ML20207F922

Amend 151 to License DPR-3,revising Pol by Changing Submittal Interval for Radioactive Effluent Rept from Semiannual to Annual

ML20207F922
Person / Time
Site:	Yankee Rowe
Issue date:	03/05/1999
From:	Mendonca M NRC (Affiliation Not Assigned)
To:
Shared Package
ML20207F885	List: ML20207F879 ML20207F922 ML20207F949
References
NUDOCS 9903110356
Download: ML20207F922 (7)

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t UNITED STATES l 2

j NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20666 0001

• * * * * ,o YANKEE ATOMIC ELECTRIC COMPANY ,

1 DOCKET NO.50-029 YANKEE NUCLEAR POWER STATION .

I AMENDMENT TO POSSESSION ONLY LICENSE

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Amendment No.151 License No. DPR-3

1. The U. S. Nuclear Regulatory Commission (the Commission or the NRC) has found that:

A. The application for amendment filed by Yankee Atomic Electric Company (the licensee) dated October 15,1998, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations set forth in 10 CFR Chapter I; B. The facility will be maintained in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C. There is reasonable assurance: (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's i regulations set forth in 10 CFR Chapter I; j l

D. The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E. The issuance of this amendment is in accordance with 10 CFR Part 51 of tha Commission's regulations and all applicable requirements have been satisfied.

2. Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment. Paragraph 2.C.(2) of Possession .

1 Only' License No. DPR-3 is hereby amended to read as follows:

(2) Technical Specificatio_n_s {

The Technical Specifications contained in Appendix A, as revised through l Amendment No.151, are hereby incorporated in the license. The licensee shall possess and maintain the facility in accordance with the Technical Specifications.

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' 3. This license amendment will be effective as of the date of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION

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i Marvin M. Mendonca, Acting Director Non-Power Reactors and Decommissioning Project Directorate Division of Regulatory improvement Programs Office of Nuclear Reactor Regulation >

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Attachment:

Appendix A Technical Specification Changes Date of issuance: March 5, 1999

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l l ATTACHMENT TO LICENSE AMENDMENT NO.151 ,

POSSESSION ONLY LICENSE NO. DPR-3 l DOCKET NO. 50-29 i

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Replace the following pages of the Appendix A Technical Specifications with the attached '

revised pages. The revised pages are identified by amendment number and contain vertical lines indicating the areas of change. 1 l

l Remove insert 1-2 1-2 3/4-6 3/4-6 6-17 6-17 i 6-22 6-22 1

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1.0 DEFINITIONS (Continued) 0FF-SITE 00SF CALCULATION MANUAL (0DCM)

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1.6 The 0FF-SITE DOSE CALCULATION MANUAL (00CM) 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 effluent monitoring alarm / trip setpoints, and in ,

the. conduct of the Environmental Radiological Monitoring Program. l The ODCM also contains (1) the Radioactive Effluent Controls and 1 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 Re' ease Reports required by Specifications 6.8 2.a and 6.8.2.b.

OPERABLE OPERABILITY l

1.7 A system., subsystem. train, componen+ 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 j assumption that all necessary attendant instrumentation, controls, electric power cooling or seal water, lubrication or other I auxillary 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 (PCF) 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 tu assure compliance with 10 CFR Parts 20. 61, and 71. state regulations, burial ground requirements.

and other requirements, governing tne disposal of solid radioactive waste.

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

l YANKEE-ROWE 1-2 Amendment No. 151 i

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3/4.4 L10VID HOLD-UP TANKS LIMITING CONDITION FOR OPERATION 3.4 The quantity of radioactive material contained in any outside tank that is not .urrounded 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 limited to less than or equal to 10 curies, excluding tritium and

' dissolved or entrained noble gases.

APPL lC AB il lT Y : At all times.

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 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> reduce the tank contents to within the limit and describe j the events leading to this condition in the next 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 analy21ng 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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YANKEE-ROWE 3/4-6 Amendment No. 151 l

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6.0 ADMINISTRATIVE CONTROLS (Continued)

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

sources shall be assigned to specific major work functions.

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

1 6.8.2 linique Report ing Roouirements

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

j b Annual Radioactive Effluent Release Report l The Annual Radioactive Effluent Release Report covering l the operation of the unit during the previous calendar ,

l year shall be submitted before May 1 of each year. The I report shall include a summary of the quantities of radioactive 14 quid and gaseous effluents and solid waste released fram 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.B.1 of Appendix 1 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

activitles identified below pursuant to the requirements of l the applicable reference specification

j YANKEE-ROWE 6-17 Amendment No. 151 l

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6.0 ADMINISTRATIVE CONTROLS (Continued)  ;

6 13 -0FF-SITE DOSE Ct.LCUlATION MANUAL (0DCM)  !

6;13.1 Changes to the ODCM:

a. Shall be documented a.1d records of reviews performed l 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 l evaluation justifying the change (s). and .l

2) A determination that the change will maintain the  ;

level of the radioactive effluent control required I by 10 CFR 20.106. 40 CFR 190. 10 CFR 50.36a, and )

Appendix I to 10 CFR 50 and not adversely impact i the accuracy or reliability of effluent, dose, or j setpoint calculations.  !

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!. b. Shall become effective after review and acceptance by the PORC~and the approvci 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

.] 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 indicati.ig the area of the page that was changed. and shall indicate the date (e.g., month / year) l the change'was implemanted.

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I YANKEE.ROWE- 6-22 Amendsent No. 151