ML20238F569

Effluent & Waste Disposal Semiannual Rept for First & Second Quarters 1998

ML20238F569
Person / Time
Site:	Yankee Rowe
Issue date:	06/30/1998
From:	Kay J YANKEE ATOMIC ELECTRIC CO.
To:	Fairtile M NRC, NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
BYR-98-054, BYR-98-54, NUDOCS 9809040060
Download: ML20238F569 (22)

Text

{{#Wiki_filter:- - - _ _ i ~ 5'ANKEE ATOMIC ELECTRIC COMPANY 'C"*[o".g]o"*;*g'" ~ 590 Main Street, Bolton, Massachusetts 01740-1398 y August 27,1998 BYR 98-054 United States Nuclear Regulatory Conunission Document Control Desk Washington, D.C. 20555 Attention: Mr. Morton Fairtile Senior Project Manager Non-Power Reactors and Decommissioning Project Directorate Division of Operating Reactor Support

Reference:

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

Subject:

SEMI-ANNUAL EFFLUENT RELEASE REPORT

Dear Mr. Fairtile:

Enclosed please find the tables that summarize the quantities of radioactive liquid and gaseous effluent and solid waste released from the Yankee Nuclear Power Station (YNPS) at Rowe, Massachusetts for the first and second quarters of 1998. These tables are submitted in accordance with the YNPS Defueled Technical Specification 6.8.2.b. We trust that this information is satisfactory; however, should you have any questions, please contact us. 1 Sincerely, I YANKEE ATOMIC ELECTRIC COMPANY g pJames A. Kay O Principal Licensing Engineer cc: J. White, NRC Region I l 9 9809040060 980630 ) PDR ADOCK 05000029 R PDR

k I l EFFLUENTAND WASTE DISPOSAL 4 SEMIANNUAL REPORT FOR FIRST AND SECOND QUARTERS 1998 Yankee Atomic Electric Company Rowe, Massachusetts nwonemmEFFLNT.98A Br2648

b - NOIES: 4 1. Yankee Nuclear Power Station's last day at any power level was October 1,1991. The facility is permanently shut down and in the process of decommissioning. Due to ceased operations, short-lived nuclides have been deleted from the gaseous and liquid effluent tables. Their activity concentrations in the fuel inventory have decayed to zero values. i i I a 1 i -ll-R WEGPDHWREFFLNT.98A i a

l LISTOFTARI FA AND APPENDICES Iltla Eage TABLE 1 A Gaseous Effluents - Summation of All Releases.................... 1 TABLE 1B Gaseous Effluents - Elevated Releases........................... 2 TABLE 1C Gaseous Effluents - Ground Level Releases....................... 3 TABLE 2A Uquid Effluents - Summation of All Releases...................... 4 TABLE 2B Uquid Effluents - Routine Releases......................,....... 5 TABLE 3 Solid Waste and irradiated Fuel Shipments......................... 6 APPENDIX A Radioactive Uquid Effluent Monitoring instrumentation............... A-1 APPENDIX B Radioactive Gaseous Effluent Monitoring Instrumentation............ B-1 APPENDIX C. Uq uid Holdup Tanks.......................................... C-1 APPENDIX D Radiological Environmental Monitoring Program................... D-1 APPENDIX E Land Use Census............................................ E-1 APPEND!X F Process Control Program (PCP)................,............... F-1 APPENDIX G Off-Site Dose Calculation Manual (ODCM)........................ G 1 APPENDIX H Radioactive Uquid, Gaseous, and Solid Waste Treatment Sys tem s.................................................. H-1 ) ' APPENDIX l Supplemental information..................................... 1-1 l i I l l l anumamvam -iii-l m l i

l TABLE 1 A Yankee Atomic Electric Comoanv. Rowe. Maccachusetts Effluent and Wanta Disonnat Semlannual Reoort l First and Second Quarters 1998 Anceous Effluents - Summation of All Relaanes E' tal Unit Quarter 1 Quarter 2 Eo a 1 A. Fission and Activation Gases l

1. TotalRelease Ci ND ND t2.50e+01

2. Average Release Rete for Period pCl/sec ND ND

3. Percent of ControlLimit" 0.00e+00 0.00e+00 B. lodinesM C. Particulate

1. Particulate with half-lives > 8 days Cl 1.76e-07 1.330-07 t3.00e+01

2. Aversos release rate for period pCi/see 2.24e-08 1.69e-08 i

3. Percent of Control Limit" 5.33e-03 6.67e-03

4. Gross Alpha Radioactivity Cl ND 5.96e-09 D. Tritium

1. TotalRelease Cl 6.46e-02 6.39e-02 t3.00e+01

2. Average Release Rate for Period pCi/sec 8.22e-03 8.13e-03

3. Percent of ControlLirnit (d)

(d) 4 ND - Not detected in gaseous effluents. (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, the percentage of the limt is based on the combined dose contribution from iodines, tritium, and particulate wth half lives greater than 8 days. Percentage of limits cre calculated using ODCM Method I dose equations. (d) Per ODCM Control 3.5, percentage dose contribution from tritium is included in Part C.3. runtoRBSYREFR A r.98A

• i" BWM

s TABLE 1B Yankee Atomic Electric Comoany. Rowe. Maccachusetts Effluent and Wanta Disonnal Samlannunt Reoort First and Second Quarters 1998 nacaous Effluents - Elevated Re!nn=es Continuous Mode Batch Mode

• Nuclides Released Unit Quarter 1 Quarter 2 Quarter 1 Quarter 2

1. Fission Gases Krypton-85 Cl ND ND Total for Period Cl ND ND

2. lodines"

3. Particulate Strontium-89 Ci ND ND Strcntium-90 Cl ND ND Cesium-134 Cl ND ND Cesium-137 Cl ND ND Zine-65 Cl ND ND Cobalt-58 Cl ND ND Cobalt-60 Ci 5.08e-08 4.25e-08 Cerium-144 Ci ND ND Manganese-54 Cl ND ND Total for Period Ci 5.08e-08 4.25e-08 i

ND - Not detected in gaseous effluents. (a) There are no longer any batch mode gaseous releases. (b) lodine-131, lodine-133, and lodine-135 actMties have been deleted. These nuclides are no longer available for discharge. . nwoomemvmtrrunsaA 2-ermos

TABLE 1C Yankee Atomic Electric Corneany. Rowe. Massachusetts Effluent and Waste Disoosal Semiannual Reoort First and Second Quarters 1998 Gaseous Effluents - Ground Level Releases (*) Continuous Mode Batch Mode # Nuclides Released Unit Quarter 1 Quarter 2 Quarter 1 Quarter 2

1. Fission Gases Krypton-85 Cl ND ND Totalfor Period Cl ND ND

2. lodines"

3. Particulate Strontium-89 Cl ND ND Strontium-90 Cl ND ND Cesium-134 Ci ND ND Cesium-137 Cl 2.44e-08 ND Zinc-65 Cl ND ND Cobalt 58 Cl ND ND Cobsit-60 Cl 1.01e-07 9.05e-08 Cerium-144 Ci ND ND Manganese-54 Ci ND ND Totalfor Period l

Cl 1.25e-07 9.05e-08 4 ND Not detected in gaseous effluents. (a) The ground level release of actMty for the first and second quarters occurred during concrete scabbing of outbuilding walls and floors. The HEPA filter units used at these work sites met all the specifications and l monitoring requirements stated in the Final Safety Analysis Report. (b) There are no longer any batch mode gaseous releases. (c) lodine-131, lodine-133, and lodine-135 actMties have been deleted. These nuclides are no longer available l for discharge. mros n atomsHwrntrrtut 98A

l I e f TABLE 2A Yankee Atomic Electric Comoanv. Rowe. Massachusetts Effluent and Waste Discosal Semiannual Reoort First and Second Quarters 1998 Uauid Effluents - Summation of All Releases Est. ot Unit Quarter 1 Quarter 2 p,, A. Fission and Activation Products

1. Total Release (not including tritium, gases, alpha)

Ci ND ND

• 2.00e+01 l

2. Average Diluted Concentration During Period pCVml ND ND

3. Percent of Applicable Limit (*)

0.00e+00 0.00e+00 B. Tritium

1. Total Release Cl 1.45e-03 4.49e-04

• 1.00e+01

2. Average DRuted Concentration During Period pCVml 2.10e-08 5.25e-09

3. Percent of Appicable Limit (*)

7.00e-04 1.75e-04 C. Dissolved and Entrained Gases

1. Total Release Cl ND ND

• 2.00e+01

2. Average D0uted Concentration During Period pCVml ND ND

3. Percent of Applicable Limitoo 0.00e+00 0.00e+00 D. Gross Alpha Radioactivity

1. TotalRelease Cl ND ND

• 3.50e+01 E. Volume of Waste Release (prior to dilution) liters 4.39e+04 2.88e+04 2.00e+01 F. Volume of Dilution Water Used During Period liters 6.90e+07 8.55e+07
• 1.5e+01 ND Not detected in liquid effluents.

l (a) Concentration limits specified in Appendix B to 10CFR20.1-20.602, Table !!, Column 2 (ODCM Control 2.1). l The percent of applicable limit reported is based on the average diluted concentration during the period. At l no time did any release exceed the concentration limit. (b) Concentration limits for dissolved and entrained noble gases is 2.00E-04 pCVml (ODCM Control 2.1). 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. weme nuosamunem l l

1 \\ l o TABLE 2B Yankee Atomic Electric Comoany. Rowe. Massachusetts Effluent and Waste Disoosal Semlannual Reoort First and Second Quarters 1998 t_iould Effluents - Routine Releases Continuous Mode Batch Mode Nuclides Released Unit Quarter 1 Quarter 2 Quarter 1 Ouarter 2 Strontium-89 Ci ND ND ND ND Strontium-90 Cl ND ND ND ND Cesium-134 Cl ND ND ND ND Cesium-{37 Cl ND ND ND ND Cobalt-58 Cl ND ND ND ND Cobalt-60 Cl ND ND ND ND Zine-65 Ci ND ND ND ND Manganese-54 Cl ND ND ND ND i Cerium-144 Cl ND ND ND ND Carbon-14 Cl ND ND ND ND tron-55 Cl ND ND ND ND Unidentified Cl ND ND ND ND 1 Totalfor Period (above) Cl ND ND NO ND Krypton-85 Cl ND ND ND ND 1 I ) 4 i l l i i ND Not detected in liquid effluents. j um. REEGOBtMihEFFUnm l-L I

l l l l;' l TABLE 3 (Sheet 1 of 2) Yankee Atomic Electric Comoany. Rowe. Mancanhusetts l Effluent and Waste Disonnal Semiannual Reoort. First and Second Quarters 1998 4 Solid Waste and Irradiatad Fuel Shioments A. SOLID WASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL (not irradiated fuel) 6-month Est. Total

1. Type of Weste Unit Period Error, %

8 a. Dry Active Waste: Class A m 1.21 e+02 d.50e+01 Containers: steel box (101 ft*) CI(Est.) 1.82e-01 8 b. Dry Active Waste: Class A m 2.03e+00 d.50e+01 l Containers:(a) CI(Est.) 8.94e-03 c. Resins: m' O.00e+00 NA CI(Est.) 0.00e+00 d. Irradiated Components: NA Ci st.) 0

2. Estimate of Nuclide Composition > 1% (by type of waste) a.

Iron-55 ' '4 3.53e+01 _ Cobalt-60 2.32e+01 Nickel-63 '4 2.22e+01 Cesium-137 1.88e+01 b. Iron-55 6.34e+01 Cobalt 40 2.00e+01 , Nig,kel-63 1.50e+01 (a) Partial shipments by the processor to disposal atras ameomewarrrunseA

i s TABLE 3 (Sheet 2 of 2) Yankee Atomic Electric Comoany. Rowe. Maccanhusetts Effluent and Waste Disconal Semlannual Reoort First and Second Quarters 1998 Solid Waste and Irradiatad Fuel Shioments

3. Solid Weste Disposition Number of Shloments Mode of Transportation Destination j

10 truck Clive, UT 5(a) truck Bamwell, SC 11(b) truck Oak Ridge, TN 3(b) truck Memphis, TN B. IRRADIATED FUEL SHIPMENTS (Disposition): None l l i l l t l l 4 (a) Partial shipments by the processor to disposal. (b) Waste shipments to processor. 84646 R ecomemvmtmNT.96A E___________

e I' APPENDIX A Radioactive i Inisid Effluent Monitoring Instrumentation Requirement: Radioactive liquid effluent monitoring instrumentation channels 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 return the instrument (s) l to operable status within 30 days being unsuccessful, ODCM Control 5.1 requires an explanation for the delay in correcting the inoperability in the next Effluent and Waste Disposal Semiannual Report. Response-As noted in the last Semiannual Effluent Report, the Turbine Building Sump composite sampler, located on the 002 discharge pathway, has been permanently removed from service as part of the plant's dismantlement and decommissioning process. On that date, the service water pumps were permanently secured from service, resulting in the cessation of water flow via the - 002 pathway. Chemistry confirmed by inspection that flow via the 002 outflow l pipe had been terminated. Additionally, auxiliary boiler arid 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 surveillance. These requirements are necessary only when releases are occurring via the appropriate effluent release points. Therefore, with the securing of the 002 pathway, 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 in the next scheduled change to the ODCM. l s L i i L A-1 ses - amtomamtram ma

f APPENDIX B Raetieunedive Ancaous Effluent Monitorina instrumentation Requirement: Radioactive gaseous effluent monitoring instrumentation channels are 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.

Response

The requirements of ODCM Control 5.2 governing the operability of radioactive gaseous effluent monitoring instrumentation were met for this reporting period. l i I e B-1 8'2" mneomammuruna

[ -- 1 l-APPENDIX C Uauid Holeinn Tanks i Requirement: Defueled Technical Specification 3.4 limits the quantity of radioactive material l contained in any outside temporary tank. With the quantity of radioactive material in any outside temporary tank exceeding the limits of Technical Specification 3.4, a description of the events leading to this condition is required in the next Effluent and Waste Disposal Semiannual Report. Rannonse: The limits of Technical Specification 3.4 were not exceeded during this reporting period. C1 mess n aam m m urun m

1 APPENDIX D Radiological Environmental Monitorina Proaram Requirement: The Radiological Environmental Monitoring Program is conducted in accordance with ODCM Control 4.1. With milk 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) for obtaining replacement sample (s) in the next Effluent and Waste Disposal Semlannual Report and inclusion of revised ' Off-Site Dose Calculation Manual figure (s) and table (s) reflecting the new I location (s). Rannonse: All required milk samples were found to be available during this reporting period. Therefore, no replacement sample locations need be identified. I I -i 8/26/98 FW4EGHD4YTEFFLNT 98A

APPENDIX E Land Use Census Raoutrement: A land use census is conducted in accordance with ODCM Control 4.2. 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 ODCM Control 3.5, ODCM Control 4.2 requires the identification of the new location (s) in the next Effluent and Waste Disposal Semiannual Report.

Response

The annual land use census is scheduled for completion during the second half of 1998. Requirement: With a land use census identifying a location (s) which yields 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 ODCM Contro! 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 required in the next Effluent and Waste Disposal Semiannual Report. Resnonse: The annual land use census is scheduled for completion during the second half of

1998, l

l l l I L l l E-1 mem RWLEOPBHWREFFLNT 98A )

k 4 APPENDIX F l Prona== Control Proaram (PCP) Requirement-PCP Control 2.0 requires that licensee-initiated changes to the PCP be submitted to the Commission in the Effluent and Waste Disposal Semlannual Report foi he t period in which the change (s) was made. I

Response

There were no licensee-initiated changes to the PCP completed during this i reporting period. i ) F-1 m., R $lEGH84YIEr rt NT.98A I

APPENDIX G Off-Rite Dose Calentation Manual (ODCM) Requirement: ODCM Control 7.2 requires that licensee-initiated changes to the ODCM be submitted to the Commission in the Effluent and Waste Disposal Semiannual Report for the period in which the change (s) was made effective.

Response

There were no licensee-initiated changes to the ODCM during this reporting period. I i l l l G-1 mese nveomammteruassa

APPENDIX H Radieive i lanid Gamm m. and hlid Wanta Tramtment Svntems Requirement: ODCM Control 7.3 requires that licensee-initiated major changes to the radioactive waste systems (liquid, gaseous, and solid) be reported to the Commission in the Effluent and Waste Disposal Semiannual Report for the period in which the evaluation was reviewed by the Plant Operation Review Committee.

Response

There were no licensee-initiated changes to the radioactive liquid, gaseous, or solid waste treatment systems during this reporting period. I H-1 mm. ameace m snua. 4

1 ?* APPENDIX l Sunnlemental Information First and Second Quarters 1999 1. Control Limits - Dose and Dose Rate Control and Cateoorv Umit a. Noble Ances Control 3.3, Total body dose rate 500 mrem / year Control 3.3, Skin dose rate 3000 mrem / year Control 3.4, Gamma air dose 5 mrad / quarter Control 3.4, Gamma air dose 10 mradlyear Control 3.4, Beta air dose 10 mrad / quarter Control 3.4, Beta air dose 20 mrad / year b. Iodine-131. Tritium. and Radionuclides in Particulate Form With Half-Uves Greater Than 8 Davs Control 3.3, Organ dose rate 1500 mrem / year Control 3.5, Organ dose 7.5 mrem / quarter Control 3.5, Organ dose 15 mrem / year - c. Liquids Control 3.1, Total body dose 1.5 mrem / quarter Control 3.1, Total body dose 3 mrem / year Control 3.1, Organ dose 5 mrem / quarter Control 3.1, Organ dose 10 mrem / year l-1 men necomemenuam

g p. 2.- Controllimits - Concentration Control and Category 1.jmil a. Ljguida Control 2.1. Total sum of the fraction of MPC (10CFR20, 1.0 i' . Appendix B, Table ll, Column 2), excluding noble gases 1 - less than: Control 2.1, Total noble gas concentration - 2.00E-04 pCl/cc t 3. Man *'waments and Annradmatinns of Total Radinadivity a. Noble maman. Krvnton-85 Continuous discharges are determined by direct measurements. A primary vent stack gas sample is taken modhly and analyzed for Krypton-85. A review of the weeloy primary vont stack noble gas integrator readings for any increase in values above the backnround level also is used as a reference. There are no longer any batch discharges. Errors associated with the above measurements are estimated to be *25 percent, b. lodines. Particulate 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 sample 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 be *30 percent. c. l_lquid 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 alpha activity, and carbon-14. Tritium analysis is performed on composite samples for continuous discharges and on each batch discharge. The errors associated with these measurements are as follows: fission and activation products, *20 percent; tritium, 10 percent; dissolved fission gases, *20 percent; and alpha activity, *35 percent. !*2 8/26/98 R\\REGAB>AYFifFFLNT.ptA

I ) I 4. Batch Releases j 9 a.- Liquids Outdoor Routine Tank First Quarter Batches MQatS* I Number of batch releases: 2. 1 Total time period for batch releases (minutes): 1885 Maximum time period for a batch release (minutes): 990 Average time period for batch releases (minutes): 943 Minimum time period for a batch release (minutes): 895 Average stream flow (Sherman Dam) during period (cfs): 841 Average discharge rate (gpm): 6.1 Outdoor Routine Tank Second Quarter Batches Moats

• Number of batch releases:

1 Total time period for batch releases (minutes): .1264 i Maximum time period for a batch release (minutes): 1264 l Average time period for batch releases (minutes): 1264 Minimum time period for a batch release (minutes): 1264 Average stream flow (Sherman Dam) during period (cfs): 629 Average discharge rate (gpm): 6.0 b.- Gases Dere are no longer any gaseous batch discharges. 5. Abnormal Releases l l ODCM Control 7.2 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. l 'a. Liquid j i There were no nonroutine liquid releases during the reporting period. b. Gases There were no nonroutine gaseous releases during the reporting period. l l E-There are no longer batch releases from outdoor tank moats due to their decontamination and removal from service as part of plant decommissioning actMties. MM8 RWEGm0HWREFFLNT.90A}}