ML20216E184

Updated TS Pages 5-8 Through 5-14,which Includes Specifications Relating to Cold Weather Operations & Spent Fuel Pool Water Chemistry

ML20216E184
Person / Time
Site:	Maine Yankee
Issue date:	03/10/1998
From:	Maine Yankee
To:
Shared Package
ML20216E183	List: ML20216E179 ML20216E184
References
NUDOCS 9803170436
Download: ML20216E184 (7)

Text

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Procedures 5.5 5.0 ADMINISTRATIVE CONTROLS 5.5 Procedures 5.5.1 Written procedures shall be established, implemented, and maintained covering the following activities:

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a. The procedures applicable to the safe storage of irradiated fuel  !

recommended in Regulatory Guide 1.33, Revision 2, Appendix A,  !

February 1978;

b. Emergency plan implementation;

c. Cold Weather Operations; l

d. Quality assurance for radiological effluent and environmental monitoring;

e. Fire Protection Program implementation; and

f. All programs specified in Specification 5.6.

l 9003170436 900310 PDR ADOCK 05000309 W PDR  ;

Maine Yankee 5-8

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Progrcms and Manuals 5.6 -

5.0 ADMINISTRATIVE CONTROLS

5.6 Programs and Manuals The following programs shall be established, implemented, and maintained.

5.6.1 Radiation Pretection Procram Procedures for personnel radiation protection shall be prepared consistent with the requimments of 10 CFR 20 and shall be approved, maintained, and adhered to for all operations involving personnel radiation exposure.

5.6.2 Offsite Dose Calculation Manual (ODCM)

a. The ODCM shall contain 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 and trip setpoints, and in the conduct of the radiological environmental monitoring program; and

b. The ODCM shall also contain the radioactive effluent controls and the radiologice! environmental monitoring activities ard descriptions of the information that should be included in the Annual Radiological Environmental Operating and Rac;oactive Effluent Release Reports required by Specification 5.7.2 and Specification 5.7.3.

Licensee initiated changes to the ODCM:

a. Shall be documented and records of reviews performed shall be retained. This documentation shall contain:

1. Sufficient information to support the change (s) together with the appfopriate analyses or evaluations justifying the chango(s);

(continued) 1 Maine Yankee 5-9

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Programs, and Manuals 5.6 5.6 Programs, and Manuals I

5.6.2 Offsite Dose Calculation Manual (ODCM)(continued)

2. A determination that the change (s) maintain the levels of radioactive effluent control required by 10 CFR 20.1302, and 40 CFR 190,10 CFR 50.36a, and 10 CFR 50, Appendix I, and not adversely impact the accuracy or reliability of effluent, dose, or setpoint calculations;

b. Shall become effective after approval of the Plant Manager or ,

designee; and

c. Shall be submitted to the NRC in the form of a complete, legible copy of the entire ODCM as a part of or concurrent with the Radioactive Effluent Release Report for the period of the report in which any change in the ODCM was made. Each change shall be identified by markings in the maigin of the affected pages, clearly indicating the area of the page that was changed, and shall indicate the date (i.e.,

month and year) the change was implemented.

5.6.3 Radioactive Effluent Controls Proaram This program conforms to~10 CFR 50.36a for the control of radioactive effluents and for maintaining the doses to members of the public from radioactive effluents as low as reasonably achievable. The program shall be contained in the ODCM, shall be implemented by procedures, and shall include remedial actions to be taken whenever the program limits are exceeded. The program shallinclude the following elements:

a'. Limitations on the functional capability of radioactive liquid and l l

gaseous monitoring instrumentation including surveillance tests and setpoint determination in accordance with the methodology in the ODCM; i

(continued) l l

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Programs, and Manuals j 5.6

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5.6.3 Radioacliyp Effluent Controls Prooram (continued)

b. Limitations on the concentrations of radioactive material released in liquid effluents to unrestricted areas, conforming to 10 CFR 20, Appendix B; Table 2, Column 2;

c. Monitoring, sampling, and analysis of radioactive liquid and gaseous effluente in accordance with 10 CFR 20.1302 and with the methodology and parameters in the ODCM;

d. Limitations on the annual and quarterly doses or dose commitment to a member of the public from radioactive materials in liquid effluents released from the unit to unrestricted areas, conforming to 10 CFR l 50, Appendix I;

e. Determination of cumulative dose contributions from radioactive effluents for the current calendar quarter and current calendar year in accordance with the methodology and parameters in the ODCM at least every 31 days;

f. Limitations on the functional capability and use of the liquid and gaseous effluent treatment systems to ensure that appropriate portions of these systems are used to reduce releases of radioactivity when the estimated doses in a period of 31 days would ext,eed 2% of the guidelines for the annual dose or dose commitment, conforming to 10 CFR 50, Appendix I;

g. Limitations on the dose rate resulting from radioactive material released in gaseous effluents to areas beyond the site boundary conforming to the dose associated with 10 CFR 20, Appendix B, Table 2, Column 1;

h. Limitations on the annual and quarterly air doses resulting from noble gases released in gaseous effluents from the unit to areas beyond the site boundary, conforming to 10 CFR 50, Appendix I; (continued) l Maine Yankee 5-11

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Programs, and Manutis 5.6 5.6* Programs, and Manuals 5.6.3 Radioactive Effluent Controls Progr.am (continued)

1. Limitations on the annual and quarterly doses to a member of the public from tritium and radionuclides in particulate form with half-lives greater than 8 days in gaseous effluents released from the unit to areas beyond the site boundary, conforming 610 CFR 50, Appendix I; and J. Limitations on the annual dose or dose commitment to any member of the public due to releases of radioactivity and to radiation from uranium fuel cycle sources, conforming to 40 CFR 190; (continued) i 4

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4 Programs, and Manuals 5.6 1

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5.6 Programs, and Manuals 5.6.4 Technical Soecifications (TS) Bases Control Proaram This program provides e means for processing changes to the Bases of these Technical Specifications.

a. Changes to the Bases of the TS shall be made under appropriate administrative controls and reviews.

b. Licensees may make changes to Bases without prior NRC approval prov;ded the changes do not involve either of the following:

A change in the TS incorporated in the license; or A change to the updated FSAR or Bases that involves an unreviewed safety question as defined in 10 CFR 50.59.

c. The Bases Control Program shall contain provisions to ensure that j the Bases are maintained consistent with the FSAR.

d. Proposed changes that meet the criteria of 5.6.4.b above shall be reviewed and approved by the NRC prior to implementation.

Changes to the Bases implemented without prior NRC approval shall <

be provided to the NRC on a frequency consistent with 10 CFR 50.71(e).  ;

5.6.5 Spent Fuel Pool Water Chemistry Program l l

This program provides <:ontrols for monitoring spent fuel pool water chemistry l to minimize the potential effects of corrosion which could affect the safe l storage of irradiated fuel. The program shallinclude identification of critical l variables and control points for these variables. The program shall also l include sampling frequencies and define corrective actions to be taken for off l control point chemistry conditions. The NRC will be notified prior to l elimination or changes to the acceptance criteria for critical variables l monitored. l (continued)

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, Programs, and Manuals  !

5.6

. a 5.6 Programs, and Manuals 5.6.6 Inservice Testina Program l This program provides controls for inservice testing of ASME Code Class 1, 2, and 3 components including applicable supports. The program shall include the following:

a. Testing frequencies specified in Section XI of the ASME Boiler and Pressure Vessel Code and applicable Addenda as follows:

ASME Boiler and Pressure Vessel Code and applicable Required Frequencies for ,

Addenda terminology for performing inservice testing l inservice testing activities activities Weekly At least once per 7 days Monthly At least once per 31 days Quarterly or every 3 months Atleast once per 92 oays i Semiannually or every 6 months At least once per 184 days <

Every 9 months At least once per 276 days Yearly or annually At least once per 366 days ,

Biennially or every 2 years At least once per 731 days I

b. The provisions of SR 3.0.2 are applicable to the above required Frequencies for performing inservice testing activities; ]

c. The provisions of SR 3.0.3 are applicable to inservice testing activities; and i

d. Nothing in the ASME Boiler and Pressure Vessel Code shall be construed to supersede the requirements of any TS.

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