Text

Proposed Defueled Tech Specs Re Required Frequency of Submittal of Radioactive Effluent Release Rept
	ML20155A256
Person / Time
Site:	Yankee Rowe
Issue date:	10/15/1998
From:	; YANKEE ATOMIC ELECTRIC CO.
To:	;
Shared Package
ML20155A254	List: ML20155A249; ML20155A256;
References
	NUDOCS 9810280234
	Download: ML20155A256 (10)
	v • d • e

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ATTACHMENT A Revised Technical Soecifications Pages Annotated Version 1-2 3/4-6 6-17 6-22

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1.0 DEFINITIONS (Continued) 0FF-SITE DOSE CALCULATION MANUAL (00CM) 1.6 The OFF-SITE DOSE CALCULATION MANUAL (00CM) contains the methodology and parameters used in the calculation of off-site doses resulting l from radioactive gaseous and liquid effluents. in the calculation of

! gaseous and liquid effluent monitoring alarm / trip setpoints, and in the conduct of the Environmental Radiological Monitoring Program.

The ODCM also contains (1) the Radioactive Effluent Controls and Radiological Environmental Monitoring Programs required by Section 61.8. and (2) descriptions of the information that should be l l

included in the Annual Radiological Environmental Operating and l l Sem4 annual Annual Radioactive Effluent Release Reports required by '

Specifications 6.8.2.a and 6.8.2.b.

OPERABLE - OPERABILITY 1.7 A system, subsystem, train, component or device shall be OPERABLE or have OPERABILITY when it is capable of performing its specified safety function (s). Implicit in this definition shall be the assumption that all necessary attendant instrumentation, controls, electric power. cooling or seal water, lubrication or other auxiliary equipment that are required for the system, subsystem, train, component or device to perform its safety function (s) are also capable of performing their necessary support function (s).

PROCESS CONTROL PROGRAM (PCP) i 1.8 The PROCESS CONTROL PROGRAM contains the current formulas sampling, analyses test, and determinations to be made to ensure that processing and packaging of solid radioactive wastes based on demonstrated processing of actual or simulated wet solid wastes will be accomplished in such a way as to assure compliance with 10 CFR Parts 20. 61 and 71 state regulations, burial ground requirements.

and other requirements. governing the disposal of solid radioactive waste.

REPORTABLE EVENT 1.9 A REPORTABLE EVENT shall be any of those conditions specified in 10 CFR 50.73.

SITE BOUNDARY 1.10 The SITE BOUNDARY shall be that line beyond defining an area within which the land is not owned, leased, or otherwise controlled by the licensee. Any area within the SITE BOUNDARY used for residential i

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'3/4.4 LIQUID HOLD-UP TANKS LIMITING CONDITION FOR OPERATION 3.4 The quantity of radioactive material contained in any outside i tank that is not surrounded by liners. dikes or walls capable of holding the tank contents. or that does not have a tank overflow connected to the liquid radwaste treatment system. shall be l limited to less than or equal to 10 curies, excluding tritium and dissolved or entrained noble gases.

APPLICABILITY: At all times.

1 ACTION:

With the quantity of radioactive mater 1.1 in any outside tank exceeding the above limit, without delay, take action to suspend all additions of radioactive material to the tasik. Within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months reduce the tank contents io within the limit and describe l the events leading to this condition in the next Sem4 annual Annual Radioactive Effluent Release Report, pursuant to Specification 6.8.2.b. ,

SURVEILLANCE REQUIREMENTS 4.4.1 The quantity of radioactive material contained in any outside tank that is not surrounded by liners, dikes, or walls capable of holding the tank contents shall be determined to be within the above limit by analyzing a representative sample of the tank's contents at least once per 7 days when radioactive materials are being added to the tank.

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YAtlKEE-ROWE 3/4-6

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'6.0 ADMINISTRATIVE CONTR01S (Continued)

The dose assignment to various duty functions may be estimates based on pocket dosimeter. TLD. or film badge measurements.

Small exposures totalling less than 23% of the individual total dose need not be accounted for. In the aggregate, at least 80% of the whole body dose received from external l sources shall be assigned to specific major work functions. l

b. Any other unit-unique reports required on an annual basis. ,

6.8.2 Unique Reporting Requirements

a. Environmental Radiological Monitoring The Annual Radiological Environmental Operating Report covering the operation of the unit during the previous calendar year shall be submitted before May 1 of each year. The report shall include summaries, interpretations. and analysis of trends of the results of the Radiological Environmental Monitoring Progrdm for the reporting period. The material provided shall be consistent with the objectives outlined in (1) the ODCM.

and (2) Sections IV.B.2. IV.B.3. and IV.C of Appendix 1 to 10 CFR 50.

l b. Sem4 annual Annual Radioactive Effluent Release Report l The Sem4 annual Annual Radioactive Effluent Release Report covering the operation of the unit during the l previous s4x-months-of-eperat4en calendar year shall be j submitted w4th4n-60-days-after-January-1-and-July-1 l before May 1 of each year. The report shall include a summary of the quantitles of radioactive liquid and gaseous ef fluents and solid waste released f rom the unit. The material provided shall be (1) consistent ,

with the objectives outlined in the ODCM and PCP. and l (2) in conformance with 10 CFR 50.36a and Section IV.B.1 of Appendix I to 10 CFR 50.

6.8.3 Special Reports Special reports shall be submitted pursuant to 10 CFR 50.4 within the time period specified for each report. These reports shall be submitted covering the activities identified below pursuant to the requirements of the applicable reference specification:

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(ANKEE-ROWE 6-17

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l 6.0 ADMINISTRATIVE CONTROLS (Continued) l 6.13 0FF-SITE DOSE CALCULATION MANUAL (0DCM) 6.13.1 Changes to the ODCH:

a. Shall be documented and records of reviews performed shall be retained as required by Specification 6.9.2.0.

This documentation shall contain:

1) Sufficient information to support the change together with the appropriate analyses or evaluation justifying the change (s), and

2) A determination that the change will maintain the level of the radioactive ef fluent control required by 10 CFR 20.106. 40 CFR 190. 10 CFR 50.36a and Appendix I to 10 CFR 50 and not adversely impact the accuracy or reliability of effluent, dose, or setpoint calculations.

b. Shall become effective after review and acceptance by the PORC and the approval of the Plant Superintendent.

c. Shall be submitted to the Commission in the form of a complete legible copy of the entire ODCM as a part of l or concurrent with the Sem4 annual Annual Radioactive '

Ef fluent Release Report for the period of the report in which any change to the ODCH was made. Each change shall be identified by markings in the margin of the affected pages, clearly indicating the area of the page that was changed, and shall indicate the date (e.g.

month / year) the change was implemented.

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YANKEE-ROWE 6-22 l

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ATTACHMENT B Revised Technical SocciHeations Paces l

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l-2 3/4-6 i 6-17 6-22 i

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1 1.0 DEFINITIONS (Continued) 0FF-SITE DOSE CALCULATION MANUAL (ODCM) 1.6 The OFF-SITE DOSE CALCULATION MANUAL (ODCM) contains the methodology and parameters used in the calculation of off-site doses resulting from radioactive gaseous and liquid effluents, in the calculation of gaseous and liquid ef fluent monitoring alarm / trip setpoints, and in the conduct of the Environmental Radiological Monitoring Program.

The 00CM also contains (1) the Radioactive Effluent Controls and l

Radiological Environmental Monitoring Programs required by Section 61.8. and (2) descriptions of the information that should be included in the Annual Radiological Environmental Operating and l Annual Radioactive Effluent Release Reports required by Specifications 6.8.7.a and 6.8.2.b.

OPERABLE - OPERABILITY 1.7 A system. subsystem train, component or device shall be OPERABLE or have OPERABILITY when it is capable of performing its specified safety function (s). Implicit in this definition shall be the assumption that all necessary attendant instrumentation, controls, electric power. cooling or seal water. lubrication or other auxiliary equipment that are required for the system. subsystem, train, component or device to perform its safety function (s) are also capable of performing their necessary support function (s).

PROCESS CONTROL PROGRAM (PCP) 1.8 The PROCESS CONTROL PROGRAM contains the current formulas, sampling.

analyses, test, and determinations to be made to ensure that processing and packaging of solid radioactive wastes based on demonstrated processing of actual or simulated wet solid wastes will be accomplished in such a way as to assure compliance with 10 CFR Parts 20. 61 and 71. state regulations, burial ground requirements, and other requirements, governing the disposal of solid radioactive waste.

REPORTABLE EVEN1 1.9 A REPORTABLE EVENT shall be any of those conditions specified in 10 CFR 50.73.

l SITE BOUNDARY 1.10 The SITE BOUNDARY shall be that line defining an area within which the land is owned. leased or otherwise controlled by the licensee.

Any area within the clTE BOUNDARY used for residential quarters or I

YANKEE-ROWE l-?

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3/4.4 LIQUID HOLD-UP TANKS LIMITING CONDITION FOR OPERATION 3.4 The quantity of radioactive material contained in any outside i tank that is not surrounded by liners, dikes or walls capable of l holding the tank contents. or that does not have a tank overflow l

connected to the liquid radwaste treatment system. shall be !

limited to less than or equal to 10 curies, excluding tritium and dissolved or entrained noble gases.

APPLICABILITY: At all times.

l ACTION:

With the quantity of radioactive material in any outside tank exceeding the above limit, without delay, take action to suspend all additions of radioactive material to the tank. Within l 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months reduce the tank contents to within the limit and describe l l l the events leading to this condition in the next Annual Radioactive Effluent Release Report, pursuant to Specification 6.8.2.b.

i SURVEILLANCE REQUIREMENTS m_

4.4.1 The quantity of radioactive material contained in any outside tank that is not surrounded by liners, dikes, or walls capable of holding the tank contents shall be determined to be within the above limit by analyzing a representative sample of the tank's contents at least once per 7 days when radioactive materials are being added to the tank.

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4 YANKEE-ROWE 3/4 6

6.0 ADMINISTRATIVE CONTROLS (Continued)

The dose assignment to various duty functions may be estimates based on pocket dosimeter, TLD, or film badge measurements.

Small exposures totalling less than 20% of the individual total dose need not be accounted for. In the aggregate, at least 80% of the whole body dose received from external l sources shall be assigned to specific major work functions. I

b. Any other unit unique reports required on an annual basis.

6.8.2 Uniaue Reporting Reauirements

a. Environmental Radiological Monitoring The Annual Radiological Environmental Operating Report covering the operation of the unit during the previous calendar year shall be submitted before May 1 of each year. The report shall include summaries, interpretations, and analysis of trends of the results of the Radiological Environmental Monitoring Program for the reporting period. The material provided shall be consistent with the objectives outlined in (1) the ODCM, and (2) Sections IV.B.2, IV,B,3, and IV.C of Appendix I to 10 CFR 50.

I b. Annual Radioactive Ef fluent Release Report i The Annual Radioactive Effluent Release Report covering I the operation of the unit during the previous calendar l 1 year shall be submitted before May 1 of each year. The report shall include a summary of the quantities of radioactive liquid and gaseous effluents and solid waste released from the unit. The material provided shall be (1) consistent with the objectives outlined in the ODCM and PCP, and (2) in conformance with 10 CFR 50.36a and Section IV.3.1 of Appendix I to 10 CFR 50.

6.8.3 Special Reports Special reports shall be submitted pursuant to 10 CFR 50.4 within the time period specified for each report. These reports shall be submitted covering the activities identified below pursuant to the requirements of the applicable reference specification:

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YANKEE-ROWE 6-17 1

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6.0 ADMINISTRATIVE CONTROLS (Continued) 6.13 0FF-SITE DOSE CALCULATION MANUAL (ODCM) i 6.13.1 Changes to the ODCM:

a. Shall be documented and records of reviews performed shall be retained as required by Specification 6.9.2.0.

This documentation shall contain:

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1) Sufficient information to support the change l together with the appropriate analyses or evaluation justifying the change (s), and

2) A determination that the change will maintain the ,

level of the radioactive effluent control required by 10 CFR 20.106, 40 CFR 190, 10 CFR 50.36a, and Appendix I to 10 CFR 50 and not adversely impact the accuracy or reliability of effluent, dose, or setpoint calculations.

b. Shall become effective after review and acceptance by the PORC and the approval of the Plant Superintendent.

c. Shall be submitted to the Commission in the form of a complete, legible copy of the entire ODCM as a part of I or concurrent with the Annual Radioactive Effluent Release Report for the period of the report in which any change to the ODCM was made. Each change shall be identified by markings in the margin of the affected pages, clearly indicating the area of the page that was changed, and shall indicate the date (e.g., month / year) the change was implemented, f

YANKEE-ROWE 6-22

ML20155A256

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