ML20029A960

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Effluent & Waste Disposal Semiannual Rept for Third & Fourth Quarters 1990
ML20029A960
Person / Time
Site: Yankee Rowe
Issue date: 12/31/1990
From: Papanic G
YANKEE ATOMIC ELECTRIC CO.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
BYR-91-030, BYR-91-30, NUDOCS 9103050153
Download: ML20029A960 (22)
v • d • e


Text

.

YANKEE ATOMIC ELECTRIC COMPANY "N*"Hl.**gly'lfpl" n.h

, 6. p')

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580 Main Sheet, Bolton, Massachusetts 017401399

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i February 28, 1991 BYR 91-030 i

t'nited States Nuclear Regulatory Conunission Document Control Desk Washington, DC 205$5 l,

Referencet (a) License No. DPR-3 (Docket No. 50-29) j

Subject:

Semiannual Effluent Release Report f

-Dear Sir Enclosed please find the tables summarising the quantities of radioactive liquid and gaseous effluents and solid waste released from the. Yankee plant at 4

Rowe, Massachusetts for the third and fourth naarters of 1990 submitted-in L

'accordance with Technlcn1 Specification 6.9.5.b.1.

The summary of the estimates of off-site radiation doses resulting from plant effluents during 1990 vill be provided in a supplemental report in accordance with Technical Specification 6.9.5.b.2.

We trust that this information is satisfactory; however, should you have any questions, please contact us.

Very truly yours.

YANKEE ATOMIC ELECTRIC COMPANY Geo

nic, Senior Project Engineer Licensing GP/gjt/WPP77/12 Enclosures cci-USNRC Region I USNRC Resident Inspector YNPS 4-

/.

t 9103050153 901231 1

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1 EFFLUENT AND k'ASTE DISPOSAL SEMIANNUAL REPORT FOR Ti!IRD AND TOURTil QUARTERS 1990 F

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Yankee Atomic Electric Company i

Rowe,_ Massachusetts

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4 IJST OF TAEl.E8_AtiD_AEEniDICES Ente 1A Gaseous Effluents - Summation of All Releases 1

1B Gaseous Effluents - Elevated Re1 cases 2

10 Gaseous Ef fluents - Ground Level Releases 3

2A Liquid Effluents - Summation of All Releases 4

2B Liquid Effluents - Routine Releases 5

3 Solid Waste and Irradiated Fuel Shipments 6

APPDIDIX A Radioactive Liquid Effluent Monitoring Instrumentation A-1 APPENDIX B Radioactive Gaseous Ef fluent Monitoring Instrumentation B-1 APPENDIX C Liquid Holdup Tanks C-1 APPENDIX D Radiological Environmental Monitoring Program D-1 APPENDIX E Land Use Census E-1 APPENDIX F Process Control Program F-1 APPENDIX G Off-Site Dose Calculation Manual G-1 APPENDIX H Radioactive Liquid, Gaseous, and Solid Waste Treatment Systen i H-1 APPENDIX I Supplemental Information I-1 l

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TABLE 1A IAnh.te Atomic Electric Company 2 Eowe. MaalAthuntitA Ef.ilutat and Watte. Dispagal Semiannual _Repari

. Third and Fourth Ouarters..1990 Caseous Effluents - Stimmation of All RelenERS Unit Quarter Quarter Est. Total 3

4 Error. %

A. Fission and Activation Cases

1. Total release ci 4.50E+00 1.31E+01 5.50E+01 _
2. Averace relegge rate for veriod uCi/see 5.72E-01 1.67E+00
3. Percent of Tech. Spee. limit (1) 2.90E-03 1 11E-QL B. Iodines
1. Tgtal Iodine-131 Ci 1.10E-04 1.1SE-07
  • 2.50E+01
2. Average release rate for period uCi/sec 1.4QE-05
1. 50 E-OL
3. Percent of Tech. Soec. limit (2) 6.32E+00 8.03E+00_

C. Particulates

1. Particulates with T-1/2 > 8 davn C1 1 06E-05 1.27E-05 3.00E+01 1
2. /sverare release rate for oeriod ici/see 1.35E-06 1.62E-06
3. Percent of Tech _Sg3 E limit (3)

(3) t

4. Grogg._pipha radioactivity C1

<6.43E-08 d.24E-08 D. Tritium

1. Total release C1 1.23E+00 5.24E-01 3.00E+01
2. Averace release rate for oeriod uCi/see 1.56E-01 6.67E-02_
3. Percent of Tech. Secc. limit (3)

(3)

(1) Technical Specification 3.11.2.2.a for gamma air dose.

Percent values for Technical Specification 3.11.2.2.b for beta air dose are approximately the same.

(2) Technical Specification 3.11.2.3.a for dose from I-131, tritium, and radionuclides in particulate form.

(3) Per Technical Specification 3.11.2.3, dose contribution from tritium and particulates are included with I-131 above in Part B. 8796R

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IMEE_1b Xanket Atomic.Elec.tzic_Com a m _EcEcu nassachuarLLs Elfluent_and Wagig Dig.pqtal.Seminnnual Repati Ihlrd and Tcurth Outriera 199D QAsig.us. E f finen11 __EltYa.tti.Ec1RAata C0A11Rucus Mode Entc.tLMade Nuclidge Releas.Ad.

Unit Quarter Quarter Quarter Quarter g

3 f,

3*

4 l

1. Filainn_ Gases Krypton-85 CA 1.82E+00 9.661-04 1.18E 00 9

Krvoton-85m Ci (l.hl3.E-03 1.21E-01

<2.54E-05,,

i Krvoton-87 Ci

<7.20E-03 1.65E-0L

<4 21E-Qi_

Krypton-88 Ci

<1.21E-02 2.75E-Q1

< ldS t-Qi__.

........Xenen -13 3 Ci 2. 251,f00 1.4BE+00 (7.8BE-05 it.33E-03 3.261+00 (2.54E-05 l

Xenon-135 Ci Xenon-135m Ci (2 d2E-03 5.70E+00

<1. 24E.QL _

.__ Xenon-138 Ci (2.00E-03 8 61E-03

< 9. 73 E-OL

_ Xenanzij2m Ci 3 37E-02 (Lh3E-01 (LDSL-Ql_L_.

Arec$-37 Ci 9.90E-03 1.42E-02 1.41E-03 Arron-41 Ci_

c i DOE-02 1.93E-01 cl.0BE-04 Carbon-14 Ci 3.61E-01 1.93E-04 7.25E-01

_,__.Xtnen-131m

-- _ C1 2 d2E-02 4.6kE Q3

<9.39E Qt _

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Unidentliled

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Total for oeriod C1 4.50E+00 1.12E+01

-1.91E+00

)

1,._.lgd in e a Inding-111 C1 1.10E 121BE-Q]

01DJE-O L Iodine-133 C1

<1.69E-06

<1.2QE-06 d 3BE-08 j

Iodine-135 Ci

<8.45E-07 (6.00E-07 tl.69E-08 Tots 1 for oeriod Ci

1. 7.QE 04 1.18E-07

<B.10E-08 L Particulatgs Strontlum-89 Ci

<1.90E-06 (9.80E-07 (3 J2E-07 Strontium-90 Ci

<4.20E-07 (2 11E-07 (4 d9E-08

__.01gium-134 Ci 3.75E-07

<1.63E-07 (2.76E-03.

Casium-137 Ci 6.28E:07 943E-07

< 4 10E-qB._._

(8.htE-0B Ba riurg-Egn.thanum-140 C1 l O6E-06

<5.10E-07 t

i Zine-65 Si (1.10E-06

<4.09E-07

<6.93E-0B Cobalt-58 01 1.04E-06 3.04E-QJ.

.__. 13.85E-0B Cchalt-60 Ci 5 131-Q6 1.01E-05

<9.R6E-08 (6.l4E-08 Iron-59 C1 3.0$E-07

<3 8,01-07 t

Chromium-51 C1 4.82E-07

<1.05E-06 (1.72E-07 2irconium-Niobium-95 Qi

<8.19E-07,_,LSOE-07

<3.03E-08 11 3}E-07

< 1,2$I:QJ_.

<2.22E-0B Cerium-141 C1 1

Cerium-144 C1

<1 d5E-06

<5 91E-07

<1.0QE-Q1__

Antimony-124 C1.

<4.52E-07

( 1. b.QE_Q 7 IL11E-QB_

Mangane s e-54 Ci 1.57E-06 1.13E-06 d.60E-08 (l 43E-07

<1,59E-06

<2.70E-07 Silver-110m C1 t

Malyhdenum-99 01

<3.18E-06

<1.18E-06 (LQQE-Q1_,

Ruthgaluto-103 Qi

<h.09E-07

<1.43E-07 (Lh2E-08 Total for oeriod C1 1.06E-05

_LR7E-05

< 1. 6 7 E,.0 6 l

  • There were no batch mode releases during this reporting period.

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' Yankee Atomic Elegiric comoany. Rowe. Maggachusetts Effluent and Waste D,iApagA1 Femiannual Report Third and Tourth Ouarters 199D SAgeous Efflutata - Ground 1.evel Releasta i

There were no routine measured ground level continuous or batch mode gaseous j

releases during the third or fourth quarters of 1990.

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TABLE 1A l

Yankee Atomic Elegirie CompanL_AQm_liataadtus1Lt8 Effluent and Waste Disposal SemiaDanal Report

]

Third and Fourth Ouarters 1990 j

Licuid Effluents - Summation of All Releases i

1 Unit Quarter Quarter Est. Total 1

3 4

Error, %

l A. Fission and Activation Products l

l

1. Total release (not including i

t-itium. cases aloha)

C1 1.21E-02 3.25E-03 2.00E+01 I

2. Average diluted concentration durine period uCi/ml 1.50E-08 7.59E-11
3. Percent of applicable limit (1) 6.62E-03 2.00E-04 B. Tritium 1 Total release C1 1.74E+01 1.77E+01 1.00E+01
2. Average diluted concentration durine period uC1/mi 2.15E-05 4.14E-07

___3.

Percent of neolicable limit (1) 7.17E-01 1.38E-02 C. Dissolved and Entrained Gases

1. Total release C1 1.29E-02 3.36E-02 2.00E+01
2. Average diluted concentration durine period uC1/mi 1.60E-08 7.85E-10
3. Percent of applicable limit (2) 7.98E-03 3.93E-04 D. Gross Alpha Radioactivity
1. Total release ci 1.56E-Q7 (2.68E-06 e3.50E+01 E. Volume of vaste released (prior to dilution) liters 1.17E+06 6.03E+06 3.00E+01 F. Volume of dilution water used durine ceriod liters 8.08E+08 4.28E+10 7.00E+00 (1) Concentration limits specified in 10 CFR Part 20, Appendix B, Tab 1' II, Column 2 (Technical Specification 3.11.1.1).

The percen* or applicable limit reported is based on the average diluted concentration during the period. At no time did any release exceed the concentration limit.

(2) Concentration limits for dissolved and entrained noble gases is 2.00E-04 microcuries/ml (Technical Specification 3.11.1).

The percent of applicable limit reported is based on the average diluted concentration during the period. At no time did any release exceed the concentration limit.

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ZdllL.la Yankee ltomic Electric Company. Rom _Maganchuse t ts Effluent and Wanie.Disprani SemiannuallersIt Third and Fourth Ouartng._10.Q J

liquid Effluent.s - Rautint lein.atta Continuous Mode Batch Mode Nucliden Released Unit _

Quarter Quarter Quarter Quarter 3

4 3

4 Strontium-89 Ci

<1.02E-05

<1.50E-04

<3.74E-05

<3.05E Strontium-90 Ci

<1.77E-06

<1.14E-04 (li89E-06

<1.04E-05

_C.ej ium-134 Ci 1.75E-05 4.84E-05 1.08E-04 3.54EQL Cesium-137 C1 3.85E-05 2.80E-04 2.71E-04 1.15E-04 lgdine-131 Ci

<1.64E-06

<1.33E-05 2.22E-06 1.41E-Oi_

_.Q2bAlt-58 C1

<1.39E-06

<1.32E-Q5 6.58E-07

<idQI-Oh_

Cobalt-60 C1 4.95E-08 6.65E-06 6.19E-05 7.20E-0$_

__ I ron-5 9 Ci (2.91E-06

<2.63E-05 2.28E-06

< 1 11EQL, Zine-65 Ci

<3.21E-06

<2.91E-05

<2.99E-05 (1. 33EQL langantag-54 Ci

<b50E-06 2.72E-07 AdQEQf

1. A1E06_.

Chromium-51 Ci

<1.22E-05

<1.05E-04 8.30E-07

< 4. 6 8E-01.

Zirconium-Niobium-95 C1 (2.33E-06

<2.24E-05 (2.16E-05

_ <b.R4E-O L i

Jolybdenum-99 Ci (9.85E-06

< 1. 0lE04

<9.25E-05

<4.30 EQi_

Technetium-99m C1

<1.30E-06

<1.24E-05

<1.09E-05

< 5 3.QI.QL Enrium-Lanthanum-140 Ci

<5.70E-06

<4.67E-05 (4.90E-05

<1.98E-03 Cerium-141 C1 12.08E-06

<1.86E-05

<1.81E-05 (8.34E-Oh_

~

Jgthenium-103 Ci (1.73E-06

<1.35E-05 (1.36E-05

< b22E _DL Cerium-144 Ci

<9.48E-06

<8.50E-05 (7.60E-05 (3.85E-05 Iodine-133.,_

Ci

<1.30E-05

<1.37E-05

<1.61E-06 3.26E-Of_,

Jelenium-75 C1-(1.74E-06 (1.52E-05

<1.44E-05 (6 78E-OL

_g11ver-110m _

Ci (1.60E-06

<1.41E-05 (1.36E-05 (6.02E Antimony-124

, ci

<1.43E-05

<1.33E-05

<1.80E-06 (6.30E-06 1.04E-02

2. 6 7 E-OL Carbon-14 Ci 2 nn-55 Ci

<2.62E-05

<7:58E-04 1.11E-03

<1dahQL Cesium-136 Ci (1.37E-06

<1 2$E-05

<1.24E-05

<5.71E-06 Antimony-125 C1 (4.98E-06

<3.97E-05

<3.77E-05

<1.65E-05

_ Tellurium-132 C1

<1.19E-06

<1.05E-05

<9.98E-06 1.97E-07 Total for oeriod (above) Ci 5.60E-05 3.35E-04 1.20E-02 2.91E-03 A non-133 Ci

<4.59E-06

<4.72E-05 8.01E-03

1. 01E-OL Xenon-135 Ci

<1.24E-06

<1.05E-05 2.57E-07 4.74E-05 Xenon-131m Ci

<5.42E-05 (4.72E-04 4.86E-04 4.3DI-OL.

Xenon-133m C1

<1.07E-05

<9.23E-05

<8.36E-05 1.23E-04 j

Krvoton-85 Ci

<4.64E-04

<4.35E-03 4.29E-03 1.00E-02.

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ThhLL.3 ygnketAirmic_ Electric Company. Rowe

  • Maf EALhuttila Muent and Wnste Digporal Semiannual _ERDCI.I Ihird and Fourth _Quantara.1990 Solid _ Waste and Irradiated Fuel Shipments A. Solid Waste Shipped Off-Site for Burial or Disposal (Not Irradiated Fuel)

-Unit 6-Month Est. Total Period Error. %

1. Type of Waste a.

Evaporator bottoms, filter sludges, spent m3 4.25E+01 resins, etc., Class A waste.

C1 2.74E+00 13.00E+01 LSA containers. 55-gallon drums

  • b.

Dry compressible waste, contaminated m3 1.33E+02 equipment, etc., Class A waste. LSA, Ci 5.73E+00 11.00E+02 101-ft3 and $1-ft -boxes 3

2. Estimate of Major Radionuclide Composition (By Type of Waste)**

a.

Tritium 3.41E+01%

b.

Iron-55 3.67E+011 Iron-55 2.35E+01%

cesium-137 3.01E+01%

Cesium-137 2,11E+01%-

Cesium-134 2.39E+01%

cesium-134 1.60E+01%

Cobalt-60 4.15E+00%

2.75E+001 N.ighel-63 2.54E+00%

Cobalt-60 Nickel-63 1.71E+00%

Niobium-1}

1.92E+00%

Carbon-14 1.51E-01%

_...Carhnn-14 2.26E-01%

Tritium 5.00E-03%

3. Solid Waste Disposition Number of shipments Mode of Trangsprtation Destination 9

Truck Barnwell. SC

~

B. Irradiated Fuel Shipments (Disposition): None j

  • Solidification agent is cement.
    • Excluding radionuclides with half-lives less than 12.8 days. 8796R

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IJtdicActive liqui (Liffluta1J1onilcrinL.inittumeniaLion i

Reauireatnit Radioactive liquid effluent monitoring instrumentation channels are l

required to be operable in accordance with Technical Specification 3.3.3.6.

With less than the minimum number of channels operable and reasonable efforts to return the instrument (s) to opsrable status within'30 days being unsuccessful, Technical Specification 3.3.3.6.b requires an explanation for the delay in correcting the inoperability in the next Semiannual Effluent Release Esport.

Responal The steam generator blowdown flow rate measuring device became inoperable on December 6, 1990 due to a worn part that required replacement. The part was ordered, and at the end of this reporting period, it had not arrived at the plant site.

It is anticipated that the flow device will be inoperable greater than 30 days. Action Statement 17 of Technical Specification Table 3.3-8 is in effect.

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.0' MILtW15.1 EILdiCAtliVe Gateous EfilgenLligni.toring_ing11.umentation httulItment: Radioactive gaseous effluent monitoring instrumentation channels are required to be operable in accordance with Technical Specification 3.3.3.7.

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 3.3.3.7.b requires an explanation for the delay in correcting the inoperability in the next Semiannual Effluent Release Report.

hasgants:

Since the requirements of Technical Specification 3.3.3.7 governing the operability of radioactive gaseous ef fluent monitoring instrumentation were met for this reporting period, no response is required.

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l AttLNDIX.I 1

l Liguld floidup_lanka Ratquirement:

Technical Specification 3.11.1.4 limits the quantity of radioactive material contained in any outside temporary tank.

With the quantity of radioactive material in any outside temporary tank exceeding the limits of Technical Specification 3.11.1.4, a description of the events leading to this condition is required in the next Semiannual Effluent Release Report.

Eciponset The limits of Technical Specification 3.11.1.4 were not exceeded during this reporting period.

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Radiologien1. Environmental Monitoring ProgrmD J

EnguiI.ement:

The radiological environmental monitoring program is conducted in accordance with Technical Specification 3.12.1.

With milk or fresh leafy vegetation samples no longer available from one or more of the required sample locations, Technical Specification 3.12.1.c requires the identification of the new location (s) for obtaining replacement sample (s) in the next Semiannual Ef fluent Release Report and inclusion of revised Off-Site Dose Calculation Manual figure (s) and table (s) reflecting the new location (s).

Resoonant All required milk and f resh Icafy vegetation samples were available during this reporting period.

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bPPENDIX E Land _Use Census Requirement: A land use census is conducted in accordance with Technical Specification 3.12.2.

With a land use census identifying a location (s) which yields at least a 20 percent greater dose or dose commitment than the values currently being calculated in Technical Specification 4.11.2.3, Technical Specification 3.12.2.a requires the identification of the new location (s) in the next Semiannual Ef fluent Release Report.

i

Response

The land use census for this reporting period did not identify any locations yielding at least a 20 percent greater dose or dose commitment than the values currently being calculated in Technical Specification 4.11.2.3.

Recuiremsnis With a land use census identifying a location (s) which yicids a calculated dose or dose commitment (via the same exposure pathway) at least 20 percent greater than at a location from which samples are currently being obtained in accordance with Technical Specification 3.12.1. Technical Specification 3.12.2.b requires that the location (s) be added to the program if permission from the owner to collect samples can be obtained and if sufficient sample volume is available.

The identification of

~

the new location (s) is required in the next Semiannual Ef fluent Release Report.

Resoonse No changes were made in the Radiological Environmental Monitoring Program as a result of the 1990 land use census.

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AffrRDIX R Irgt.ggs Control PitEIA2 Eequirement:

Technical Specification 6.14.1 requires that a licensee initiated change (s) to the Process Control Program be submitted to the Commission in the Semiannual Radioactive Effluent Release Report for the period in which the change (s) was made.

Response

There was no licensee initiated change (s) to the Process Control Program during this reporting period.

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MJ1NMX._0 CihlittAsc..CalculatietL11anual Letuitettent :

Technical Specification 0.15.2 requires that a licensee initlated change (s) to the Off-Site Dese Calculation Manual be submitted to the Commission in the Semiannual Radioactive Effluent Release Report for the period in which the change (s) was made ef f ective.

s Lestonse There was no 11censee initiated change (s) to the Off-Site Dose Calculation Manual during this reporting period, G-1 i

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APPENDIX.11 hadicAcliy.C. Lindb._Gattaus, ansLinliLMaale Trentecnt Systema i

I Etadttatall Technical Specification t>.16.1 requires that a licensee initiated major change (s) to a radioactive waste system (s) 4 (liquid, gaseous, and solid) be reported to the Connission in the Semiannual Radioactive Effluent Release Report for the period in which the evaluation (s) was reviewed by the Plant 1

Operation Review Connittee.

i-Rtre nt.e There was no licensee initiated major change (s) to a radioactive waste system (s) (3.1guid, gaseous, and solid) during this reporting period.

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h1'E.G81E.1 Supplemental Informg11gn Ihird and rourtttquartern 1990 1.

Iechnical Specification Limita - Done and Dose Rate Technical Specification and Categaty limit a.

Noble Gatta 3.11.2.1 Total body dose rate 500 mrem /yr 3.11.2.1 Skin dose rate 3000 mrem /yr 3.11.2.2 Gamma air dose 5 mrad in a quarter 3.11.2.2 Gamma air dose 10 mrad in a year 3.11.2.2 Beta air dose 10 mrad in a quarter 3.11.2.2 Beta air dose 20 mrad in a year b.

Iodine-131. Tritium. nnd Radionuclides in Particulate Form With Half-Liveg Greater Than 8 Daya 3.11.2.1 Organ dose rate 1500 mrem /yr 3.11.2.3 Organ dose 7.5 mrem in a quarter 3.11.2.3 organ dose 15 mrem in a year C.

Liquijl1 3.11.1.2 Total body dose.

1.5 mrem in a quarter 3.11.1.2 Total body dose 3 mrem in a year 3.11.1.2 organ dose 5 mrem in a quarter 3.11.1.2 organ dose 10 mrem in a year I-1 8795R 8796R

2.

Technical Speciffention limits - Concentration Technical.Epecificatian and calzgary Limit a.

Noble.Gasea No MPC limits b.

ladine-131. Tritium. and Radionuclidta No MPC limits in Particulate Form With En1f-Lives prenter Than 8 Days C.

L1.q11[dA 3.11.1.1 Total sum of the fraction of MPC (10 CFR Part 20, Appendix B, Tables II.

Column 2), excluding noble gases less than:

1.0 3.11.1.1 Total noble gas concentration 2.00E-04 uC1/cc 3.

t11anntsments and Anproximations of Total Radioactivity a.

Noble Caama

" Continuous discharges" are determined by indirect measurement.

Primary gas samples are taken periodically and analyzed.

It is assumed that in primary to secondary leakage all gases are ejected through the air ejector.

In primary coolant charging pump leakage all gases are ejected to the primary vent stack either during flashing or liquid waste processing.

" Batch discharges" are determined by direct measurement.

Errors associated with these measurements are estimated to be 155 percent.

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Indings Iodines are continuously monitored by drawing a sample f rom the primary vent stack through a particulate filter and charcoal cartridge. The filter and charcoal cartridge are re

  • d and analyzed weekly.

The errors associated with these mt,orements are estimated to be 125 percent.

c.

Particulates The particulate filter described in (b) above is analyzed weekly.

The errors associated with the determination of particulate ef fluents are estimated to be 330 percent.

d.

Licuid Effluente

?

Liquid effluents are determined by direct measurement.

In line composite samples are analyzed for Strontium-89, Strontium-90, Iron-55, gross alpha activity, and Carbon-14.

There is no compositing of samples for tritium or dissolved fission gas analysis.

For continuous discharges composite samples are used for gamma isotopic analysis. A gamma isotopic analysis is performed on a representative sample for each batch release using the Marinelli Beaker geometry.

The errors associated with these measurements are as follows:

fission and activation products,120 percent; tritium, 110 percents dissolved fission gases,120 percent; alpha cetivity, 135 percent.

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Liguida The batch release data is presented in two categories in order to provide accurate discharge rate values.

Third Quarter Routine Batch Outdoor

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Number of batch releases:

32 4

Total time period for batch releases (minutes):

10.044 4,050 Maximum time period for a batch release (minutes):

1.708 1,340 Average time period for batch releases (minutes):

314 1.012 Minimum time period for a batch release (minutes):

25 705 Average stream flow (Sherman Dam) during period (cfm):

383 383 Average discharge rate (gpm):

22.2 5.9 Fourth Outritz Routine Batch Outdoor EgaggL Tank Maala Number of batch releases:

25 6

Total time period for batch releases (minutes):

6.919 2,527 Maximum time period f or a batch release (minutes):

1,113 765 Average time period for batch releases (minutes):

277 421 Minimum time period for a batch release (minutes):

90 230 Average stream flow (8 herman Dam) during period (cfm):

732 732 Average discharge rate (gpm):

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GAus Third Ouarter There were no batch releases during this reporting period.

Fourth Ouarter Number of batch releasect 1

Total time period for batch releases 215 minutes Maximum time period for a batch release:

215 minutes Average time period for batch releases 215 minutes Minimum time period for a batch release:

215 minutes 5.

Abnomal Releasta a.

Liquid There were no nonroutine liquid releases during the reporting period.

b.

Gana There were no nonroutine gaseous releases during the reporting period.

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