ML20216J016

Amend 99 to License DPR-36,revising Tech Specs 5.9.1.6 & 5.9.1.7,allowing Addl Time for Filing Supplemental Dose & Meteorological Summary Repts & Ensuring Refs to Other Tech Specs Correct

ML20216J016
Person / Time
Site:	Maine Yankee
Issue date:	06/25/1987
From:	Nerses V Office of Nuclear Reactor Regulation
To:
Shared Package
ML20216H992	List: ML20216H984 ML20216J016 ML20216J037
References
NUDOCS 8707020075
Download: ML20216J016 (5)

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MAINE YANKEE ATOMIC POWER COMPANY DOCKET NO. 50-309 MAINE YANKEE ATOMIC POWER STATION AMENDMENT TO FACILITY OPERATING LICENSE i

Amendment No. 99 License No. DPR-36

1. The Nuclear Regulatory Commission (the Commission) has found that:

A. The application for amendment by Maine Yankee Atomic Power Company (the licensee), dated February 24, 1987 complies with the  !

standards and requirements of the Atomic Energy Act of 1954, l as amended (the Act), and the Commission's rules and regulations y set forth in 10 CFR Chapter I; B. The facility will operate 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 i 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 regulations; 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 the Commission's regulations and all applicable requirements have been satisfied.

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2. . Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph ?.B(6)(b) of Facility Operating License No. DPR-36 is hereby amended to read t.s follows:

(b) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 99, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.

3. This license amendment is effective 60 days from the.date of this letter.

FOR THE NUCLEAR REGULATORY COMMISSION Y ic hf&

Nerses, Acting Director Pro,iect Directorate I-3 Division of Reactor Projects I/II

Attachment:

Changes to the Technical Specifications Date of Issuance: June 25, 1987

4 ATTACHMENT TO LICENSE AMENDMENT NO. 99 FACILITY OPERATING LICENSE NO. DPR-36 DOCKET NO. 50-309 i Revise Appendix A as follows:

Remove Pages Insert Pages 5.9-3 5.9-3 5.9-4 5.9-4 1 1

l The Annual Radiological Environmental Operating Reports

, shall include summarized and tabulated results of radio-logical environmental samples taken during the report period pursuant to the tables and figures in the ODCM.

In the event that some results are not available for inclusion with the report, the report shall be submitted noting and explaining the reasons for the missing results.

The missing data shall be submitted as soon as possible in a supplementary report.

The reports shall also include the following: a summary description of the radiological environmental monitoring program including a map of all sampling locations keyed to a table giving distances and directions from the reactor; and a discussion of all analyses in which the LLD required by Table 4.8-2 was not achievable.

5.9.1.6 Radioactive Effluent Reports l l 5.9.1.6.1 Semiannual Radioactive Effluent Release Report I i

Routine Radioactive Effluent Release Reports covering the' l

, operating of the unit during the previous 6 months of j operation shall be submitted within 60 days after  ;

January 1 and July 1 of each year. I The Radioactive Effluent Release Reoorts shall include a summary of the quantities of radioa tive liquid and gaseous )

effluents and solid waste released from the unit with data summarized on a quarterly basis.

The Radioactive Effluent Release Reports shall include the following information for each class of solid waste (as defined by 10 CFR Part 61) shipped off-site during the report period:

a. Container volume.

b. Total curie quantity (specify whether determined by measurement or estimate).

c. Principal radionuclides (specify whether determined by measurement or estimate).

d. Source waste and processing employed (e.g., dewatered spent resin, compacted dry waste, evaporator bottoms).

e. Type of container (e.g., LSA, Type A, Type B, Large Quantity),

f. Solidification agent or absorbent (e.g., cement, j asphalt,"Dow"). t I l Amendment No. M,50iff,79,86,M.99 5.9-3

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I. The Radioactive Effluent Release Reports shall include a list and description of unplanned releases from the site-to-site boundary of radioactive materials in gaseous and ,

liquid effluents made durihg the reporting period. 1 The Radioactive. Effluent Release Reports shall include a listing of new locations for dose calculations and/or environmental monitoring identified by the land use census pursuant to Specification 4.8.B.

The Radioactive Effluent Release Report shall include changes to the ODCM for information.

5.9.1.6.2 Estimated Dose and Meteorological Summary Reports A. A report of the estimated maximum potential doses to the j members of the public from radioactive effluent releases for the previous calendar year shall be submitted within j 90 days af ter January 1 of each year. The assessment of U radiation doses shall be performed in accordance with the Off-Site Dose Calculation Manual (0DCM).

B. An annual summary report of hourly meteorological data .

collected over the previous year shall either be submitted l within 90 days after January 1 of each year or be retained' in a file that shall be provided to the NRC upon request.

This annual summary may be either in the form of an hour-by-hour listing on magnetic tape of wind speed, wind direc-tion, atmospheric stability, and precipitation (if measured) or in the form of joint frequency distributions of wind speed, wind direction, and atmospheric stability.

5.9.1.7 Special Reports Special reports shall be submitted to the Regional Adminis-trator of the Regional Office of the NRC within the time period specified for each report. These reports shall be submitteo concerning the activities identified below pur-suant to the requirements of the applicable specification or rule.

a. Reactivity anomalies, Specification 3.15.

b. Excessive radioactive release, Specifications 3.16B and 3.17B, and 3.17C.

c. Plans for restoration of 115 kV service, Specifica-tion 3.12.  ;

d. Total Dose, Specifications 3.16 and 3.17.

Amendment No M ,50, ,79,86,((,99 l

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