effluent Report covering the first six months of the year were used to determine the off-site doses for the first half of 1986 and are included for completeness, even though the Technical ) Specification changes requiring dose analysis to be reported were not implemented until July 1,1986, half-way through this annual pe:iod. As required by Technical Specification 5.9.1.6 dose commitments resulting from the release of radioactive materials in liquids and gases were estimated in accordance with the "llaine Yankee Atomic Power Station Off-Site Dose Calculation Manual" (0DCM) under a " Method II" analysis. A " Method II" analysis incorporates the methodology of Regulatory Guide 1.109 (Reference 1) and uses measured meteorological data recorded at the plant site during the reporting period. Meteorological conditions concurrent with the reported release of radioactive materials were used for determining the gaseous pathway doses. The dose impact analysis also included an assessment of the dose from radioactive effluents to commercial worm diggers on the tidal flats of Montsweag Bay (Bailey Cove), taking into account appropriate occupancy factors associated with this activity in the site vicinity. All calculated dose estimates for this reporting period are below the dose criteria of 10 CFR Part 50, Appendix I. 5143R
Appendices A through I indicate the status of reportable items per the requirements of Technical Specifications 3.16.C, 3.17.D, 3.28. A 3.28.B, 4.8.A 4.13, and 5.9.1.6. 5143R
i,: :o 2.0 = METEOROLOGICAL DATA Meteorological data was collected during the reporting period from the site's 200-foot meteorological tower located along the access road. The tower instrumentation is designed to meet'the requirements of Regulatory' Guide 1.23. (Reference 2) for meteorological monitoring. The main release point for gases discharged from the plant is via the
-176-foot primary vent stack, located between the reactor containment and the primary auxiliary building. The primary vent stack is treated as a mixed mode elevated release point dependent upon windspeed as described in Regulatory Guide 1.111 (Reference 3).
X/Q and D/Q values were derived for'all receptor points from the site meteorological record 'using a straight line air flow model. All dispersion and deposition factors have been calculated employing appropriate' source configuration considerations and removal mechanism (e.g., dry deposition) described in Regulatory Guide 2.111 (Reference 3). Terrain elevations for the surrounding area were factored into the calculation of X/Q and D/Q values at each receptor location. 5143R
.m .
y : c> 3.0 DOSE ASSESSMENT 13.1 Doses from Liauid Effluents-1 Technical Specification 3.16.B, limits total body (1.5 mrem per quarter,
.and 3 mrem per year) and organ doses (5 mrem per quarter, and 10 mrem per
- year) frora liquid effluents to a member of the public to those specified in 10 CFR Part 50, Appendix I. By implementing the requirements of Technical Specification 3.16, assurance is provided that the release of radioactive material in liquid effluents will be kept as lou as is reasonably achievable."
Exposure pathways .that could exist as a result of liquid effluents are ingestion of fish and shellfish, and direct exposure from shoreline sedimentation. The potable water pathway and the irrigated foods pathway are not considered since the receiving water is not suitable for either drinking or' irrigation. The direct exposure to worm diggers on tidal flats has been-accounted for. with an occupancy factor of 325 hours per year (0.037). The dose analysis for the fish and shellfish pathways assumes a 10 to 1 dilution based on the discharge of effluents via a submerged multiport diffuser which extends approximately 1,000 feet into the tidal estuary. For shoreline direct exposure, a dilution ratio of 25 to I has been applied. The resultant whole body and organ doses from liquid effluents were , determined by summing the contributions from all pathways. The whole body and organ doses to a member of the public from liquid effluents are given in Table 5. The estimated quarterly and annual doses due to liquid effluents are below the 10 CFR Part 50, Appendix I dose criteria of Technical Specification 3.16.B. 5143R
.s'
.b' 3.2 Doses From Noble Gases Technical Specification 3.17.B limits the gamma air dose (5 mrad per quarter, and 10 mrad per year) and beta air (10 mrad per quarter, and 20 mrad per year) dose from noble gases released 'in gaseous effluents from the site to areas at and beyond the site boundary. to those specified in 10 CFR Part.50, Appendix I. By implementing' the requirements of Technical Specification 3.17,
. assurance is.provided that the releases of radioactive noble gases in gaseous )
effluents will be kept "as low as is reasonably achievable."' Dose estimates due to the release of noble gases to the atmosphere.were calculated at the site boundary, tidal mud flats, nearest residents (including l l vegetable gardens), and nearest milk animal in each of the sixteen principle l compass directions, as well as the approximate point of highest off-site p ground level. air concentration of radioactive materials. The beta air dose determination utilizes a semi-infinite cloud model. l The gamma dose was calculated using a finite cloud sector average model with a Gaussian distribution of. activity in.the vertical plane. The gamma radiation received from the cloud at a point of interest was determined by integrating the contribution from a differential volume over the entire cloud, taking into account the geometry of the cloud, variation in concentration, attenuation by the interaction of photons with matter in the path between the source and
; receptor point, and scattering of radiation from material outside the direct path to the point of interest. No additional credit was taken for decay of radionuclides in transit to the receptor point.
The estimated quarterly and annual gamma and beta air doses at the point of highest off-site exposure are listed in Table 5. The estimated gamma and beta air doses due to noble gases released in gaseous effluents are below the 10 CFR Part 50, Appendix I dose criteria of Technical Specification 3.17.B. 5143R
3.3 Doses From Iodine-131. Iodine-133. Tritium. and Radionuclides in Particulate Form Hith Half-Lives Greater Than 8 Days Technical Specification 3.17.C.1 limits the organ dose to a member of the public from Iodine-131, Iodine-133, tritium, and radionuclides in particulate form with half-lives greater than 8 days (hereafter called iodines and particulates) in gaseous effluents released from the site to areas at and beyond the site boundary to those specified in 10 CFR Part 50, Appendix I (7.5 mrem per quarter, and 15 mrem per year). By implementing the requirements of Technical Specification 3.17.C, assurance is provided that the releases of iodines and particulates in gaseous effluents are kept "as low as is reasonably achievable." Exposure pathways that could exist as a result of the release of iodines and particulates to the atmosphere include external irradiation from activity deposited onto the ground surface, inhalation, and. ingestion of vegetables, meat and milk. Dose estimates were made at the site boundary, tidal mud flats, nearest residents (including vegetable gardens), and nearest - milk animal in each of the sixteen principle compass directions. The nearest resident, nearest vegetable garden and nearest milk animal in each sector were identified by the most recent Annual Land Use Census as required by Technical Specification 4.8.B. Doses were also calculated at the point of approximate maximum ground level air concentration of radioactive materials in gaseous effluents. Doses were calculated for pathways which were determined by the field survey to actually exist. Conservatively, a vegetable garden was assumed to exist at each milk animal location. Furthermore, the meat pathway was also assumed to exist at each milk animal location. Heat and milk animals were assumed to receive their entire daily feed intake from pasture during the second and third quarters. During the first and fourth quarters (nongrowing season), meat and milk animals receive all their daily feed from stored feed supplies. The resultant organ doses were determined after adding the contributions from all pathways at each location. Doses were calculated for the whole body (both from internal and external sources), GI-tract, bone, 5143R
- .- -+.
liver, kidney,. thyroid, lung and skin for adults, teenagers, children and infants. The maximum estimated quarterly and annu'al' organ. doses due to - iodines and particulates at any of the off-site ~ receptor locations are reported in Table-5. - The doses to other organs at all other locations' for other age. groups are less than the doses reported in Table 5. The estimated organ doses from iodines and particulates in gaseous effluents are below the 10CFR Part 50, Appendix I dose criteria of Technical Specification 3.17.C.I. 5143R
REFERENCES 11 . Regulatory Guide 1.109, " Calculation of Annual Doses to Man from Routine-Release of ~ Reactor Effluents for the Purpose of- Evaluating Compliance With 10 CFR Part 50, Appendix I," U.S. Nuclear Regulatory Commission, Office of Standards Development, . Revision 1, October _1977. 2.; Regulatory Guide 1.23, "On-Site Meteorological Programs (Safety Guide 23)," U.S. ' Nuclear Regulatory Commission, Office of Standards Development, February.1972.
- 3. Regulatory Guide 1.111, " Methods for' Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from. Light-ilater-Cooled Reactors," U.S. Nuclear Regulatory Commission, Office of_ Standards Development,_' Revision 1, October 1977.
~8-5143R
> o TABLE 1A Maine Yankee Atomic Power Station Effluent and Haste Disp.oSal Semiannual Reoort Third and Fourth Ouarters. 1986 Gaseous Effluents - Summation of All Releases Unit Quarter Quarter Est. Total
-3rd 4th Error, %
A. Fission and Activation Gases
- 1. Total release Ci 1.33 E+00 4.23 E+02 2.50 E+01
- 2. Averaae release rate for period UCl/sec 1.68 E-01 5.38 E+01_
- 3. Percent of reculatory limit % 1.16 E-04 3.69 E-02 B. Iod.ines
- 1. Total Iodine-131 Ci 3.77 E-04 3.61 E-04 2.50 E+01
- 2. Averaae release rate for period UCi/sec 4.79 E-05 4.59 E-05_
- 3. Percent of reaulatory limit % 9.55 E-05 9.15 E-05.
C. Particulates 1.ParticulateswithT-1/2l8 days Ci 5.03 E-05 4.85 E-05* 2.50 E+01
- 2. Averaae release rate for period UCi/sec 6.40 E-06 6.17 E-06*
- 3. Percent of reaulatory limit % 8sH7 E-06__2194 E-06*
- 4. Gross aloha radioactivity Ci 2.15 E-07 9.86 E-OR_
D. Tritium
- 1. Total release C1 2.06 E+00 5.78 E-01 2.50 E+01 I'
- 2. Average release rate for oeriod UCi/sec 2.62_E-01 7.35 E-02
- 3. Percent of regulatory limit % 2.61 E-04 7.52 E-05
- Strontium analysis for the fourth quarter not yet available. They will be j included in a supplemental report.
8510L-DS
.o Q\ l O '_ TABLE IB. Maine Yankee Atomic Power Station
. Effluent and Haste Dispas,a1 Semiannual __R_epart Third and Fourth Ouarters. 1986 Gaseous Effluents - Elevated Release Continuous Mode Batch Mode Nuclides Released -Unit Quarter Quarter. Quarter Quarter.
3rd 4th 3rd 4th
- 1. Fission Gases Krvoton-85 Ci N/D* N/D* 8.93 E-01 1.99 E+00 Krvoton-85m Ci N/D* N/D* N/D* N/D*
Krvoton-87 Ci N/D* N/D* N/D* N/D* Krvoton-88 Ci N/D* N/D* N/D* N/D* Xenon-133 Ci N/D* 4.21 E+02 4.22 E-01 4.39 E-01 Xenon-135 Ci N/D* N/D* 3.12 E-03 3.42 E-03 Xenon-135m Ci N/D* N/D* N/D* N/D* Xenon-138 Ci N/D* N/D* N/D* N/D* Xenon-133m Ci- N/D* N/D* 2.30 E-03 2.61 E-03 Argon-41 Ci N/D* N/D* N/D* N/D* Xenon-131m- Ci N/D* N/D* 1.38 E-Q2 N/D* Unidentifled Ci N/D* N/D* r'/D
- N/D*'
Total for oeriod Ci N/D* 4.21 E+02 1.33 E+00 2.44 E+00
- 2. Iodines Iodine-131 Ci 3.77 E-04 3.61 E-04 N/0* N/D*
Iodine-133 C1 1.62 E-04 1.24 E-04 N/D* N/D*
-Iodine-135 Ci N/D* N/D' N/D* N/D*
Total -for oeriod Ci 4.64 E-04 4.85 E-04 N/D* N/D*
- 3. Particulates Strontium-89 Ci N/D* **
N/D* N/D* Stiontium-90 C1 N/D* ** N/D* N/D* Cesium-134 Ci N/D* N/D* N/D* N/D* Cesium-137 Ci 7.51 E-07 N/D* N/D* N/D* Barium-Lanthanum-140 Ci N/D* N/D* N/D* N/D* Zinc-65 Ci N/D* N/D* N/D* NLD* i t-58 Cab _it Ci N/D' N/D' __l{!D
- N/D*
Cobalt-60 Ci 3.15 E-06 N/D* NLD* N/D* Others Ci N/D* N/D* N/D* N/D*
*N/D - Not Detected
- Strontium analyses not yet available from outside vendor. Hill be provided in supplemental report.
8510L-DS
-- - - =-- - - - - - - - - - - - - - - - - - - - - - - - - - -
>.z ..-
TABLE 1C
- Maine Yankee Atoric Power Station -
Effluent and Haste-Disoosal Semiannual Report-
-Third and Fourth Ouarters 1986' Gaseous Effluents - Ground level Releases
- There.were'no~ routine measured ground level continuous:or batch mode gaseous -
- releases ,during the third'or fourth quarters of 1986'.
1 6 8510L-DS
av ; s
~;
31 ^ >
^ '
iTABLE 2A Maine Yankee Atomic Power Station Effluent _and Haste Dispoial Semiannual ReDort Third and Fourth Ouarters. 1986 Liquid Effluents - Summation of All Releases
~
Unit -Quarter Quarter Est.' Total 3rd 4th Error. %'
;A.. Fission and Activation Products 7
1.' Total release (not including tritium. gases. aloha) Ci _ 3,52_ E-02__1,7.1_ E-0L*__i l . 50 E+01
- 2. Average diluted concentration durina ceriod uCi/ml 1.85 E-10 8.22 E-10*
- 3. Percent of aoolicable limit- % 2.92 E-02 2.39 E-Ol*
- 8. Tritium
- 1. Total release Ci 7.03 E+01 1.01 E+02 1.50 E+01
- 2. Average diluted concentration during Deriod uCi/mi 3.70 E-07 4.86 E 3. Percent of aDollCable limit % 1.23 E-02 1.62 E-05 C. Dissolved and Entrained Gases
- 1. Total release C1 1.30 E-01 9.81 E-01 1.50 E+01
- 2. Average diluted concentration durina ceriod UCi/ml 6.84 E-10 4.72 E-09'
- 3. Percent of aoolicable limit % 3.42 E-04 2.36 E-03 D. Gross Alpha Radioactivity-
- 1. Total release Ci 4.63 E-06 1.14 E-07 1.50 E+01
- 2. Average diluted concentration during oeriod uCi/mi 2.44 E-14 5.48 E-16 E. Volume of waste released (prior to dilution)- liters 1.95 E+07 1.08 E+07 1.00 E+01 F. Volume of dilution water used durina ceriod liters 1.90.E+11 2.08 E+11 1.00 E+01
- Strontium and Iron-55 analyses not yet available. They will be included in a supplemental report.
8510L-DS -
(
;w.
r
' TABLE 2B
- Maine Yankee Atomic Power Station Effluent'and Haste Disposal Semiannual Report Third and Fourth Ouarters. 1986 Liould Effluents Continuous Mode Batch Mode Nuclides Released Unit Quarter Quarter' Quarter Quarter 3rd ~ 4th 3rd 4th Strontium-89 Ci N/D* **
7.31 E-05 **
-Strontium-90 Ci N/D* **
N/D* ** Cesium-134 Ci N/D* N/D* 1.70 E-05 2.13 E-01 __ Cesium-137 Ci N/D* N/D* 1.52 E-04 8.45 E-04 Iodine-131 Ci N/D* N/D* 1.64 E-02 1.43 E-01 Cobalt-58 Ci N/D* N/D* N/D* 7.27 E-06 _ Cobalt-60 C1 N/D* N/D* 1.18 E-Q2 7.24 E-04 _J ron-59 C1 N/D* N/D* N/D* N/D* Zinc-65 Ci N/D* N/D* N/D* N/D* Manaanese-54 Ci N/D* N/D* N/D* N/D* Chromium-51 Ci N/D* N/D* N/D* 4.11 E-05 Zirconium-Niobium-95 C1 N/D* N/D* N/D* N/D* _Nolybdenum-99 Ci N/D* N/D* 2.38 E-05 1.04 E-QL Technetium-99m Ci flip
- l!LD* 3.0LE-05 8.61Ec0L i.
Barium-Lanthanum-140 Ci il/D* fl/D' NLD* N/D* Cerium-141 Ci N/D* tl/D
- N/D* N/D*
Others Niobium-97 Ci N/D* fl/ D* 1.52 E-03 1.36J-QL . Iodine-133 C1 N/D* N/D* 1.65 E-04 1.94 E-OL . Silver-110m Ci N/D* N/D* 9.90 E-04 5. 26_E-OL Antimony-124 Ci N/D* N/D* N/D' 1.16 E-04 Iron-55 Ci N/D* ** 4.01 E-03 **
-Cesium-136 Ci N/D* N/D* 2.92_E-05 N/D*
Antimonv-125 Cl N/D* nip
- fl/D* 2.62_E-03 Unidentifled C1 3.91 E-04 2J 6 E-04 ft/D* fl/D*
Total for o_eriod (above)(1)C) 0.00 E+01 0.00 E-01 3.52 E-02 1.71 E-01 _ Xenon-133 C1 1.98 E-04 NLD
- 1.29_E-Q1 _
7.12J-QL Xenon-135 Cl N/D* NLD* 2.44 E_-J4 2A S E-0_1_. _ Xenon-133M C1 N/D* lilD* 2.16 E-04 - 6.98 E-03_ _ Xenon-131H Ci N/D* HlD* 6.10J-04 Lh2J-QL _ Xenon-135M Ci fl/D* N/D' lilD* 1.2LE_DL
.Kryoton-85M Ci fl/D* N/D* il/D' 8.57 E-OL N/D* - Not Detected
-(1) - Total for period does not include unidentified in 'snis summation but is included in Table 2A, Item AI.
- Strontium and Iron-55 analyses not yet available from outside vendor. 11111 be submitted in suppicment report.
8510L-DS
t TABLE 3 Maine Yankee Atomic Power' Station Effluent and Haste Discosal Semiannual Report. Third and Fourth Ouarters. 1986 Solid Haste and Irradiated Fuel Shipm_enti A. Solid Haste Shipped Off-Site for Burial or Disposal (Not Irradiated Fuel)* Unit 6-Month Est. Total Period Error. %
- 1. Type of Haste
- a. Spent resins, filter sludges, evaporator m3 24.07 f jo bottoms, etc. - LSA container **, m , cj 58.63
- b. Dry compressible waste, contaminated m3 68.75 +1
'0 equipment, etc. - LSA container +, ++ cj 30.17
- c. Irradiated components, control rods, m3 0
, etc. cj 0
- d. m3 Cj
- e. m3 Cj
- 2. Estimate of Major Nuclide Composition (By Type of Haste)***
- a. Co-60 227. 107.
Cs-137 337. 107. Fe-55 107. i 107. Ni-63 347. 107.
- b. Co-60 127. 107.
Cs-137 47. 107. N1-63 20% 10% Fe-55 647. 107.
- 3. Solid Haste Disposition Number of Shioments Mode of Tramportation Destination 7 Trucking over liighway Chem-Nuclear, Barnwell, S.C.
B. Irradiated fuel Shipments (Disposition) None
+ Container volume equal to 55 gal ons (drums).
- Container volume equal to 110 ft (boxes).
m Container volume equal to 170 ft (liners) (llIC).
- Solid waste as Class A, defined in 10CFR61.55 81.56 m3, 3.10 C1.
- Solid waste as Class B, defined in 10CFR61.55 5.89 m3, 58.33 C1.
- Solid waste as Class C, defined in 10CFR61.55 5.38 m3, 26.86 C1.
** Solidification agent is cement.
*** Excluding nuclides with half-lives less than 12.8 days.
1
---- -__----- ---------- j
, e
. TABLE 4 Supplemental Infor_ma_ tion o
Third and Fourth Ouarters. 1986
- 1. Technical Soecification limits - Dose and Dose Rate lechnical Soecification and Category Limit
- a. Noble Gases 3.17.A.1 Total body dose rate 500 mrem /yr 3.17.A.1 Skin dose rate 3000 mrem /yr 3.17.B.2 Gamma air dose 5 mrad in a quarter 3.17.B.2 Gamma air dose 10 mrad in a year 3.17.B.2 Beta air dose 10 mrad in a quarter 3.17.B.2 Beta air dose 20 mrad in a year
- b. Iodine-131. Iodine-133. Tritium. and Radionuclides in Particulate Form Hith Half-Lives Greater than 8 days I
l 3.17.A.1 Organ dose rate 1500 mrem /yr i 3.17.C.1 Organ dose 7.5 mrem in a quarter I 3.17.C.1 Organ dose 15 mrem in a year 3.17.C.1 Organ dose (contaminated oil burning) <0.0075 mrom in a quarter 3.17.C.1 Organ dose (contaminated oil burning) <0.015 mrem in a year
- c. Liaulds 3.16.8.1 Total body dose 1.5 mrem in a quarter 3.16.B.2 Total body dose 3 mrem in a year 3.16.B.1 Organ dose 5 mrem in a quarter 3.16.B.2 Organ dose 10 mrem in a year
- 2. Reaulatory Limits Maximum Permissible Contentratien
- a. Fission and activation gases: 10CFR20; Appendix B, Table 2, Column 1
- b. Iodines: 10CFR20; Appendix B, Table 2, Column 1 c Particulates, (with half lives greater than 8 days) 10CFR20; Appendix B, Table 2, Column 1
- d. Liquid effluents: 10CFR20; Appendix B, Table 2, Column 2
- e. Total noble gas concentration 2E-04 uC1/cc
- 3. Average Enerav - fiqt_ApplLtilbic 5143R
F TABLE _4 (Continued)
- 4. Measurements and Acoroximations of Radioactivity
- a. Fission and Activation Gases Continuous Discharge - Vent stack samples are analyzed monthly.
Activity levels determined are assumed constant for the surveillance interval. The continuous vent stack monitor reading is used as a~ basis for increasing periodic sample frequency. Batch Discharges - Direct measurements of the waste gas hold-up drums are taken prior to discharge. Containment vents and purges are analyzed by direct measurement of the containment atmosphere at periodic intervals during discharge.
- b. Iodines Primary vent stack iodine totals are taken from a minimum of weekly measurements of an in-line charcoal filter.
- c. Particulates Primary vent stack particulate totals are taken from a minimum of weekly measurements of an in-line particulate filter,
- d. Liquid Effluents Samples of secondary systems' liquid effluents are analyzed weekly for gross beta-gamma, alpha, tritium, dissolved gases, and gamma emitting isotopes.
Each batch release is analyzed for gross beta-gamma, alpha, tritium, dissolved gases, and gamma emitting isotopes prior to discharge. Composite samples are made of secondary and primary systems 11guld effluents for a quarterly analysis of Strontium-90 and Strontium-89. Primary system liquid effluents are also analyzed quarterly for Iron-55.
- 5. Batch Releases
- a. Liquidi
- 1. Number of batch releases: 73
- 2. Total time period for batch releases: 183 hours, 2 minutes
- 3. Maximum time period for a batch release: 8 hours, 25 minutes
- 4. Average time period for batch releases: 2 hours, 30 minutes
- 5. Minimum time period for a batch release: 54 minutes 5143R
TABLE 4 (Continued)
- 6. Average stream flow during periods of release of effluents into a flowing stream: N/A
- 7. -Maximum gross release concentration (uC)/ml): 3.29E-07
- b. Gaseous
- 1. Number of batch releases: 9
- 2. Total time period for batch releases: 7 hours, 17 minutes
- 3. Maximum time period for a batch release: 2 hours, 53 minutes
- 4. Average time period for batch releases: 49 minutes
- 5. Minimum time period for a batch release: 15 minutes
- 6. Maximum gross release rate (uCi/sec): 2.93E+04 6.. Abnormal Releases
- a. Liauid There were no abnormal liquid releases during the reporting period.
- b. Gaseoui (See Appendix D)
- 7. On-Line Containment Purges There were no on-line containment purges during the reporting period.
The total on-line purge time for the calendar year 1986 was 85 hours, 52 minutes. 1 l l l 5143R l l-
TABLE 5 Maine Yankee Atomic Power Station Effluent and Haste Disposal Semiannual Report Third and Fourth Ouarters. 1986 Maximum Off-Site Doses and Dose Commitments to Members of the Public Dose (mrem) ist 2nd 3rd 4th Source Quarter Quarter Ouarter Quarter Year
- Total Body: 5.2 E-5 4.7 E-5 2.4 E-4 8.1 E-5 4.2 E-4 (1)
Liquid Effluents Maximum Organ: 2.6 E-3 4.8 E-3 1.9 E-3 1.4 E-2 2.3 E-2 (2) Airborne Effluents Iodines and Particulates 8.7 E-3 2.8 E-2 1.2 E-2 4.6 E-3 5.3 E-2 (3) (4) (5) (6) Noble Gases Beta Air 3.4 E-2 9.2 E-4 1.6 E-4 1.7 E-2 5.2 E-2 , (mrad) (7) (8) (9) (10) Gamma Air 1.3 E-2 3.8 E-5 3.0 E-5 7.1 E-3 2.0 E-2 (mrad) (11) (12) (13) (14) (1) Maximum total body dose for all periods was to an adult. (2) Maximum organ dose for all periods was to an adult's thyroid. (3) Maximum organ dose to child's thyroid at 700 m SE. (4) Maximum organ dose to infant's thyroid at 2700 m N. (5) Maximum organ dose to infant's thyroid at 2700 m N. (6) Maximum organ dose to child's thyroid at 700 m SE. (7) Maximum dose at 670 m SE. (8) Maximum dose at 1219 m N. (9) Maximum dose at 1368 m NNE. (10) Maximum dose at 670 m SE. (11) Maximum dose at 700 m SE. (12) Maximum dose at 762 m NH. (13) Maximum dose at 1000 m SE. (14) Maximum dose at 700 m SE. 8510L-DS
. v .-
$ 1 4
~
1 e TABLE 6A-MAINE YANKEE fJAN86-DEC86. JOINT FREQUENCY DISTR 18UTION (UPPER LEVEL)
'197.0 FT WIND DATA STA8! LIT) CLASS A CLASS FREQUENCY (PERCENT) = 3.34 WIND DIRECTION FROM SPEED (MPH) . N NNE NE .NE E ESE SE SSE S SSW SW WSW W WNW N'J NNW VE B'. TOTAL CALM 0 0 0 0 0 ,0 0 0 0 0 0 0 0 0 0 0 0 0 (I) .00 .00 .00 '00
. 00 _ .00 00 .00 ' .00 00 00 00 .00 .00 00 00 00 .00 (2) 00 00 00 00 ' C0
. 00 .00 00 .00 00 00 00 00 00 00 '. 00 .00 00 C-3 0 0 0 1 5 1 1 1 1 1 0 0 1 0 0 0 0 12 (1) 00 00 .00 36 f.78 36 36 36 26 36 00 00 36 00 .00 00 .00 4.27 (2) 00 00 00 .01 06 01 01 01 01 01 00 00 01 00 00 00 00 .14 4-7 2 3 11 3 1 0 1 4 11 6 5 2 3 l' 0 3 0 56 L (1) .71 1.07 '3 11 1.07 36 .00 36 1.42 3 91 2.14 ~ 1.78 .71 1.07 36 00 1.07 .00 19.93 (2) .02 .04 13 .04 01 00 .01 .05 13 .07 .06 02 .04 01 .00 04 00 67 !
8-12 3 5 13 3 0 1 0 2 10 22 6 5 12 3 4 7 0 96 (1) 1.07 1 78 4.63 1 07 00 .36 00 .71 3.56 7.83 2.14 1.78 4.27 1.07 l.42 2.49 00 34.16 (2) .04 06 .15 04 00 .01 .' .02 .12 .26 07 06 .14 .04 05 03 00 1.14 13-18 9 4 5 0 0 0 0 0 3 15 0 0 3 13 16 11 0 79
' (1) 3.20 1,42 1.78 .00 00 00 00 .00 1.07 5 34 00 00 1.07 4.63 5.69'3.9I 00 20.I,1 (2) .11 .05 06 00 00 00' 00 00 04 .18 00 00 04 15 19 13 00 94 l 19 24 0 0 1 0 1 0 0 0 3 9 1 0 0 4 10 2 0 ~31 (1) .00 00 .36 .00 36 00 00 00 1.07 3.20 36 00 .00 1.42 3.56 71 00 11.03 (2) .00 .00 01 00 01 00 00 00 .04 11 01 00 00 .05 .12 .02 00 37 GT 24 0 0 0 0 0 0 0 0 0 0 0 0 0 2 4 1 0 7 (1) 00 00 00 00 00 00 .00 00 00 00 00 00 00 71 1.42 36 00 2.49 (2) .00 .00 .00 00 .00 00 00 00 00 .00 00 , 00 00 02 05 01 00 08 ALL $PEEDS 14 12 30 7 7 2 2 7 28 53 12 7 19 23 34 24 0 231 (1) 4.98 4.27 10-68 2.49 2.49 71 71 2.49 9 96 18.86 4 27 2.49 6 76 8 19 12.10 8.54 00 100 00
- (2) .17 .14 36 .00 .08 .02 .02 08 33 .63 14 08 23 27 .40 29 .00 3 34 l
l (1) PERCENT OF ALL C000 OSSElvAi!0N3 FOR TH!$ PAGE L (2) 7EICENT OF ALL G0CD 08SElvAi!0NS FOR TH!$ PER!00 to CALM (WIND SPEED LESS THM 08 EDUAL 10 .(0 Mfm l l . l 1 i l l l 5143R l l ( i
L C.. f .; 4 . O TABLE 6B HAINE YANKEE JAN86-DEC86 JOINT FREQUENCY DISTRIBUTION . (L'PPEP LEVEL) 197.0 FT WINO DATA STABILITY CLAS3 8 CLASS FREQUINCY (PERCENT) = 1,76 WIND DIRECTION FROM SPEED (MPH) N NNE NE ENE E ESE SE SSE S SSW SW WSW W ENW NW NNU VR9L TOTAL CALM 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0
- (1) 00 00 .00 00 .00 00 00 00 .00 .00 00 .00 00 .00 .00 00 00 00 (2) 00 00 00 00 00 .00 00 .00 00 .00 00 00 00 00 00 00 00 00 C-3 0 'l 0 0 0 0 0 2 1 0 0 0 0 0 0 0 0 4 (1) .00 68 00 .00 .00 00 00 1.35 .68 00 .00 .00 00 00 - 00 00 00 2.70 (2) .00 ~ 01 00 .00 .00 00 00 02 01 00 00 00 .00 00 00 00 .00 .05 4-7 1 1 2 4 0 0 1 2 5 4 2 I I 0 0 3 0 27 (1) .68 68 1.35 2.70 00 00 69 1.35 3.30 2.70 1.35 69 69 00 .C0 2 C') .C0 18.24 (2) .01 01 02 05 00 .00 01 02 06 05 02 01 01 00 00 (4 00 .32 0-12 2 8 5 3 2 0 0 5 7 6 5 2 2 6 3 3 0 59 (1) 1.35 5.41 3.38 2.03 1 35 00 .00 3.38 4.73 4.05 3.39 f.35 1.35 4.05 2.03 2 03 00 31.E6
. (2) 02 10 .06 04 02 00 .00 06 08 07 06 02 02 .07 06 .04 00 70-13-18 1 0 4 0 1 0 0 0 2 7 1 3 3 2 9 1 0 34 (I) .68 00 2.70 00 68 00 .00 00 1.35 4.73 60 2.03 2.03 f.35 6 03 69 00 22.97 (2) 01. 00 05 .00 01 .00 00 00 .02 09 01 .04 04 .02 11 01 00 .40 19-24 0 1 1 0 0 0 0 0 2 2 0 0 1 2 6 3 0 19 (1) .00 .68 . 68 .00 .00 00 00 00 1.35 1.35 00 .00 68 1.35 4.05 2.03 00 12.16 (2) .00 01 01 .00 00 00 00 00 02 02 00 00 01 02 07 04 00 21 G1 24' 0 0 0 0 0 0 0 0 0 1 0 0 0 2 2 1 0 6 (I) 00 00 00 .00 00 00 00 00 00 68 00 00 00 1 35 1 35 60 00 4.05 (2) 00 00 .00 00 00 00 00 00 00 .08 00 00 00 02 02 01 00 .07 Alt. SPEED $ 4 11 12 7 3 0 1 9 17 20 0 6 7 12 20 11 0 149 (1) 2 70 7.43 8 11 4.73 2.03 .00 .68 6.00 11.49 13.51 5 41 4 05 4.73 8 11 13.51 7 43 .00 100.00
-(2) 05 .13 .14 .09 04 00 01 11 20 24 10 07 08 14 .24 13 00 1-76 (ll*PlACENT OF ALL 0000 C8SERVAi!ONS FOR TNIS PAGE (21sPERCENT OF ALL 0003 08SERVAi!0N$ F0f THIS pet!00 Ce CALM IUlN3 STEED LESS THAN Of EDUAL 10 60 MPH)
$143R
3
- TABLE 6C MAINE YANKEE JAN86-DEC66 J0!NT FREOUENCY DISTRIBUTION (UPPER LEVEL) 197.0 FT WIND DATA - STABILITY CLASS C CLAS3 FREUUENCY (PERCENT) = 4.76 WIND DIRECTION FROM SPEED (MPH) N ENE NE ENE E ESE SE SSE S SSW SW W:V W WNU NW NNW VF2L TOTAL CALM 0 0- 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 C (1) .00 00 .C0 00 .00 00 00 00 00 00 00 00 00 00 00 00 .00 .C0 (2) .00 00 00 00 00 00 00 .00 00 00 00 .C0 00 .00 00 00 00 00 C-3 0 0 1 1 3 1 1 1 3 1 1 1 0 2 0 0 0 16 (1) 00 00 25 25 .75 25 25 25 75 25 25 25 00 50 .00 .C0 00 4.00 (2) 00 00 01 01 04 .01 01 01 04 01 01 01 00 02 00 00 00 .19 4-7 4 4 6 5 2 I I 3 13 5 3 3 5 2 3 3 0 63 (1) 1.00 1.00 1.50 1.25 50 .25 25 75 3.25 1.25 75 75 l 25 50 75 75 00 15.75 (2) 05 .05 .07 .06 02 01 .01 04 15 .C6 04 04 .06 .02 04 04 00 75 8-12 12 13 11 9 2 0 I 8 22 19 6 5 8 13 15 9 0 153 (1) 3.00 3.25 2.75 2.25 50 00 25 2.00 5.50 4.75 1.50 1.25 2.00 3.25 3.75 2.25 00 33.25 (2) .14 .15 13 .Il 02 00 01 .10 26 23 07 06 10 .15 .18 11 .00 1.G2 13-1B 11 8 3 0 0 0 0 2 4 13 1 5 9 14 32 6 0 103 (1) 2.75 2.00 75 00 .C0 00 00 50 1.C0 2 25 .25 1 25 2.25 3.50 0.C0 1 50 C0 27.00 (2) 13 10 .04 00 00 00 00 .02 05 .15 01 .C6 11 17 30 07 .C0 1.23 19-24 2 0 0 0 0 0 0 0 1 4 2 0 1 10 11 0 0 47 (1) 50 .C0 .00 .C0 00 00 00 00 25 1.C0 50 00 25 2.50 4.75 2.00 .C0 11.75 (2) 02 00 00 00 .00 00 00 00 01' 05 02 00 .01 .12 23 10 00 56 GT 24 2 0 0 0 0 0 0 0 1 1 0 0 0 4 4 1 0 13 (1) 50 00 C0 00 00 00 00 00 25 25 00 .00 00 ,1 C0 1.00 25 00 3.25 (2) 02 .C0 C0 00 00 00 00 .C0 01 01 00 00 00 05 .C5 01 .C0 15 ALL SPEEDS 31 25 21 15 7 2 3 14 44 43 13 le 23 45 73 27 0 400 ft) 7.75 6 25 5.25 3 75 1.75 50 75 3.50 11.00 10.75 3.25 3 50 5.75 11.25 10.25 6.75 00 100.00 (2) 37 30 25 .18 00 02 04 17 !2 51 15 17 27 54 87 32 00 4 76 (1): PERCENT OF ALL GOOD OBSERVATIONS FOR THIS PAGE (21sP!! CENT OF ALL C000 CRSERVAi!CNS FOR THIS PERIOD C= CALM (WIN 0 SPEED LEES THAN CR ECUAL TO 60 NrH)
$143R
- 7
?,- ve .
.e.
e 1N4BLE 6D-NAINE YANKEE JAN86-DEC86 JOINT FREQUENCY DISTRIBUi!CN (UPPER LEVEL). 197.0 FT W140 DATA ' STA81LITY CLASS D CLASS FRE8UENCY (PERCENT) = 48.10 WIND DIdECTION FROM SPEED (MPH) N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW VR9L -TOTAL CALM 0 0 0 0'- 0 'O 0 0 1 0 0 0 0 0 0 0 0 1
.(1) .00 .00 ' 00 .00 00 .00 00 - 00 02 00 .00 00 00 00 .00 00 .00 02
-(2) 00 .00 00 00 00 00 00 00 - 01 00 00 00 00 00 00 00 00 01 C3 14 14 13 8 12 8. Il 13 11 13 20 17 18 7 19 11 0 209 (1) 35 .35 .32 20 32 20 27 .32 27 32 .49 42 44 .I7 .47 27 00 5.17 (2) .17 17 .15 .10 .I4 .10 .13 15 .!3 .15 24 .20 .21 .03 23 .13 .00 2.48 4 44 50 69 74 57 63 72 65 84 81 65 51 48 44 37 48 0 ~952 til 1.09 1.24 f.71 1.83 1.41 1.56 1.78 1.61 2.08 2.00 1.61 1.26 1.19 1.09 91 1 19 .00 23.53 (2) .52 .59 82 .88 .68 . 75 ' 86 .77 1.00 96 71 61 57 .52 .44 .57- 00 11.32 0-12 99 120 130 66 52 41 68 102 200 172 101 42 51 53 72 73 0 1442 (1) 2.45 2.97 3.21 1.63 1.29 1.01 1.68 2.52 4.94 4.25 2.50 1.04 1.26 f.31 1.78 1.80 .00 35 64 (2) 1.18 1.43 1.55 .78 .62 49 01 1.21-2.30 2.04 1.20 50 .61 .63 86 .87 00 17.14 13 18- .79 100 $3 '17 15 12 21 71 135 86 75 33 35 72 165 49 0 1010 (1) 1.95 2.47 1.31 .42 .37 ' 30 .52 1.75 3.34 2.13 1.05 82 87 1.78 4 08 1 21 00 25.16 (2) ~. 9 4 1.19 .63 20 .18 14 25 .84 1.61 1.02 89 39 42 86 f.96 58 00 12 10 19-24 26 19 8 2 7 3 3 16 35 30 8 8 8 43 90 34 0 340 (1) .64 .47 20 05 17 .07 07 .40 .87 74 20 20 20 1.06 2.22 84 .00 8.40 (2) 31 23 10 .02 .00 04 04 .19 .42 36 .to 10 .10 51 1 07 .40 00 4.04 GT 24 6 2 2 0 0 0 3 I B 11 0 1 0 11 31 8 0 04 (1). .15 .05 .05 .00 00 00 07 02 .20 27 00 02 00 27 77 20 00 2 08 (2) 07 02 02 00 00 00 04 .01 .10 13 00 01 00 13 37 .10 00 1.C0 ALL SPEEDS 268 - 305 275 167 143 127 178 268 474 393 261 152 160 230 414 223 0 4046 (1) 6.62 7 54 6.80 4.13 3.53 3 14 4.40 6.62 11.72 9.71 6 65 3.76 3.95 5 68 10.23 5.51 03 100 00 (2) 3.19 3.63 3.27 1 99 1.70 1.51 2.12 3.19 5.64 4.67 3.20 1.01 f.90 2.73 4.92 2.65 00 48.10 (1)* PERCENT OF ALL GOOD OBSERVATIONS FOR THIS FACE 12)*7tRCENT OF ALL 0000 CISERVAf!CNS FOR THIS FERIOD Ce CALM (WIND SPEED LESS THtN 02 EQUAL 10 60 MPH) 5143R
3 TABLE 6E MAINE YANKEE JAN86-DEC06 J0!NT FRECUENCY DISTRIEUTION (UPPER LEVEL)
'197.0 FT WIND DATA STABILITY CLASS E CLASS FREQUENCY (FERCENT) = 25.44 WIND DIRECTION FRCM l
SPEED (MfH) N NNE NE ENE E ESE SE SSE S SSW SW USW W WNW NW IlNW VfBL TOTAL CALM 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 (1) .C0 .C0 .C0 00 00 00 .C0 00 .C0 00 00 .C0 00 .00 00 .C0 00 .C0 (2) 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 C-3 7 11 4 8 8 9 13 23 14 23 14 12 16 5 11 7 0 185 (1) 33 .51 19 37 37 .42 61 1.07 65 1.07 65 56 75 .23 51 33 .C0 8.64 (2) 00 .13 05 10 .10 .11 15 27 .l7 27 17 14 19 .C6 13 .CS 00 2.20
.4-7 31 22 34 26 14 16 :S 29 07 96 71 36 44 37 37 31 0 643 (1) 1.45 1.03 1.59 1.21 .65 75 1.17 1.31 4.07 4.49 3.32 1.69 2 C6 1.73 1.73 1.E2 00 30 05 (2) 37 .26 .40 .31 .17 19 30 33 1.03 1.14 84 43 52 .44 .44 .46 00 7.64 8-12 57 49 22 13 7 14 9 24 123 94 56 35 54 69 91 93 0 203 (1) 2.66 2 29 1.03 61 33 65 42 1.12 5.75 4.31 2.62 1 64 2.52 3 22 4.63 3.09 .C0 37.76 (2) 69 59 .26 .15 .CB 17 11 .29 1.46 1.12 .67 .42 64 62 1.19 91 00 9.61 13 10 30 10 11 0 1 1 6 10 42 62 19 12 10 34 C3 37 0 321 (1) 1.40 84 51 00 05 05 29 47 f.96 2.90 09 56 04 1.51 4.11 1.73 00 10 18 (2) 36 21 13 .00 01 01 07 12 50 74 23 14 21 .40 1.C5 .44 .C0 4.62 19-24 4 0 0 0 0 0 3 4 7 17 1 1 2 12 10 5 0 66 (1) .19 .00 00 .C0 00 .C0 14 .19 .33 79 05 .C5 01 .56 47 .23 .C0 3.C3 (2) .05 .C0 .00 .C0 00 00 04 .C5 00 20 01 01 02 .14 12 .C6 .00 .73 GT 24 0 0 0 0 0 2 14 14 8 7 1 0 0 2 1 0 0 49 (1) .C0 00 00 00 00 09 65 .65 37 33 05 00 .C0 .C1 05 .C3 .C0 2.21 (2) 00 00 .00 00 00 02 .17 17 .10 00 08 00 .C0 02 01 .C0 .C0 53 ALL CPEEDS 129 100 71 47 30 42 70 103 201 211 162 96 134 151 246 171 0 2140 (1) 6 03 4.67 3.32 2.20 1.40 1 96 3.27 4.01 13.13 13 17 7.57 4.49 6.26 7.43 11.50 7.11 .C0 100.00 (2) 1.53 1.19 .e4 56 36 50 83 1.22 3.34 3 55 1.93 1.14 1.51 1.89 2.92 2.03 00 25 44 (I)*FERCENT OF ALL C000 08SERVATION3 FOR THIS PAGE (2): PERCENT OF ALL C000 CBSERVAi!DNS FOR THIS EERIOD C= CALM (WIND $ FEED LES3 TPAN CR [CUAL TO 60 NFH) 5143R
F a O o-6 TABLE 6F flAINE YANKEE JAN86-DEC86 JOINT FREQ'JENCY DISTRIBUi!0N (UFFER LEVEL) 197.0 FT WIND DATA STABILITY CLASS F CLASS FRECUENCY (FEICEHT) = 0.71 WIND DIRECTI0tt FROM SPEED (MPH, N NNE NE ENE E ECE SE SSE S SSW SW W3W W WNW NW NNW VABL TOTAL CALM 0 0 1 0 0 0 0 0 0 0 0 0 0 0 0 0 0 1 (1) 00 00 .14 .C0 .C0 00 00 00 .C0 00 00 00 00 .C0 00 00 00 14 (2) 00 00 01 .C0 00 00 00 00 00 00 .C0 .C0 .00 00 00 00 00 01 C-3 6 2 7 2 3 4 1 3 6 13 11 7 0 6 4 0 0 11 (1) 62 27 .95 .27 .41 .55 14 .41 02 1.77 1.50 95 1.09 02 55 1.C9 00 12 41 (2) .07 02 08 .02 04 05 .01 04 07 15 .13 .C; 10 .07 05 10 00 l.C3 4-7 18 19 27 0 7 11 5 6 45 44 41 32 27 24 25 19 0 353 (Il 2.46 2.59 3.68 1.09 .95 1.50 60 62 6.14 6.00 5.59 4.37 3.60 3.27 3.41 2.59 00 43.64 (2) 21 23 .32 10 .00 .13 06 07 54 52 .49 .38 32 .29 30 23 00 4 26 8-12 26 9 4 1 1 0 1 2 29 27 7 18 26 22 30 25 0 229 (1) 3.55 1.23 .55 14 .14 .C0 14 .27 3.96 3.63 95 2.46 3.55 3.00 4.01 3.41 00 31 11 (2) 31 11 05 01 01 .C0 .01 02 34 32 09 21 31 26 36 30 00 2.71 13-19 4 1 0 0 0 0 0 3 3 0 1 2 5 13 12 9 0 53 (1) .55 14 .00 ,00 00 00 00 .41 41 00 14 27 60 1.77 1.64 1.23 .C0 7.23 (2) .C5 .01 00 00 00 00 .00 04 .c4 00 01 02 06 .15 14 Il .C0 63 19-24 0 0 0 0 0 0 0 0 0 0 0 2 0 0 0 0 0 2 (I) .C0 00 .00 00 .C0 00 00 .00 .C0 00 .C0 27 .C0 00 00 .00 .00 27 (2) .C0 .C0 00 00 00 00 00 00 .00 00 .00 02 00 00 00 .C0 .C0 02 OT 24 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 C (1) .00 .00 .C0 00 .C0 .C0 00 00 .C0 93 C0 .C0 .C0 00 00 00 00 .C0 (2) 00 00 00 .C0 00 00 00 00 00 .C0 .C0 00 00 .C0 .C0 00 .C0 00 ALL SPEEDS 54 31 31 11 11 15 7 14 03 04 60 61 (6 65 71 61 0 733 (1) 7.37 4.23 5 32 1.50 1.50 2.05 .95 1.91 11.32 11.46 9.11 0 32 9.00 0.07 9 69 B.32 00 1C0.00 (2) 64 37 .46 13 13 18 00 17 91 1 00 71 73 .70 77 84 .73 C0 0 71 (1)=FEICLNT OF ALL 0000 OB3ERVATIONS FOR THIS FACE (2) PERCENT OF ALL GOOD Cl$ERVATICNS FOR THl3 FER103 C= CtLM (WINO CFEID LESS THtN 02 EC'JAL 10 (0 t'?H) 24 5143R
., e
- e o
TABLE 6G MA!NE YANREE JAN86-DEC66 JOINT FREQUENCY DISTRIBUi!D'l (UFFER LEVEL) , 117.0 FT WIND DATA STA!!LITY CLASS G CLASS FREQUENCY (FERCEHT) = 7.68 WIND DIRECTION FROM SFEED(MPH) N NNE NE ENE E ESE SE SSE S SSU SW WSU W WNW NW NHW VREL TOTAL CALM 0 0 0 0 0 0 0 1 0 0 0 0 1 1 1 0 0 4 (1) .00 00 .00 .00 .00 00 00 .15 .00 00 00 00 .15 15 .15 .C0 00 .60 (21 .00 00 .00 00 .00 .00 .C0 .01 00 00 .C0 .00 01 01 01 00 .C0 05 C-3 7 7 0 4 5 6 6 2 4 12 17 6 14 20 16 12 0 146 (1) 1.C6 f.C6 1.21 60 .75 50 10 30 60 1.81 2.56 50 2.11 3.C2 2.41 f.81 .00 22.02 (2) .C8 .C3 .10 .05 .C6 07 .07 .C2 05 .14 .20 07 .17 24 11 14 .00 1.74 4-7 23 27 15 12 5 7 to 12 20 45 31 25 24 to 20 18 0 320 (1) 3 47 4.07 2.26 1.81 .75 1.C6 1.51 1.81 3.02 6.71 5.83 3.77 3.62 2.71 3.02 2.71 00 48.27 l (2) 27 .32 .18 .14 .06 08 .12 .14 24 54 .46 .30 .21 21 .24 .21 00 3.00 8-12 18 .20 14 2 0 l 4 2 6 1 6 11 24 20 17 15 0 161 (1) 2 71 3.02 2 11 30 .C0 .15 .60 30 50 1.36 10 1.66 3.62 3.02 2.56 2.26 .C0 25.41 (2) 21 .24 .17 .02 .C0 01 .05 02 07 11 07 13 21 24 .20 18 .00 2.01 , 13-18 1 3 1 0 0 0 0 0 0 0 0 1 2 6 5 4 0 23 l (1) 15 .45 .15 .00 00 00 .C0 00 00 00 .00 .15 .30 50 75 .to 00 3.47 (2) .01 .04 .01 .C0 .00 .00 .00 .00 .00 00 .C0 01 .02 07 .C6 05 .C0 27 11-24 1 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 I (1) .15 .00 .C0 .00 00 .C0 .c0 00 .C0 .C0 .00 .00 00 .00 .C0 .00 .C0 15 l .e0 .00 .0a .00 .C0 00 00 .00 00 .c3 .cl (2) 01 .c3 .C0 .c3 .C0 .C0 .C0 GT 24 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 C (1) 00 .00 00 .C0 .CC .C0 .C0 .C0 .C0 00 .00 00 .00 .C0 .00 .C0 0) 0 (2) 00 00 .C0 .C0 00 .00 00 00 .C0 .C0 .Ci .00 .00 .C0 .00 .C0 .C0 . C '. ALL SPEECS 50 57 33 18 10 14 20 17 30 66 62 43 65 65 51 41 0 LO (1) 7.54 8.60 5.73 2.71 1.51 2.11 3.02 2.!6 4.52 1.15 1.35 6.41 1.00 1.80 0.10 7.31 .00 100.C0 (1) .51 .68 .45 21 .12 17 24 20 .36 78 .74 .51 .77 .77 .70 .53 .C0 7.23 (llePERCENT OF ALL CCOD CIS!RVAf!CNS FOR THIS PAGE (2)=PE8 CENT OF ALL CCO3 CISERVATIONS FCt THIS FERICS Ce CtLM (WIN 3 ! TEED LESS THM 02 EC'JAL TO .(0 MPH) 5143R
4 e TABLE 11 MAINE YANXEE JAN36-CEC 86 JOINT FREQUENCY DISTRIBUT10N (L'PPER LEVEL) 197.0 FT WIND DATA STABILITY CLASS ALL CLA33 FIECUENCY (PERCENT) s 100.00 WIND DIRECTICH FACM SPEED (MPH) 4 NNE hE ENE E ESE SE SSE S S;W EW WSU U WNW NW NNW VRBL TOTAL CALN 0 0 1 0 0 0 0 1 1 0 0 0 1 1 1 0 6
- 11) .C0 .C0 01 00 00 .00 00 .01 01 .00 00 .00 01 01 01 00 00 07 (2) 00 .C0 01 00 00 00 00 01 01 03 00 00 01 01 01 .C0 00 07 C-3 34 35 33 24 36 21 33 45 40 63 63 43 57 40 50 33 0 663 (1) .40 .42 31 29 .43 34 31 54 .43 75 .75 .51 .68 48 51 .45 .00 7.08 (2) .40 .42 39 29 .43 .34 .31 54 .40 .75 75 51 60 .40 51 .45 .00 7.E9 4-7 123 126 164 132 66 99 415 120 265 tot 226 150 152 126 122 133 0 2419 (1) 1.46 1.50 1.12 1.57 1.02 1.17 1.37 1.43 3.15 3.34 2.69 1.78 1.81 1.50 1.45 1.53 00 28.76 (2) 1.46 1.50 1.95 1.57 1.01 1.17 1.37 1.43 3.15 3.34 2.69 1.70 1.01 1.50 1.45 1.50 00 29.76 8 12 217 224 199 17 64 57 63 145 317 349 187 118 177 106 240 215 0 2955 (1) 2.58 2.66 2.37 1.15 .76 .60 91 1.72 4.72 4 15 2.22 1.40 2.10 2.21 2.85 2 56 .00 35.13 (2) 2.58 2.66 2.37 1.15 .76 .68 91 1.72 4.72 4.15 2.22 1.40 2.10 2.21 2.05 2.!6 .C0 35.13 13 1B 135 134 77 17 17 13 27 C6 199 103 17 56 75 154 327 117 0 1704 (t) 1.61 1.51 .92 20 20 15 32 1.02 2 25 2.10 1.15 67 69 f.f3 3.01 1.31 00 20.26 (2) 1.61 1.59 .92 20 20 15 32 1.02 2.25 2.10 1.15 .67 ,69 1.03 3.61 1.31 00 20.26 19 24 33 20 10 2 8 3 6 20 48 62 12 11 12 71 135 52 0 505 (1) 39 .24 .12 .02 .10 .04 .07 .24 .57 .74 .14 .13 .14 .C4 1.61 .62 .C0 6.C0 (2) 31 24 .12 .02 .10 04 07 24 57 74 14 .t3 14 04 l 61 .62 .C0 6.C0 GT 24 8 2 2 0 0 2 17 15 17 20 1 1 0 21 42 11 0 159 (1) 10 02 .02 00 00 02 20 .10 20 24 01 01 00 25 ?50 .13 0) 1.01 (2) .l0 .02 .02 .00 .C0 02 20 18 20 24 01 01 .C0 25 50 13 .00 1.61 ALL SPEE05 550 541 4t6 272 211 202 28I 432 957 959 5C6 379 474 591 917 566 0 8411
. (I) 6.54 6.43 5.70 3 23 2.51 2 40 3.34 5.14 11.33 11.31 6.97 4.51 5 64 7.12 to 90 6.73 00 100 00 (2) 6 54 6.43 5.79 3.23 2.51 2 40 3.34 5.14 11 33 11 31 6 17 4 51 5.64 7.12 10.90 6.73 00 100 00 (lisPIRCENT CF ALL C000 085(AVAi!0N3 FOR IHIS PAGE (2)*PERC[NI CF ALL CCC3 0$$[fVATICN3 FCI THIS P[R!CD Ce CAtM IWIND 57tt0 LEIS THAN CR (CL'AL 10 60 MPHI
~26-
$143R
o . ,D oEPGDJX_a Radicactiye L1 quid _Efil fS ent Monitpring_Loitr_umentation N. Roauirement: Radioactive 11guld effluent monitoring instrumentation'il'.annels . are required to be operable in accordance with Technical Specification 3.28.A. With less than the minimum number of channels operable and reasonable efforts to return the instrument (s) to operable status within 30 days being unsuccessful, Technical Specification 3.28.A requires an - explanation for the delay in correcting the inoperability in the next Semiannual Effluent Release Report. Respmic: Since the requirements nr Technical Specification 3.20.A governing the operability of radioactive 11guld effluent monitoring instrumentation were met for this reporting period, no report is required. e I A-1 5143R
<=
o , v .- 6
. APPEtIDIX B Radioactive Gaseous Effluent lionitoring Instrumentatiqc.
' EfLqu tgment:
Radioactive gaseous effluent monitoring instrumentation channels are required to be operabic in accordance with Technical 4 Specification 3.28.B. filth less than the minimum number of channels operable and reasonable efforts to return the instrument (s) to operable status within 30 days being unsuccessful, Technical Specification 3.20.8 requires an explanation for the delay in correcting the inoperabillty in the next Semiannual Effluent Release Report. Reapsnic: Since the requirements of Technical Specification 3.28.B governing the operability of radioactive gaseous effluent monitoring instrumentation were met for this reporting period, no report is required. i t (3 l 2 i u B-1 NSlay 4 \-i
. i,
a N 'n APPEilDJX_C Radioloalcal Environmental Mo.nl.tqt na i Program Reauirement: The radiological environmental monitoring program is conducted in accordance with Technical Specification 4.8.A.1. Hith the - level of radioactivity in an environmental sampling medium at a location specified in Technical Specification Table 4.8-1 exceeding a reporting level of Technical Specification Table 4.8-3 when averaged over any calendar quarter, Technical -l Specification 4.8.A.3 requires an evaluation of any release condition, environmental factors, or other aspects which caused
~ the limits of Technical Specification Table 4.8-3 to be exceeded, be reported to the Commission in the next Semiannual Effluent Release Report.'
\
' Response: Since the conditions of Technical Specification 4.8.A.3 were not exceeded during this reporting period, no report is required.
I I b C-1 5143R
., s APPENDIX D x -
Unolanned Radioactive Effluent Releases Reauirement: Technical' Specification 5.9.1.6 requires that the Semiannual Effluent Release Report shall include a list and description of unplanned releases from the' site-to-site boundary of radioactive f : materials in gaseous and 11guld effluents made during the I
- reporting period.
Resoonse: One abnormal gaseous release occurred on December 30, 1986 when radioactivity was discharged through la valve off the gas space
~
on the volume contro1. tank. -The gas was carried-through the ventilation system and released via the primary vent stack. The
- release'was determined.to be not more than 420 curies, primarily.
Xe-133. Neither the dose rate nor MPC limits were determined'to have been exceeded. The effluent activity resulting from this ' incident has been included in Tables'1A and 18. 1 n k l J j- + D-1
~5143R 1
\
+
- + y +re-- -
9,mty'-, - e- w1--*F F'vpr--w--g-m v - 79y-
. . APPEflDIX E Land Use Census Reautrement: Technical Specification 5.9.1.6 requires that a listing of new locations for dose calculations and/or environmental monitoring identified by the land use census pursuant to Technical Specification 4.8.B be included in the next semiannual Radioactive Effluent Release Report. Responia: The results of the first land use census conducted under the newly-implemented Radiological Effluent Technical Specifications are included in Table E-1. E-1 5143R
-.. .. s TABLE E-1
-Maine Yankee'1986 Land Use Census (Distance in Kilometers)
~ Nearest- JNearest' Nearest tillk Animal Sector . Residence. GLrden Hithin-~8 Km N - l '.' 3 1.3 2.7
.NNE 2.3 2.5 -
.NE 1.3 1.3 -
ENE 0.9 1.2 - E 0.9 0.9 - ESE- 1.4. ' 1. 5 -7.1 SE- 0.7 - 3.2 -
'SSE 0.9 1.0 -
S -1.7 2.7 .-
- SSH 3.0- 5.2 -
SH. 1.4 3.8 7.9
.. HSH 1.0 3.0 -
H- 2.6. 2.7 7.2
'HNH- 0.8 2.8 -
NH 2.0 2.0 -
-NNH 1.1 1.1 -
E-2
-5143R
F. APPENDIX F-i
.Liguid Radwaste' Treatment System-Reauirement: Hith radioactive liquid waste'being discharged'without treatment with estimated-doses-in excess of the limits..in1 Technical.
Specification 3.17.C.l'_ a report must be submitted:to the Commission in the Semiannual Effluent Release Report for the period. " Response: The requirements. of Technical Specification 3.17.C.1 were met during this period and, therefore, no report is required. F-1 5143R
? -
g .,, i w
- Gaseous Radwaste Treatment System
~
- Reautrement: 'Hith} radioactive gaseo'us waste being discharged without
= treatment with doses in excess of the' limits in Technical
' Specification 3.18.0;1, . a report must be submitted.. to the Commission in .the Semiannual' Effluent Release Report for the -
period.
~
Response: .The requirements of' Technical Specification 3.18.D.1 were met
-during this perio'd and, therefore, no report.is required.
o n t G-1 5143R
.o r 10' APPENDIX H r
Off-Site Dose Calculation Manual Reauirement: Technical Specification 5.9.1.6 requires that licensee initiated
. changes to the Off-Site Dose Calculation Manual be submitted to the Commission in the Semiannual Radioactive Effluent Release Report for the period in which the change (s) was made effective.
Responte: -Hith the implementation of the NRC-approved RETS on July 1, 1986, several sections of the ODCM were revised to reflect the final requirements of the Radiological Effluent Technical Specifications. The changed pages of the original ODCM submitted to NRC for review are attached for information purposes. The changes to the 03CM include:
- a. Revised dose equations for total body (Section 2.1.1) and critical organ (Section 2.1.2) to reflect the addition of a correction factor (K) to account for changes in liquid effluent dilution flow during periods of release.
- b. The addition to Tablo 2.1 of a liquid dose factor for Fe-55.
- c. The addition to Sections 3.3.1, 6.0, and A.7 to describe a means for determining the critical organ dose due to the burning of contaminated oil in the plant's auxiliary boiler (including dose factors on table 3.3).
- d. Modifications of the radiological environmental monitoring stations listed on Table 4.1 and Figures 4.1, 4.2, and 4.3 to reflect the final requirements of Environmental Monitoring Program required by Technical Specification 4.8.
- e. Corrections to Sections 5.1.1 and 5.1.2 for the methods used in determining compliance with Technical Specification 3.16.A.
11 - 1
. _ _ i
m-
- l e
~
l l i (. TABLE OF CONTENTS (Continued) Pago 3.3.11 Dose to the Critien1 0rgan......................... 15 4.0 ENVIROU;f ENTAL H0HITORING . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 19 5.0 HONITOR SETP0INTS................................................ 29 i 5.1 Technical Specification 4.13.B. Liquid Effluent Honitor Setpoints.......................................... 29
. 5.1.1 . Allowablo Concentrations of Radioactivo !!atorials in Liquid Effluents................................ 30 5.1.2 !!onitor Rosponse for Liquid Ef fluents. . . . . . . . . . . . . . 32 5.2 Technical Specification 4.13.D. Gascous Effluent Honitor Sotpoints.......................................... 33 5.2.1 Allowable Concentrations of Radioactivo !!atorials in Gaseous Effluents............................... 34 5.2.2 Honitor Responso for Gaseous Effluents............. 35 6.0 HETEOR0 LOGY..................................,................... 38
(- 41
-APPENDIX A BASIS FOR I!!E DOSE CALCULATION !!ETl!0DS . . . . . . . . . . . . . . . . . . . . .
A.1 Liquid Effluent Dosos...................................... 41 A.2- Total Body Doso Rato from Noble Gasos...................... 43 A.3 Skin Doso Rate from Noblo Gases............................ 45 A.4 Critical Organ Dose Rato from Iodinos and Particulatos..... 47 A.5 Gamma Air Dos 0............................................. 48 A.6 Beta Air Dos 0.............................................. 49 , A.7 Doso from Iodinos and Particulates......................... 50 ; APPENDIX B Hotooro1ogy........................................ 51 REFERENCES....................................................... 53 1 4
-V-
, _ _ _ _ _ -w,.
g se. o O ( LIST OF FIGURES ~ Number Titio Page 4.1 Environmental Radiological Sampling Locations . Within 1 Kilometer of Haine Yankee 2) 4.2 Environmental Radiological Sampling Locations Within 12 Kilometers of Haine Yankee 24 4.3' Environmental Radiological Sampling Locations Outside'12 Kilometers from Maine' Yankee 25
#.4 Direct Radiation Honitoring Locations Within 1 Kilometer of Haine Yankee 26 4.5 Direct Radiation Honitoring Locations Within 12 Kilometers of Haine Yankee 27 4.6 Direct Radiation Monitoring Locations outside 12 Kilometers from Maine Yankee 28 5.1 Maine Yankee Liquid Radwaste System 36 5.2 Haine'Yankoo Gaseous Radwaste System 37 I -
-vi- _ -_
3 ; O LIST _OP TABLES (E
-Number Titio Page 2.1 Maine Yankoe Dose Factors for Liquid Releases 6' 3.1 Maine Yankoo Dose Factors for Noblo Gas Rolenses 16-3.2 Haine Yankee Dose Factors for Iodines, Tritium, and Particulate Releases 17 3.3 Maino Yankco Dose Factors for Iodino, Tritium and 17a Particulate Released Via the Auxiliary Dollers 4.1 Radiological Environmental Honitoring Stations 19
- j.
Maine Yankee Maximum _ Annual Average Atmospheric 6.1 38 Dilutica Factors k 9 (; [ t i
-vil-
9
,e
/
f ., t 2.1.1 Doso to the Total Body The total body dose in mrom for a liquid release is: tb i itb (2-1) I where: Q.1 is the total activity ralcased for radionuclide i, in Ci (for strontium and Fe-55 use the most recent measuremont available): DFL is the site specific total body liquid dose itb factor for radionulcide i, in mrem /Ci (sco Table 241); and K is equal to 935/Fd; where F (typically monthly average)d.is dilutionthe flowaverage of the circulating water system at the point of 3 C., dischaaje from the multiport diffuser (in ft /sec).- i T (.
- t. - _ - _ _ _ _ _ _ _ _ _
o .c 9
/
c 2.1.2 Dose to the Critical Organ The critical organ dose in n em for a liquid release is: D = K Og DFL $2-2) ico 1 uhere: is total activity releaced for radionulcide i, O*. in Ci (for strontium and Fe-55 use the most recent measurement available): DFL. is the cito specific critical organ liquid Ic dose factor for radionuclide i, in mrcm/Ci
.(see Table 2.1); and K is equal to 935/P I"h #" is the average d
(typically monthly average)ddilution flow of (' the circulating vater system at the point of discha59 fr :n the multiport diffuser (in ft /sec). k-J 3-
. +
' 'o u
.4 Table 2.1 i Maine Yankee Dose Factors for Liquid Releases-Total Critical Organ Dose Factor Dose Factor mrom/Ci mrom/Ci DFL DFL Nuclide itb ico 11 - 3 2.96E-07 2.9GE-07 Na-24 2.46E-05 2.83E-05 Cr-51 1.54E-05 1.45E-03 Mn ,54,' 4.27E-03 2.55E-02 Mn156
- 1.89E-06 4.09E-05 Fe-55 1.24E-02 7.53E-02 l Fe-59 8.58E-02 6.54E-01 Co-58 2.22E-03 1.35E-02 Co-60 4.79E-02 7.80E-02 Zn-65 2.68E-01 5.39E-01 l
l, Sr-89 2.13E-04 7.45E-03 Sr-90. 3.lGE-02 1.29E-01 l 1.74E-02 Zr-95 5.15E-04 [~ Mo-99 2.95E-05 2.63E-04 5 Tc-99m 3.79E-05 6.22E-05 l Sb-124 1.34E-03 9.36E-02 I-131 2.07E-04 9.86E-02
}'
I I-132 2.53E-06 3.24E-06 b I-133 2.46E-05 1.13E-02 I-135 7.26E-06 4.31E-04 Cs-134 2.798-02 3.12E-02 i d Cs-137 2.92E-02 3.41E-02 Ba-140 1.54E-04 3.41E-02 Co-141 2.81E-05 9.13E-03 I W-187 6.28E-06 1.32E-03 e b ' lL,. ._- _ -_--- - 1
l l
, : s.
o 3.3.1 Dose to the Critical Organ The. dose to the critical organ in mrem f rom iodine-131, iodine-133, tritium, and radioactive materials in particulate form with half-lives greater than eight days released via the olant stack is: O gg
= Qg DFG ico
( -6) i where: Qg is the total activity of rad.ionuclide i released via the plant stack during the period of interest, in Ci; and DFG jc, is the site specific critical organ dose factor for radionuclide i for a' gaseous release from the plant stack in mrem /Ci (see Table 3.2). ( The dose to the critical organ in mrem f rom iodine-131, iodine-133, tritium, and radioactive materials in particulate form with half-lives greater than eight days released to the atmosphere from the auxiliary boiler due to the' burning of contaminated waste oil is: I 1 aux
! D = Q . DFW (3-7) co 1 ico where:
is the total activity of radionuclide i released via the auxiliary Qf boiler stack during the period of interest, in Ci; and .]. r 11 DFW is the site specific critical organ dose factor for radionuclide i 9 for gaseous release f rom the auxiliary boiler, in mrem /Ci (sce Table 3.3).
- (. ..
- g .-
9 o- . e
.v Talile 3.3 Maine . Yankee Dose Factors for Iodine. Tritium._
and Particulate Released Via the Auxi_11ary Boiler
- Critical Organ Dose Factor (mrem /Ci)
Nuclide DFWico H-3 2.37E-03 C-14 1.58E+00 Cr-51 7.35E-03 Hn-54 1.04E400 Fe-59 1.15E440
' 4.78E-01 Co-58
'Co-60 1.62E401 I 2n-65 2.55E400 1.30E-04 b- Rb-88 2.50E+01 j Sr-89
' Sr-90 9.57E+02 Zr-95 1.24E400 f Sb-124 2.00E400
(...I I-131 3.73E402 1-133 4.33E+00 I-135 2.01E-01 Cs-134 3.46E+01 Ba-137 6.09E401 Cc-140 4.99E-01 Ce-141 3.35E-01 i
!, Cc-144 7.96E+00 l
- DFW $c, for use with the burning of contaminated waste oil.
C.
-17a-
I.. i g s ; i
}
e , TAllLE 4.1 (Continued) Radiological Environmental lionitoring Stationsa Distanco Direction Exposure pathway- Sample Location From the From th'o and/or Sample and Designated Codo b plan t - ( bn) plant
- 4. INGESTION
- a. Hilk T!!-16 Baker Farm 7.2 W TH-17 Looman Farm 7.9 SU I!!-25 !!anson Farm 16.0 W
- b. Fish and Fil/11U/CA/ IIA-ll Long Lodge Area 1.1 S Invertebratos FII/l!U/Cn/ IIA-23 Doothbay liarbor' 12.6 SSE FII/l!U/CA/ IIA-24 'Shoopscot Rivor 11.2 S
- c. Foo'd Crop f TV-IX Indicator - -
Vogot'ation (to bo determinod) TV-IX Indicator - - (to bo datorminod) TV-2X to be datormined - - Footnotos: a 'Samplo locations are shown on Figuros 4.1 to 4.6. b Station-lX's are indicator stations and Station 2-x's aro control stations, c A dilution factor of 10 chall bo applied to any radioactivity detected in a samplo at this station.
'd. The station codo lottors will vary with the samplo media collected. The sampling of all four media typos is not required during each sempling
-period.
e Control station may bo oither Station 23 g Station 24 doponding on camplo specios collected at indicator station.
- f. Food crop compling is not required uhile milk compling is being dono.
.. l k,
.b
- f .
jr
-( * : .
e o
/. / *
/l *-
N. ,/ / - J
- I
/ \rls % ,
. I S g N. ,.*
* \ J
~ .
f
\ \ ,.* .
l.P. t . '. . 1 . .
-- SITE r.OU: MARY ;
I . s . . [ . f .
, : c .:
I : 6 :
. . a .
.: l:
l' f s' : # .
/
s' %
... WC-13
***
- Ar/CF-Il *
,I -
, \ ,
l
, . . l
* . s . *
.l*
f. j ...
* / PRIMARY VE!!T STACK
. i;/j
.* *l l
..' ;. G ,.
- l f. . *
=
. s ,
LIESTrQ2T ISLM.9
\ .* * ..
..j
, ut-It . .
.. . l CAltlY VT. ,
. ..i
'Il
! * ** p3.gg I .
. ,)
CA.Il *
.lf
.I
. a SE-lO .
. i .
. t @ .
* * . ,00
- g i, ..
.- t a.i t Cag 1 --I *
, l
- gg filFiUSt R ww _-:3 ,
. h , *
?ttif tt".
ll n,-r @ hi k f i r,URE -- .
.4.1 i f
. . . _ E..n.v..i .
uAnhAm_Jutihrare r.n.n.'re n.t..a.l. - - - - m1 *ia..a fuedYarnkee i o '.ol _u l 5 wa l i r " L c c a t i '.nl
,. ~ e; e
e n
, i. -
) @
W l a n'n.13.us
'5' -
1 $ ' O' W15CA55Mi e.
.M -
. AI'/ Cr .' 14 1:
. SEE ENLAR'ilstENT 84 FtrURE 4.8 At'fcL. s t _ .
.c I.-
1,
/ ;
4
'I' - N. .-
N(QUA$$[T [AK('
- 8;
- o [0GECOM3, .
@ uc.2t. .
t ... ,
! ')
1-
. n,. i,, e'- -
. \
j*
~. ,
' - ,@ Al*/CF-16; , , ,
I I.d . e .. 8
- h. f .
^
5
? > .
ME-10 .. ' ;
.' ph -
- Y BATH e . 3 @'e WOOLWICil g.y l .
} :h q I
' , Dt-il .
. , g
' b_
- b. , '. ' ,h w
.. v e
t' .i = r - v
* ('
9 .. ,' ' .
~.
p y - j ' Fit.24 sm.:4 C 000fHBAY HAR202 n.g.yt g O., 'I A.24
, ' "\ 25
.' r.terc w IstAc '
TIGURC 4.2
/ _
Invironmenttil Rat 11oloriltal Samplinq t ocations _ Witisin 12 r.ilcm?ters of 11aine Yankee \ -2 3 -
~
, -l e
\ c
- e. <-i, i ,,, i, . : ...,,,.....
- l .
. .g
.' f 5 k P. ) ,
Ric, n.. . e
,- [. DRl5Dite l SCE ENLARntitlut tu FIG 1RC 4.1
\
~:'
) tituct.Sitte .-. 1 .
.p 1,
_,' h'g
.'e 0?P.ARl500TTA I -
00w00ltiltAM e . If , l .
.T E COM3 .
Tit-256- pi,ytt
- y e CR15fCL t
l-
.:g ,
"J " f :
. . cj .
i
' I
- M
- .. o,
,,, , < e .
m,, e: t
; mm,,
-f (..c-,) . '
o
- Td I 1,: .- [ :I
(
' ?'
. -. - . .:'y .b - .,. -- -- l
.. :e :
- y .
. 4:.l
)
I . A T L AI.7 [( (,1([ 4y 1 I O l t) p i e-- --a i.____.._,_j k i I t,stt t I l'% fitt!QE 4.3 ( Environr, ental Padiologi_ca,1_53rgp1in_g 1 oqa t lens. Ontside 12 Kiloceters Fron 11aine Yankee ao
a c. 5.1.1 Allowablo Concentrations of Radionctivo 11ntorials in Liquid Effluonts Technical Spocification 3.16.A.1 requires that the concentration of radioactive material in liquid offluents rolenced from the sito to Back River bo limited to the concentrations specificd in 10 CFR Part 20, Appendix B, Tablo II, Column ~2 for radionuclidos other than noblo casos and 2E-04 microcuries/ml total activity concentration for all dissolved or entrained noblo' gases. To ensure compliance with Tochaical Specification 3.16.A.1, the following method may be used for each release of liquid offluent. Prior to each release a grab sample will be analy: ed to determine the activity concentration of each radionuclido. The !!PC-fraction, R , for each liquid 3 offluont release point will bo calculated by the rolationship defined by lloto 1 of 10 CFR Part 20, Appendix B: R (5-1) 3= i 1 whoro: R is tho !!PC-fraction for the roloaso point j, dimensionless; C is the diluted activity concentration of radionuclido 1, in uCi/ml; and is equal to undiluted concentration of radionuclidoi times fl F F The total dilution flow in gpa fj Thb flow rato of the offluent relonso at point j in gpa
!!PC g
is the maximum permissiblo concentration of radionuclide i as specified in 10 CFR Part 20, Appendix B, Tablo II, Column 2, in uCi/ml. Tho !!PC-fractions for the various relcare raints are then cu=ed to yield the total ItPC-fraction, R: R = . P 'o- Rd_)
t _ Je; 2 *" , e
'The total'MPC-fraction,'R,:at the discharr.,e to the-Dack River must be' loss than or equal to one.
'R'= < 1 (5-3) e I
9 9 k '- L t t e i i
\
. I
o-
- 9
'5.1.2 Monitor Rosponso for Liquid Effluonts
{- The responso of each liquid offluent monitor is established by combining the appropriate concentration, flow rato, dilution, principal gamma emitter, goomotry, and detector officiency. The radiation monitor alarm / trip notpoint for a' tost tank roloaso is set such that the sum of the HPC ratios of the diluted nuclidos is loss than or equal to 0.6 at the discharco to the Back Rivor. The setpoint is dotormined in tho following manner:
- 1. The CPH of each undiluted nuclido is detormined from the responso graphs._ If a nuclido other than 58Co 60Co, 131I, 133I, 134Cs and 137Cs or unidentified nuclidos contributes more than 10% of the total activity uso, the conservative 131I rosponso curvo to dotormino the CPH. (Unidentified nuclido activity is dotornined by subtracting identiflod activity from gross gamma activity.)
I
- 2. Set tho alarm sotpoint at background plus the calculated CUP from Stop 1.
3.. If the dischargo HPC ratio is calculated to bo loss than 0.6, you can incroeso the alarm sotpoint Cl!P by a factor of 0.6/actuni ratio.
- 4. The HPC ratio for a test tant discharge may bo increased to loss than 1 if it is dotormined that no other radioactivity is boing roloased to the Back River.
(
,4 :
6 . Tir . 6.0- HETEOROLOGY [ The atmosplieric ' dilution f actors in the dose calculation methods assume - an Lindividual whose behavior inevitably leads to a dose higher than anyone else. Since annual _ average meteorology varies little from year to year, the location of. this critical receptor can be predicted by scanning all the reasonable off-site locations to find the location with the highest dilution factors. Important off-site locations are: site boundaries and nearest residences in each of the sixteen meteorological sectors, as well as all farm locations within five miles of the plant. Exposure pathways assumed to exist at site boundary locations are direct exposure f rom radioactive materials in the air, direct exposure f rom I .-
' radioactive materials deposited on the ground, and exposure from inhalation of L radioactive materials. In addition to the pathways present at site boundary lo' cations, exposure pathways present at cach residence include ingestion of radionuclides in home grown vegetables. All farm locations. include all l
exposure pathways found at residences plus ingestion of radionuclides in meat n i and milk. tieteorological data for the year 1979 through 1983 were analyzed for the values of the maximum annual average dilution factors at the important receptor locations described 'above. Yankee Atomic Electric Company's (YAEC) AEOLUS computer code (Reference 2) calculated all atmospheric dilution factors. Appendix B briefly describes the YAEC AEOLUS computer code model. Table 6.1 lists the maximum annual average dilution factors for all important receptor locations for releases via the plant stack. Each dose and dose rate calculation method incorporates the maximum applicabic off-site annual average dilution factors listed in Tabic 6.1. The maximum potential dose to a member of the public due to plant stack releases in any year will be conservatively estimated by the dose calculated for a f hypothetical full-time resident living on a farm 120 meters from the plant in
.the south sector.
I l i_ A.7 Dose from Iodinos and particulates {- Method I is used to demonstrato compliance with Technical Specification 3.17.c which limits the doso commitmont to a member of the public from iodino-131, iodine-133, tritium and radioactivo materials in particulato form with half-lives greater than eight days in gaseous offluents released via the plant stack or auxiliary boiler stack to areas at and beyond the site boundary. The dose commitment to an individual from iodine-131, iodine-133, tritium and radioactivo materials in particulate form with half-lives greator than eight days released to the atmosphoro via the plant stack is calculated using tho methods of Equations 12, 13, and 14 in Rogtlatory Guido 1.109 (Reference 1). Gaseous pathways contributing to individual dosos at Maino Yankoo are: external irradiation from radionuclidos deposited on the ground surface, inhalation of radionuclidos in air, and ingestion of atmospherically rolcased I radionuclidos in food. The uso of the methodology of Equations 12, 1;, and 14 for a one curio release of each radionuclido in gaseous offluents yielded tho doso impact to the critical organ. Table 3.2 lists the resulting site specific critical organ dose factors for plant stack releases giving the number of millirem por curie released for each radionuclido. Since the doso factors of Tablo 3.2 represent a varloty of critical organs, method I conservatively calculates a critical organ dose consisting of a combination of real critical organs. Similiarly, Tablo 3.3 lists the sito specific doso factors for releases via the auxiliary. boiler resulting from burning of contaminated wasto oil. Except for tho site specific values noted below, wo utilized the paramotor values recommended in Regulatory Guido 1.109 (Roforence 1) to derive the critical organ doso factors for lodinos and particulatos. Hilk and moat animals are on pasture 50 percent of the timo, consumin6 ( 100 porcent of their food from pasture during that period. This assumption is conservative sinco most dairy operations use supplomontal fooding of animals when on pasture or actun11y rostrict eninnis to full tino slinge fonding, m
'_ A s.
- f. b'
- -- deposition rates'(2 models),'and
(. ~ , l
> - ~ dose statistical distributions for postulated accidental radioactive releases and exposure intervals (based on dose rate data per unit
-dilution factor (X/Q) as input; thyroid, total body beta, total body gama and skin doses).
AEOLUS pro' duces hourly and long-term averages of: 4
- non-depicted dilution factors for evaluating ground level
' concentrations of noble gases, tritium, carbon 14 and non-elemental iodines, l
- depleted dilution factor for estimating ground level concentrations of elemental radioiodines and other particulates,
~
effective gamma dilution factors for evaluating gama dose rates from a sector-averaged finite cloud (multiple-energy undepleted source), and l .m
. deposition factors for computing dry deposition of elemental radioiodines and other particulates.-
l A more detailed description of the AEOLUS diffusion model is provided in section 2.3.5 (long-term diffusion estimates) of the NEP 1 and 2 PSAR (Reference 4) and the AEOLUS computer code manual (Reference 2). l ! Annual average non-depleted dilution factors, of fcctive gama dilution factors and deposition (D/0) rates for Maine Yankee were calculated using the j_ ' following AEOLUS options; Sector-average model with temperature dif ference 1- ( AT) atmospheric _ stabilitics, spilt-il model, plume rise, and no recirculation correction factors for the plant stack, or as a ground level release point for t the auxiliary boiler. Dilution factors due to the plant stack for'the critical locations are provided in Table 6.1. b. i
2 - . 9
-APPEilDIX I Lower Limit of DelKtion for RadiologLcal Analyleg Reguirement: Technical Specification 4.13 requires that when unusual circumstances result in LLDs higher than required, the reasons shal_1 be documented in the Semiannual Radioactive Effluent Release Report.
Response: On occasion, the specified LLDs for Ce-141 and Zn-65 ..ere not met. This was due to interference from other nuclides detected in the sample. For Ce-141, this occurred in 12 samples, and Zn-65, in 7 samples. I-1 5143R
.(
2 $ * ' ( APPENDIX J Reactor Coolant System Activity Bagpirements: Technical Specification S.9.1.3 B requires that a repord. covering the results of specific activity analysis in which the primary coolant exceeded the limits of Specification 3.2, be submitted annually for the previous calendar year. The report shall include (1) Reactor power history starting 48 hours prior to the first sample in which the limit was exceeded; (2) Results of the last isotopic analysis for radiolodine performed prior to exceeding the limit, results of analysis while limit was exceeded and results of one analysis after the radiciodine activity was reduced to less than limit. Each result to include date and time of sampling and the radiolodine concentrations; (3) Clean-up system flow history' starting 48 hours prior to.the first sample in which the limit was exceeded; (4) Graph of the iodine-131 concentration and one other radiciodine isotope concentration in microcuries per gram as a function of time for the duration of the specific activity above the steady state level; and (5) the time duration when the specific activity of the primary coolant exceeded the radiolodine limit. Response: The information for two instances requiring reporting are shown in Tables 7A and 78 and Graphs 7A and 78.
A
\
J 5143R
N 4;
' [ ,
DM -
'L - '"
./; '
TABLE 7A w M.g , .p *
> a 4 k' . q .:
> ^ . Reactor . Letdown Date Time m Radiciodine' Activity (Uci/am) Power Flow Rate p
s I-131 -{,132 _ , I-133 I-134 I-135% _LU ?/JEj (GPM);
; ira ~_ -
t I*r. ,
' -; ' ) , ->
,.,m
'. w 10/17/86 '
C_ 100 '80/ - ' y I' . . [ . 10/18/86 0438 .7/01E-2 8,46E-2; ,l'.11E-1 1.66E-1 '1.29E-1 '1.17E-1. 100 80
~<r; s c y ;; -
+60/19/86 0111 M
~
y- PLANT 80
-r TRIP-0310 2.96 1.29 3.28 1.46E-1" 1.96 /
4X~ 0 122 0453 .3.04 8.53E-1 3.21 9.38E-2 .3 94 0 i.146 ~-.3 y. 0704 - 2.59, 4.81E-1 , 2.62 1.66E-2 1.19 '3.41 ' 0 ..-132 - 0855 2.16 2.68E-1 2.04 7.81E-1 , 2,79. 0 147 1040 1.83 2.13E-1 4- 1.66 - 5.86E-1? J'2.34 0 - - 134 a 1310' 1.38 1.41E-1 1.16 # 3.62E 1.72 0f - 131-1503 1.15 1.33E-1' 9735E-1 P< 2.36E-1_ 1. 43 0 . 93' 1635 1.07 1.24E-1 8.15E-1 1. 83 E--1, 1.31 1 0 " 104-I ._^ 1734 1.02 1<24E-1 7.47E-1 1.59E-1. I'.21 0 104
~
1924 8.1PE-1 1.22tE-1 -5.80E-1* 1.11E-1 9:88E-1 .0 103 2206 7.23E-1 1.15E-1 4.gry 80E-1 7.62E-1 J 8.53E d y 1 ~11 102 10/20/86 2400 , yy /{$/ ~ - ,, . _,
" .99.8 137 (max)
. .. -?x ,
1,0 10/21/86 ser 4-
; 0 115 (max) w
~
)..^- a1 -
10/22/86 ' 1 ,-
' d i'l ~ .' '
100 80 9 " V - . .- .
-r x 1 HOURS DOSEQ'. 1-131 cxcee'ded Iuct/gm=18 hours,ifm:'iisutes #
s
,%*/ \e f v .<
w .,
- ,- ; 73_ - -
.,5 -
5143R , J-2 4-
. n
,, "i
- c-h g
= _ _ . __ t r. , 4 _'*
., .- a e
!!l1lll I!lll:Ill, 1ll!1 ll11l j
2
- q 13 '
33 - ' 11 - II 8 2 Q v E S O D
~ ='
~ -i e
N .' 6 % 6 s
/ =i 9
1
/
0 1 6 i 4 0 N 2 2 N - 1 S 0 1 x i 2 R U A 7 1 1 N O H ( k H 1 3 P - A : s J R ,i E S
\'
G H E J J
,' T T
I V N I T x ,'a C A x E N I k
,'e D \
O N I
\ '
\
'4 N
~
t I
'2 1I I
I
~/
f
. . . - . - . ' ~ . . - '
?J OJ 3J =S . " .=N* : a .".N 0d .* .~. .u.~ .
.* N E=N Ue mW*& > U c
. 2:
TABLE 78 s-Reactor . Letdown' - Date Time Radiciodine Activity-(Uci/am) Power' Flow Rate I-131 I-132 I-133 I-134 I-135- DEI (%) (GPM) 11/13/86 , 100 80 11/14/86 100 80' 11/15/86 0250 7.04E-2 9.87E-2 1.43E-1 1.77E-1 1.50E-1 1.28E-1 -100 80-2119 PLANT TRIP 2242 1.77 1.15 2.47 4.86E-1 1.67 2.62 0 l 11/16/87 0035 2.40 9.83E-1 3.11 1.52E-1 1.79 3.43 0 0219 2.24 5.89E-1 2.70 3.71E-2 2.99. 0-0415 1.84 3.51E-1 2.12 9.54E-1 2.50 0 0615 1.39 2.13E-1 1.51 5.66E-1 1.85 0 0815 1.28 1.82E-1 1.30 4.16E-1 1.67 0 119 1215 8.20E-1 2.23E-1 7.57E-1 6.09E-2 2.16E-1 1.05 1515 5.41E-1 1.91E-1 4.69E-1 1.18E-1 1.37E-1 6.88E-1 2015 3.58E-1 1.29E-1 3.07E-1 .97E-1 4.49E-1 11/17/86 74 120 [ 10/21/86 97 115 HOURS DOSEQ - I-131 exceeded I uci/gm = 18 hours, 56 minutes j l 5143R J-4 1 I
GRAPH 78 .- 0 ' IODINE ACTIVITIES: 21:19 11/15/86 - 16:15~11/16/86 ' - E._ i
~
b x , e:-- / g
-- / g DOSE Q - I-131 - - -
7 g I-133 ra 7 ". -- / \ N o" / \ i
/ \
\
$O 4 _. / N .
/ N if, . --
/ \s w -
l r
- N
>@-- N x
! C~ ; N e N M ' f N f N f N
- S..f g ,
'N
~%
i i S. .! g .i I ' Is 2 4 's a ls $2 i4 la TIME (HOURS.) I J-5
MAME HARHEE AWMICPOWERCOMPARUe ,,,aug,aja?n"g%e h (207) 623-3521
$ March 2, 1987 MN-87-23 GDH-87-44 Region I United States Nuclear Regulatory Commission Office of Inspection and Enforcement 631 Park Avenue King of Prussia, Pennsylvania 19406 Attention: Mr. Richaro H. Vollmer, Regional Administrator
References:
(a) License No. DPR-36 (Docket No. 50-309)
Subject:
Semiannual Effluent Release Report Gentlemen: Enclosed is the Maine Yankee Semiannual Effluent Release Report. The report includes the annual meteorological summary, annual estimated maximum potential dose, the annual reactor coolant system activity report and changes to the Off-Site Dose Calculation Manual. These reports are submitted in accordance with Technical Specifications 5.9.1.6 and 5.9.1.38. This report covers the period from July 1,1986 to December 31, 1986. Very truly yours, MAINE YANKEE ATOMIC POWER COMPANY b h Av' G. D. Whittier, Manager Nuclear Engineering and Licensing GDH/bjp
Enclosure:
(62 paget) cc: Mr. Ashok C. Thadani Mr. Cornelius F. Holden Mr. Pat Sears Mr. Donald Hoxie - DHE Mr. John Brochu - DEP Aiaerican Nuclear Insurers Document Control Desk f United States Nuclear Regulatory Commission Washington, D. C. 20555 7269L-DS _. _ _ . - . _ _ _}}