ML20203H524

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1997 Effluent & Waste Disposal Semiannual Rept for Third & Fourth Quarters
ML20203H524
Person / Time
Site: Yankee Rowe
Issue date: 12/31/1997
From: Kay J
YANKEE ATOMIC ELECTRIC CO.
To: Fairtile M
NRC (Affiliation Not Assigned), NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
BYR-98-014, BYR-98-14, NUDOCS 9803030251
Download: ML20203H524 (29)
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Text

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YANKEEATOMIC ELECTRIC COMPANY

C"Hla*8o.2"l" s,

580 Main Street, Bolton, Massachusetts 0174015J8

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Februaiy 28,1998 BYR 98-014 United States Nuclear Regulatory Commission Document Control Desk Washington, D.C. 20$55 Attention:

hir, hiorton Fairtile Senior Project hianager Non Power Reactors and Decommissioning Project Directorate Division of Operating Reactor Support

Reference:

(a) License No. DPR 3 (Docket No. 50 29)

Subject:

SEhil ANNUAL EFFLUENT REL tiASE REPORT

Dear hir. Fairtile:

Enclosed please fmd the tables that summarize the quantitles of radicactive liquid and gaseous eftluent and solid waste released from the Yankee Nuclear Power Station (YNPS) at Rowe, hiassachusetts for the third and fourth quarters of 1997. These tables are submitted in accoroance with the "(NPS Defueled Technical Specification 6.8.2.b. The summary of the estimates of offsite radiation doses resulting from plant ellluent during 1997 will be provided in a supplemental report in accordance with Control 7.2 of the Offsite Dose Calculation hianual.

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

Sincerely, Ah 'EE ATOhilC ELECTRIC COhfPANY GA James A. Kay Principal Licensing Engineer (GLg'I s

cc: hir. R. Bellamy, NRC Region I eq 0803030251 971231 PDR ADOCK 05000029 M

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EFFLUENT AND WASTE DISPOSAL SEMIANNUA!. REPORT FOR THIr4D AND FOURTH QUARTERS 1997 Yankee Atomic Electric Company Rowe, Massachusetts ne.nnuum era mm.

ERRATA The f,rst quartor gaseous roloasos reported in Tables 1 A and 10 and Append!x 1 of tho Som. annual Report covering tho first and second quarters of 1992 have boon rovised to includo a Dasoous batch dischargo of 50 pCi of Krypton 85 which was inadvertently omittod from the original report. The revised tablos and Appendix are provided in Appendix K to this report.

a monmwi ern

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NOTES:

1.

Yankoo Nuclear Power Station's last day at any power lovel was October 1,1991. The f acility is permanontly shut down for futuro decommissioning. Due to ceased operailons, short lived nuclidos have boon doloted from the gaseous and liquid offluent tables. Their

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  • activity concentrations in tho fuel inventory have decayed to zero values.

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LIST OF TABLES AND APPENDICES I!1In Page TABLE 1 A Gasoous Effluents Summation of All Roloasos.................

1 TABLE 10 Gasoous Ef fluents Elevated Roloasos........................

2 TABLE 10 Gaseous Ellluonts Ground Levol Rolocsos....................

3 TABLE 2A Liquid Effluents Summation of All Roloasos....................

4 TABLE 2B Liquid Effluents Routino Roloasos...........................

5 TABLE 3 Solid Wasto and Irradiated Fuel Shipmonts.....................

6 APPENDIX A Radioactivo Liquid Elfluent Monitoring Instrumentation........... A 1 APPENDlX B Radioactivo Gasoous Etfluent Monitoring Instrumentation.......... B 1 APPENDIX C Liquid Holdup Tanks....................................... C 1 APPENDIX D Radiological Environmental Monitoring Program................. D 1 APPENDIX E La nd U so C o n s u s......................................... E 1 APPENDIX F Process Control Program (PCP).............................. F 1 APPENDIX G Off.Sito Doso Calculation Manual (ODCM)..................... G1 APPENDIX H Radioactivo Liquid, Gasoous, and Solid Wasto Trea'mont Sys t e m s................................................. H 1 APPENDIX l Supplomontal lnformation..................................

1 1 APPENDIX J Sowago Sludge Disposal.

..................................J1 APPENDIX K Errata Pagos for the 1992 First and Second Quarter Effluent And Wasto Disposal Report................................. K 1 nurnowa m Iv-mw

e T ABLE 1 A Yankee Atomic Electric Comoanv. R0wo. Massachus0tts Effluent and Wasto Diso0 sal Semiannual Reoort Third and Fourth Ouarters 1997 Gaseous Effluents - Summation of Al! Releases

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o Unit Quarter 3 Oua:1er 4

,o A. Fission and Activation Gases

1. Total Release Ci 0 00e+00 0 00e+ 00 s2 50e+01
2. Average Release Rate for Penod pCl/sec 000e+00 0 00e+00 1
3. Percent of Control Limit

0 00e+00 0 00e+00 D. lodines"d C. Parilculates 1 Particulates with half-lives > 8 days Cl 9 82o.08 2 50e 08

  • 3 00e+01
2. Avera je release rate for period pCi/sec 124e-08 318e-09

% Percent of Control Limit'0 8 00e-03 5 33e-03

4. Gross Alpha Radioactivity Ci

<318e 08

<3 57e-08 D. Tritlum

1. Total Release C6 7.69e C2 6 06e 02

$3 00e+01

2. Average Release Rate for Period pCl/sec 9 780 03 7.71e-03
3. Percent of Control Limit'd'
  • /o NA NA (a) ODCM Control 3.4.a for gamma air dose. Percent values for ODCM Control 3.4.b for beta air dose would be approximately the same.

(b) lodine data have been deleted. These nuclides are no longer available for discharge.

(c) Per ODCM Control 3.5, th3 percentage of the limit is based on the combined dose coritt.bation from iodines, tritium, and particulates with half lives greater than 8 days. Percentage of limits are calculated using ODCM Method I doJe equations.

(d) Per ODCM Control 3.5, percentage dose contribution from tritium is included in Part C.3.

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- TABLE 1B Yankee Atomic Electric Comoanv. Rowe. Massachusetts FA'uent and Waste Discosal Semlannual Reoort 7Altd and Fourth Querters 1997 fagueoen Effluants - Elevated Releases t

Continuous Mode Batch Mode'*

Nuclides Released Unit Quarter 3 Ouarter 4 Ouarter 3 -

Quarter 4 l r

1. Fission Gases

_,, y/on A5 Cl 0.00e+00 0.00e+00 I

}otal for Pr_77 _,

Cl 0.00e+00 0.00e+00

2. lodines*)
3. Particulates S'rontium 89 Ci

<B.40e-07

<4.74e 07 b

Strontium-90 Ci

<5.30e-07

<2.22e-07 Cesium-134 Ci

<2.67e 07

<2.55e-07 Cosie:n-137 Cl 1.61e.08

<2 72e-07 Ziry -65 Ci

<7.44e-07

<6.40e-07

'4balt 58 Ci

<2.81 e-07

<?A2e-07 Cobalt-n Cl 8.21e 08

<4.78v.07 Zirconium-Niobium-95 Ci

<4.79e-07

<3.75e-07 i

Cerium-144 Ci

< 1.M e-06

<8.06e-07 Antimony 124 Ci

<8.67e-07

<6.66e-07 Manganese-54 Ci

<2.02e ^4),,

<2.25e-07 Sliver-110m Ci

<4.26e-07

<3.41 e-07 j

Total for Period Ci 9.82e-08

<4.98e-06 (a) There are no longer any batch mode gaseous releases.

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(b) lodine-131, led;ne-133, and adine-135 activities have been deleted. These nuclides are no longer available for discharge.--

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TABLE 1C

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Yankee Atomic Electric Como.xahe. Massachusetts Effluent and Waste Disoosal Semiannual Reoort Third and Fourth Quarters 1997 Gasoous Effluents Ground Level R0leasec Cont;nuous Mode Batch Mode

Nuclides Released Unit Quarter 3 Ouarter 45 Quarter 3 Quarter 4

1. Fission Gases Krypton 85 Ci 0.00e+00 0.00e+00 Total for Period Ci 0.00e+00 0.00e+00

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2. lodines*
3. Particulates Strontium-89 Ci 0.00e+00

<1.23e 07 Strontium-90 Ci 0.00e+00

<4.52e-08 s

Cesiuni 134 Ci 0.00% 00

<1.25e-08 Cesium-137 Cl 0.00a+00 4 59e-09 F

Zinc 6 5 Ci 0.00e+00

<2.76e-08 Coba;t 58 Ci 0.00e+00

< 1.23e-08 Cobatt 60 Ci 0.00e+00 2.04e-n8 Zirconium-Niobium-95 Ci 0.00e+00 s2.26e 08 Cerium-144 Ci 0.00e+00

<4 37e 08 Antimony-124 Ci 0.00e+00

<3.42e-08 Manganese 54 Ci 000e+00

< 1.35e-08 Sliver 110m Ci 0.00e+00

<2.15e 08 Total for P3riod Ci 0.00e+00 2.50e-08 (a) There are no longer any batch mode gaseous releases.

(b) The gitund level selease of activity for the fe'h. Quarter occurred during scabbling of outbuildings and moat wall and floors. The HEPA filter units used for these work sites met hil the specifications and monitoring requirements stated in the Final Safety Analysis Report. The small dose contribution from this source hao an insignificant impact on the total dose value associated with gaseous elevated releases.

(c) 'odine-131, lodine-133, and lodine 135 activities have beer. deleted. These nuclides are no !onger available for discharge, m am m erronT,.:. men,.

1

4 TABLE 2A Ygnhoe. Atomic Electric Comoanv. Rowe. Massachusetts Effluent and Waste Discosal Semiannual Report Third and Fourth Quarters 1997 Liau:d Effluents - Summation of All Releases Est;9 o

Unit Quartes 3 Quarter 4 A. Fiss'on and A"tivation Products

1. Total Release (not including tritium, gases, a!pha)

Cl 1.300-06

< B.11 e-05

  • 2 00e4 01
2. Average Diluted Concentration During Period pCi/mi 1.67e 11

< 1.130-09

3. Percent of Applicable limit

6 93e 15 0 00e+00 B. Teltlum

1. Total Release Ci 7.270-O'1 3 85e-03
  • 1.00e +01
2. Average Diluted Concentration During Period pCihnl 9.33e-08 5.35e-08
3. Percent of Applicable Limit'*>

3.11 e-03 1.78e-03 J

C. DistrAved and Entra'. led Gases

1. Total Release Ci

<9 39e-05

< 1.73e-04 e2.00e+01

2. Average Diluted C(ncentration During Period pCi/mi

<1 28e-09

<2 41e-09

3. Percent of Applicaule Limit
  • 0.00e <00 0.00e+00 D. Gross Alpha Radio.letivity
1. Total Release Ci

<4.26e-02

<6.410-02

  • 3.50e+01 E Volume of Waste Release (prior to dilution) liters 9,26e+04 1.15e+05
  • 2.50e+01 F. Volume of Dilution Water Used During Period liters 7.79e+07 7.19e+07 21.50e+01 (a) Co.. centration limits specified in 10CFR20, Appendix B, Tat le 11, Column 2 (ODCM Control 2.1). The pe cent of applicable limit repc-ted is based on the averags diluted concent.ation during (ne period. At no time did any release exceed the concentration limit.

(b) Concentretion limits for dissolved and entrained noble gases is 2.00E-0/. pCi/ml (ODCM Ovntrol 2.1). Th i percent of applicable 'imit reported is based on the average dilutad concentration during the period. At no time did any telease exceed the concentration limit.

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TABLE 2B y.gnkOo Atomic EIOctrlg_Comoanv. Rowe. Massachusetts EffluOnt and Waste Discosal Semiannual Reoort Third and Foyrth Quarters 1997 Liauld Effluents - R0utine Releases Continuous Modo Batch Mode Nuclidos Released Uni 1 Ouader 3 L uarter 4 Ouarter 3 Quarter 4 Strontium-89 Ci 0.00e+00 0.00e+00

<3 83e 06

<4 72e-06 Stiontiuti Ci 0.00e<. 00 0.00e+00 g.34e-06

<2.89e 06 Cos!um 134 Ci 0.00e+00 0 00e+00

<3 59e 07

<7.12e-07 Cesium 137 Cl l

0.00e+00 0.00e+00 6 41e-07

<7.990-07 L

Coba%58 Ci 0.00e+00 0.00e+00

<3 83e-07

<6.19e-07 Cobalt 60 Ci 0.00e+00 0.00e+00 6.60e-07

<108e 06 I.

Iron-59 Ci 000e+00 0.00e+00

<8 91e-07

< 1.41 e-06 h

Zinc 65 Ci 0.00e+00 0.00e+00

<1.17e 06

< 1.96e-06

_ Manganese-54,.

Ci 000e+00 0.00e +00

<3 55e-07

<612e-07 Zirconium N obium-95 Ci 0.00e+00 0.00e+00

<6.23e-07

<1.06e-06 Cariurr-144 Cl 0.00e+00 0.00e+00

<2.06e-06

<3.42e-06 Silver 110m Ci 0.00e+00 0.00e+00

<5.900-07

<9.78e-07 Antimony 124 Ci 000e+00 0.00e+00

<1.23e-06

<7.21e 07 Carbon-14 Ci 0.00e+00 0.00e+00

<6.43e-06

<5.58e-06 Iron-55 Ci 0.00e+00 0.00e+00

<2.10e-05

<5 31e-05 Antimony.125 Ci 0.00e+00 0.00e+00

<9.440 07

< 1.40e-06 i

Unidentified Ci 000e+00 0.00e+00 0.000+00 0.00e+00 Total for Period (above)

Ci 0.00e+00 0.00e+00 1.30e-06

< 8.11 e-05 Krmton-85 Ci 0.00e+00 0.00e+00

<9.99e 05

<1.73e-04 nunmanur es afam

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. TABLE 3 (Sheet 1 of 2)

Yankee Atomic Electric Comoanv. Rowe. Massachusetts Effluent and Waste Disposal Semiannual Reoort Third and Fourth Quarters 1997 Solid Waste and Irradiated Fuel Shloments A. SOLID WAS TE SHIPPED OFFSITE I-OA P,URIAL OR DISPOSAL (not Irradiated fuel)

1. Type of Waste Unit 6 mgnth Est. Total Penod Error. %

a.

Dry Active Waste: Class A Conteiners m'

1.07e+01 t2*50e+01 steel liner (201 ft',177.5 ft', 7.5 ft

Ci (Eat.)

7.94e-01

+

b.

Resins. Filters, Evap Bottoms; Class A Containers m'

2.50e+00 t2 50e+01 steel drum (7.5 ft')

CI (Est.)

5.24e ' 2 c,

Dry Active Waste: Class A Containers m'

4.38e+02 22'50e+01 steel box (101 ft')

C1 (Est.)

3.70e-01 3

e2.50e+01 d.

Dry Active Waste: Class A Containers (b)

Ci st.)

95e 0

2. Estimate of Major Nuclide Composition (by type of wante) >1%

a.

Iron-55 6.50e+01 Cobalt 60 2.26e+01 Nickel-63 1.06e+01 b.

Cesium 137 3.19e+01 Cobalt 60 2.80e+01 Nickel 63 2.65e+01 fron-55 1.17e+01 c.

Iron 55 4.47e+ 31 Cobalt-60 2.71 e+01_

Nickel-63 2 47e+01 Cesium 137 3A9e+00

- d.

Iron-55 6.34e+01 Cobalt-60 1.99e+01 Nickel %

1.50e+01 neemarrtut.sve - zw.

TABLE 3 (Sheet 2 of 2)

Yankee Atomk Electric Comoany. Rowe. Massachusetts Effluent and Waste Disoosal Semlannual Reoort Third and Fourth Quarters 1997 Solid Waste and Irradiated Fuel Shlomen'.s

3. Solid Waste Disposition Number of Shioments Mode of Transoortation Destination 3

truck Bamwoll, SC 17(b) truck Barnwell, SC 38 truck So. Clive UT 9(a) truck Oak Ririge, TN 3(a) truck Memphis, TN 1(6 truck Bamwell, SC B. IPRADIATED FUEL SH'PMENTS (Disposithn)* None (a) Waste shipments to processors (b) Partial shipments by the processor to disposal JP8MYREFFLNT.978 "7"

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APPENDIX A Radioactive Liagid Effluent Monitorina Instrumentation Reauirement:

Radioactive liquid effluent monitoring instrumer.tation char nels are required to be operable in accordance with ODCM Control 5.1, With less than the minimum number of channels operable and reasonable efforts to i sturn the instrument (s) to operable status within 30 days being unsuccessful, ODCM Control 5.1 requires cri explanation for the delay in correcting the inoperability in the next Effluent and Waste Disposal Semiannual Report.

Resoonse:

As part of the plant's dismantlemant and decommissioning process, the Turbine Building Sump composite sampler, located on the 002 discharge pathway, was permanently removed from service on June 2,1997. On that date, the service water pumpa were permanently secured from service, resulting in the cessation of water flow via the 092 pathway. Chemistry confirmet' by bspection that flow via the 002 out,' lou pipe had been terminated. Additionally, auxiliary be!!er and air conditioning equipment that also had drains associated with the 002 discharge have been similarly removed from service. All remaining drains in the Turbine Building have been plugged to assure that no inadvertent releases occur via the 002 pathway.

ODCM Tables 2.1 and 5.1 state the analysis and compositing sample requirements for plant effluent surveillances. These requirements are necessary only when releases are occurring via the appropriate effluent release pointa. Therefore, with the securing of the 002 patt.way, no continued operation of the Turbine Building Sump composite sampler is required.

Reference to the Turbine Building Sump composite sampler will be deleted from ODCM Control 5.1.

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APPENDIX B l

_ Radioactive Gaseous Effluent Monitorina instrumentati?D t

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_ Reauirement:

Radioactive gaseous effluent monitoring instrumentation channels era required to be operable in accordance with ODCM Control 5.2, 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, ODCM Control 5.2 requires an explanation for the delay in correcting the inoperability in the next Effluent and Waste Disposal Semlannual Report.

I Resoonse:

The requirements of ODCM Control 5.2 governing the operability of radioactive gaseous effluent monitoring instrumentation were met for this reporting period.

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f APPENDIX C t

Llauld Holduo Tanks Reauirement:

Defueled Technical Specification 3.4 limits the quantity of radioactive material -

contained in any outside temporary tank. With the quantity of radioactive materialin any outs!de temporary tank exceeding the limits of Technical 4

Specification 3.4, a description of the events leadhg to this condition is required in the next Effluent and Waste Disposal Semlannual Report.

Resoonse:

The limits of Technical Specification 3.4 were not exceeded during this

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reporting period.

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i APPENDIX D l

Radioloalcal Environmental Monitorina Proaram i

Reauirement:

The Radiological Environmental Monitoring Program is conducted in accordance with ODCM Control 4.1. With milk or fresh leafy vegetat;on samples no longer available from one or more of the required sample locations, ODCM Control 4,1 requires the identification of the new location (s)

L for obtair: w. rer!scement sample (s) in the next Effluent and Waste Disposal Semlannual Recm; and inclusion of revised Off Site Dose Calculation Manual l

figure (s) and L.cle(s) reflecting the new location (s),

i Resoonse:

All required milk or fresh leafy vegetation samples were available during this reporting period.

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APPENDIX E I

Land Use Census i-Reaulrement:

A land use census 13 conducted in accordance with ODCM Control 4.2. With a land use census identifying a location (s) which yields at least a 20 percent j

greater dose or dose commitment than the values currently being c.alculated l

In ODCM Control 3.5, ODCM Control 4.2 requires the identification cf the new location (s) in the next Effluent and Waste Disposal Semlannual Report.

j Resoonse:

The land use census for this reporting period did not identify any locations yielding at least 20 percent greater dose er dose commitment than the values j

currently being calculated in ODCM Control 3.5.

Reoulroment:

W;th a land use census identifying a Iccation(s) which yields :2 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 ODCM Control 4.1, ODCM Control 4.2 requires that the new location (s) be added to the Radiological Environmental

Monitoring Program if permission from the owner to collect samples can be obtained and sufficient sample volume is available. The identification of the new location (s) is requireo.n the next Effluent and Wasto Disposal 1

Semiannual Report.-

Resoonse:

No new locations were added to the Raoiological Environmental Monitoring Program as a result of the 1997 land use census.

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APPENDIX F Process Control Procram (PCP)

Reauirement:

PCP Control 2.0 requires that licansee initiated changes to the PCP be

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submitted to the Commission in the Effluent and Warte Disposal Semiannual Report for the period in which the change (s) was made.

Resporna:

There were no licensee initiated changes to the PCP during this reporting period.

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APPENDIX G Off Site Dose Calculation Manual (ODCM) 9eauirement:

ODCM Control 7.2 requires that licensee-initiated changes to the ODCM b3 submitted to the Commission in the Effluent and Waste Disposal Semiannual Report for the period in which the change (s) was made effective.

Resoonse:

There were no licensue-initiated changes to the ODCM during this reporting period.

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i APPENDIX H Radioactivo Liouid. Gaseous. and Solid Wasto Treatment Svstems Roauirement:

ODCM Control 7,3 requiros that licensoo-initit.ted major changes to the radioactive wasto systems (liquid, gaseous, and solid) bo reported to the Commission in the Effluent and Wasto Disposal Somlannual Roport for the period in which the ovaluation was reviewad by the Plant Operation Review Committoo.

Resoonso:

Thoro woro no major changes to the radwasto treatmont systorns during this reporting period.

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APPENDIX l Sucolemental Information Third and Fourth Quarters 1997 l

1.

Control Limits - Dose and Dose Ratg Control and Cateoorv Lim!1 a.

Noble Gases i

Control 3.3, Total body dose rate 500 mrem / year Control 3.3, Skin dose rate 3000 mrem / year 4

Control 3.4, Gamma air dose 5 mrad / quarter Control 3.4, Gamma air dose.

10 mrad / year i

Control 3.4, Beta air dose 10 mrad / quarter Control 3.4, Deta air dose 20 mradlyear b.

lodine-131. Tritium. and Radionuclides in Particulate Form With Half-Lives Greater Than 8 Davs Control 3.3, Organ dose rate 1500 mrom/ year Control 3.5, Organ dose 7.5 mrem / quarter l

Control 3.5, Organ dose 15 mrem / year c.

Liquids Control 3.1, Total body dose 1.5 mrem / quarter j

Control 3.1, Total body dose 3 mrem / year Contiol 3.1, Organ dose '

5 rr?;m/ quarter Control 3.1, Organ dose 10 mrem / year i

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Qpntrollimits Concentration Control and Cateaorv 1,1rn!!

a.

Uquids Control 2.1, Total sum of the fraction of MPC (10CFR20, 1.0 Appendix E, Table ll, Column 2), excluding noble gases less than' Control 2.1, Total noble gas concentration 2.00E-04 pCi/cc 3.

Measurements and Acoroximations of Total Radioactivity a.

bl ale Oases. Krvoton-85 Conmuous discharges are determined by direct measurements. A primary vent stack gas sample is taken monthly and analyzed for Krypton-85. A review of the weekly primary vent stack noble gas integrator readings for any increase in values above the backgre,e-d level also is used as a reference. There are no longer any batch discharges. Errors associated with the above measurements are estimated to be 125 percent.

b, lodines. Particulateg There are no longer any iodine isotopes available for discharge. The sampling system design requires the use of a charcoal cartridge as a support for the particulate filter during particulate collection. The sampling system continuously draws a t, ample from the primary vent stack through a filter and charcoal cartridge. The particulate filter is removed and analyzed weekly. The errors associated with the determination of particulate effluents are estimated to t'e 230 percent.

c.

Llauld Effluents A gamma isotopic analysis is performed on a representative sample using a Marinelli Beaker geometry for both a batch or continuous discharge. Composite samples for batch and continuous discharges are analyzed for strontium-89, strontium-90, iron-55, gross alp' a activity, and carbon-14.

Tritium analysis is perfcrmed on composite samp[es for continuous discharges and on each batch discharge. The errors associated witn these measurements are as follows: fission and activation products,120 percent; tritium, 10 percent; dissolved fission gases. *20 percent; and alpha activity,135 percent.

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Batch Releases-4 a.

Liqulda The batch release data is pf asented in two categories to provide accurate average discharge rate values.

Batch Releases Outdoor Tank Third Quarter Routine Moats Number of batch releases:

1 5

Total time period for batch releases (minutes):

1320 4305 Maximum time period for a batch release (minutes):

1320 1815 Average time period for batch releases (minutes):

1320 861 l

Minimum time period for a batch release (minutes):

1320 400 Average stream flow (Sherman Dam) during period (cfs):

255 255 Average discharge rate (gpm):

6.1 3.8 Fourth Quarter Namber of batch releases:

2

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Total time period for batch releases (minutes):

2,160 6,402 Maximum time period for a batch release (minutes):

1,255 1,480 Average time period for batch releases (minutes):

1,080 914 Minimurn +1me period for a batch release (minutes):

905 320 Average stream flow (Shennan Dam) during period (cfs)*

462 462 Average discliarge rate (gpm):

6.2 2.9 b.

Gases There are no longer any gaseous batch discharges.

5.

Abnormal Releases-T ODCM Control 7.2 requires the reporting of any unplanned releases from the site to the site boundary of rad' active materialin gaseous and liquid effluents made during the reporting period.

a.

Liauld There were no nonroutine liquid releases c,uring the reporting penod.

b.

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

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APPEND!X J Sewaae Sludae Discosal Reauirement:

For periods in which disposal of septage occurs, the licensee shall report in the Effluent and Waste Disposal Semiannual Report, the volume discharged, liquid and solid fractio.1s, and total activity discharged.

Resoonse:

1 he following information is provided for the disposal of sewage sludge during the reporting period:

Volume Discharged (gallons):

9.50e+03 Liquid Fraction (by weight) of Wacte:

7.91 e-01 Solid Fraction (by weight) of Waste:

2.090-01 Nuclide Content in Liquid Fraction (pCl/g): N D'*)

Nuclide Content ir. Solid Fraction (pCl/g wet):

Cesium-137

= 1.61e-07 Cobalt-60

= 6.70e-07 Total Activity Discharged (pCl):

Cesium 137

= 1.21e+00 Cobalt-60

=5.03e+00 TOTAL 6.24e+00 (a)

ND = Not Detectable J-1 uw.

mammurun era

APPENDIX K Errata Paaes for the 1992 First and Second Ouarter Effluent and Waste Discosal Report Attached are revisions to the following pages to the Semiannual Report covering the first and second quar 1ers c' 1992:

Page 1 (Table 1 A) a Page 2 (Table 1B)

+

Page 1-2 (page 2 of Appendix I)

Page 1-4 (page 4 cf Appendix l}

9 I

mamma;were K-1 mm.

b

TABLE 1A ERRATA Yankee. AtJmic Electric Company. Rowe Massachusetts Effluent and Waste Disposal Semiannual Report First and Second Ouarters 1992 Caseous Effluents Summation of All Releases Est. Total Unit Quarter 1 Quarter 2 Error %

A.

Fission and Activation Gases 1.

tal Release Cl 5.00E-05 0.00E+00 12.50E+01 2.

Ac. rage Release Rate for Period uC1/sec 6.36E 06 0.00E+0v 3.

Percent of Technical Specification 7.41E-07 0.00E+00 Limit u t

B..

lodines 1.

Total Iodine 131 Ci

<8.70E 07 s7.62E 07 12.50E+01 2.

Average Release Rate for Period uCi/sec

<1.11E 07 (9.69E 08 3.

Percent of Technical fpecification 1.11E 01 8.27E 02 Limit (2)

C.

Particulates 1.

Particulates with T-1/2 > 8 days C1 4.29E-06 1.86E 06 13.00E+01 2.

Average Release Rate for Period uC1/sec 5.46E-07 2.34E 07 (3)

(3) 3.

Percent of Technical Specification Limit 4.

Gross Alpha Ra6 Mctivity Ci

<5.37E-08

'4.69E 08 0.

Yritium 1.

Total Reicase Ci 1.16E+00' 8.59E 01 13.00E+01 t"

2.

Average Release Rate for Period uCt/sec 1.48E 01 1.09E 01 Perc' nt of Technical Spect'* cation 3.

e

'33 (33 Limit u)

Based on beta-air dose which was the most limiting of either the gamma air or beta-air dose requirements.

(2)

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

(33 Per Technical Specification 3.11.2.3. dose contribution from tritium and particulates are included with 1.31 above in Part B.

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e TABLE 18 ERRATA Yankee Atomic flectric Company. Rowe, Massachusetts Effluent and Waste Disposa' Semiannual ReDort First and Second Og.rters 1992 Gaseous Efflue'i}

El lated Releases Continuous Mode Batch Mode

  • Nuclides Released Unit Quarter 1 Quarter 2 Ouarter 1 Quarter 2 1.

Fission Gases l

Krypton 85 Ci 0.00E+00 0.00E+00 5.00E-05 Xenon 133 Ci 0.00E+00 0.00E+00 0.00E+00 Xenon 131m Ci 0.00E+00 0.00E+00 0.00E+00 Tota'.or Period Ci 0.00E+00 0.00E+00 5.A0E-05 l

2.

Todines Iodine 131 Ci

<8.70E 07

<7.62E 07 0.00E+00 Total for Period Ci

<8.70E 07

<7.62E 07 0.00E+00 3.

Particulates Strontium 89 Ci

<1.*E -S.

<6.85E 06 0.00E+00 Strontium 90 Ci

<3.;90 07

<2.33E-07 0.00E+00 Cesium 134 Ci

<3.900 'J7

<3.21E 3/

0.00E+00 Cesium 137 Ci 3.18E 08 1.04E 07 0.00E+00 Barium Lanthanum 140 Ci

<1.27E 66

<1.05E 06 0.00E+00 Zinc 65 Ci

<9.61E-07

<7.67E-07 0.00E+00 Cobalt 58 Ci

<4.26E 07

<3.55E-07 0.00E+00 Cobalt 60 C1 4.26E 06 1.76E-06 0.00E+00 Iron-59 Ci

<9.09E 07

<7.36E-07 0.00E+00 Chromium-51 C i'

<2.63E 06

<2.11E-06 0.00E+00 Zirennium Niobium-95 Ci

<7.36E 07

<6.15E-07 0.00E+00 Cerium 141 Ci

<3.33E 07

<2.68E 07 0.00E+00 Cerium 144 Ci

<1.41E 06

<1.13E 06 0.00E+00 Antimony 124 Ci

<3.81E-07

<3.21E-07 0.00E+00 Manganese 54 Ci

<4.48E-07

<3.68E-07 0.00E400 Silver 110m Ci

<3.91E-07

<3.0BE-07 0.00E+00 There were no batch mode gaseous releases during the second quarter.

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'2-

ERRATA YAEC 1st/2nd Otr. 1992 Report Technical Specification and Cateoory lim'i t c.

Liouids 3.11.1.1 Total sum of the fraction of HPC (10CFR20. Appendix B, Table II, Column 2), excluding noble gases less than:

1.0 I

3.11.1.1 Total noble gas concentration 2.00E 04 pCi/cc 3.

Measurements and Anoroximations of Total Radioactivity a.

poble Gases Continuous discharges are determined by taking a grab sample from the primary vent stack using a Marinelli gas sample container.

Errors associated with this measurement.are estimated to be 125 percent.

Routine plant batch discharges do not occur because all the l

gaseous systems are vented, and the production of fission gases has ceased with the permanent shutdown of the facility.

The only source for noble gases is within the cladding of the spent fuel stored in the Spent Fuel Pool. There was one batch gaseous discharge 1 associated with testing area monitors located in the Spent Fuel Pit and the Primary Auxiliary Building.

b.

Iodines lodines are continuously monitored by drawing a sample from the primary vent stack through a particulate filter.and charcoal cartridge..The filter and charcoal cartridge are removed and analyzed-weekly. The errors associated with these measurements are estimated to be 25-percent.

c.

Particulates The par'.iculate filter described in (b) above is analyzed weekly.

The errors associated with the determination of particulate effluents are estimated to be 130 percent.

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9et-V Tv E

ERRATA YAEC 1st/2nd Otr. 1992 Report Outdoor Routine Tank Second Quarter Batches Moats Number of batch releases:

34 4

Total time period for batch releases (minutes):

9957 8160 Maximum time period for a batch release (minutes):

780 2820 Average time period for batch releases (minutes):

293 2115 Minimum time period for a batch release (minutes):

210 1835 Average stream flow (Sherman Dam) during period (cfs):

468 468 Average discharge rate (gpm):

25 4.4 b.

Gases First Quarter Number of batch releases:

1 Total time period for batch releases:

25 minutes Maximum time period vor batch releases:

25 minutes Average time period for batch release:

25 minutes Minimum time period for batch release:

25 minutes Second Quarter There were no batch releases during this period.

5.

Abnormal Releases Technical Specification 6.9.5.b requires the reporting of any unplanned releases from the site to the site boundary of radioactive material in gaseous and liquid effluents made during the reporting period, a.

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

b.

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

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