Text

Amend 90 to License DPR-36,revising Tech Specs to Incorporate Specific Requirements for Iodine Spiking Into Annual Rept Per Generic Ltr 85-19 & to Delete Primary Coolant Iodine Activity Rept
	ML20197B600
Person / Time
Site:	Maine Yankee
Issue date:	10/27/1986
From:	Thadani A; Office of Nuclear Reactor Regulation
To:	;
Shared Package
ML20197B571	List: ML20197B566; ML20197B600; ML20197B611;
References
	GL-85-19, NUDOCS 8610300335
	Download: ML20197B600 (9)
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NUCLEAR REGULATORY COMMISSION

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MAINE YANKEE ATOMIC POWER COMPANY DOCKET N0. 50-309 MAINE YANKEE ATOMIC POWER STATION AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 90 License No. DPR-36

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

A. The application for amendment by Maine Yankee Atomic Power Company, (thelicensee),datedJuly 29, 1986, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Comission's rules and regulations 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 Comission; C. There is reasonable assurance (1) that the activities authorized p' 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 Comission's regulations; D. The issuance of this amendment will not be inimical to the comon i defense and security or to the health and safety of the public; and f E. The issuance of this amendment is in accordance with 10 CFR Part 51 of the Comission'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 2.B(6)(b) to read as follows:

b. Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 90 , are hereby incorporated in the licen w. The licensee shall operate the facility in accordance with the Technical Specifications.

3. This license amendment is effective as of the date of its issuance.

FOR THE NUCLEAR REGULATORY COMMISSION

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l Ashok . Thadani, Director PWR P ject Directorate #8 Division of PWR Licensing-B

Attachment:

Changes to the Technical Specifications Date of Issuance: October 27, 1986 e

ATTACHMENT TO LICENSE AMENDMENT NO. 90 TO FACILITY OPERATING LICENSE NO. DPR-36 DOCKET NO. 50-309 Revise Appendix "A" as follows':

Remove Pages Insert Pages 3.2-1 3.2-1 3.2-2 3.2-2

5.9-1 5.9-1 5.9-2 5.9-2 5.9-3 5.9-3 5.9-4 5.9-4 O

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3.2 REACTOR COOLANT SYSTEM ACTIVITY

, Applicability:

Applies to measured maximum activity in the reactor coolant system.

Objective:

To ensure that the reactor coolant activity does not exceed a level connensurate with the safety of the plant personnel and the public.

Specification:

) A. The specific activity of the primary coolant shall be limited to less than or equal to 1.0 micro Ci/ gram DOSE EQUIVALENT I-131.

Remedial Action: . If the specific activity of the primary coolant is greater than 1.0 micro Ci/ gram DOSE EQUIVALENT I-131 for more than 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months 'during one continuous time interval or exceeds the limit line shown on' Figure 3.2-1, the reactor must be made sub-critical with T less than 500 F within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months (Condition 4 Transthermal). avg l

B. The specific activity of the primary coolant shall bc limited to less than or equal to 100/E micro Ci/ gram.

Remedial Action: If the specific activity of the primary coolant

' is greater than 100/T micro Ci/ gram, the reactor must be made sub-i -

critical with T less than 500*F within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months (Condition 4 l Transthennal). "V9 Remedial Action: If the specific activity of the primary coolant is greater than 1.0 micro Ci/ gram DOSE EQUIVALENT I-131 or greater than 100/E micro Ci/ gram, the sampling and analysis reouirements of Item 1 cf Table 4.2-1 shall be performed until the specific activity of the primary coolant is restored to within its limits.

BASIS:

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' The limitations on the specific activity of the primary coolant ensure that the resulting 2 hour2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months doses at the site boundary will not exceed an appropriately small fraction of the Part 100 limit following a steam generator tube rupture.

3.2-1 Amendment No. JE,$5, 90 i

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! PERCENT OF RATED THE" MAL POWER l FIGURE 3.2-1 DOSE EQUlVALENT l-131 Primary Coolant Specific Activity Limit Versus Percent of RATED THERMAL POWER with the Primary Coolant Specific Activity >1.0pCi/ gram Dose Equivalent 1131 i

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(

l 3.2-2 Amendment No. 90

)

5.9 REPORTING REQUIREMENTS ROUTINE REPORTS 5.9.1 In addition to the applicable reporting requirements of Title 10, Code of Federal Regulations, the following reports'shall be submitted to the Regional Administrator of the Regional Office of the NRC unless otherwise noted.

STA,RTUP REPORT 5.9.1.1 A sumary report of plant startup and power escalation testing shall be submitted following (1) receipt of an operating license, (2) amendment of the license involving a planned increase in power level, (3) installation of fuel that has a different design or has been manufactured

. by a different fuel supplier, and (4) modifications that may have significantly altered the nuclear, thermal, or hydraulic performance of the plant. The~ report shall

. address each of the tests identified in the FSAR and shall include a description of the measured values of the operating conditions or characteristics obtained during the test program and a comparison of these values with design predictions and specifications. Any corrective

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actions that were required to obtain satisfactory opera-tion shall also be described. Any additional specific details required in license conditions based on other commitments shall be included in this report.

5.9.1.2 Startup reports shall be submitted within (1) 90 days following completion of the startup test program, (2) 90 days following resumption or commencement of commercial power operation, or (3) 9 months following initial crit-icality, whichever is earliest. If the Startup Report does not cover all three events (i.e., initial criticality, completion of startup test program, and the resumption or commencement of commercial power operation), supplementary reports shall be submitted at least every three months until all three events have,been completed.

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. ANNUAL REPORTS l 5.9.1.3 Annual Reports covering activities as described below for l the previous calendar year shall include:

I A. A tabulation on an annual basis of the number of l station, utility and other personnel (including contractors) receiving exposures greater than 100 mrem /yr and their associated nan rem exposure according to work and job functions,* e.g., reactor operations and surveillance, inservice inspection, routine maintenance, special maintenance (describe maintenance), waste processing, and refueling. l

This tabulation supplements the requirement of $20.407 of 10 CFR Part 20.

5.9-1 Amendment No. M EO,77,7H 90

The dose assignment to various duty functions may be i estimates based on pocket dosimeter, TLD, or film badge measurements. Small exposures totaling less than 20% of the individual total dose need not be accounted for. In the aggregate, at least 80% of the total whole body dose received from external sources shall be assigned to specific major work functions.

B. The results of specific activity analysis in which the primary coolant exceeded the limits of Specifica-tion 3.2. The following infomation shall be included:

(1) Reactor power history starting 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months prior to the' first sample in which the limit was exceeded; (2) Results of the last isotopic analysis for radio-iodine performed prior to exceeding the limit, results

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of. analysis while limit was exceeded and results of one analysis after the radiciodine activity was reduced to less than limit. Each result should include date and time of sampling and the radioiodine concentrations; (3) Clean-up system flow history starting 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months prior to the first sample in which the limit was exceeded; (4) Graph of the I-131 concentration and one other radiciodine isotope concentration in microcuries per gram as a function of time for the duration of the specific activity above the steady-state level; and (5) The time duration when the specific activity of the primary coolant exceeded the radiotodine limit.

MONTHLY OPERATING REPORT 5.9.1.4 Routine reports of operating statistics and shutdown experience shall be submitted on a monthly basis to the Management Infomation Branch ~of the Office of Resource Management U.S. Nucleci Regulatory Coninission, Washington, D.C. 20555, with a copy to the Regional Office, to arrive no inter than the 15th of each month following the calendar month covered by the report.

UNIQUE REPORTING REQUIREMENTS -

5.9.1.5 Annual Radiological Environmental Operating Report Routine Radiological Environmental Operating Reports covering the operation of the unit during the previous calendar year shall be submitted prior to liay 1 of each year.

The Annual Radiological Environmental Operating Reports shall I include summaries, interpretations, and an analysis of trends of the results of the radiological environmental surveillance activities for the report period, and an assesrment of the environmental impact of plant operation, if any. The reports shall also include the results of the land use censuses required by Specification 4.8.B.

5.9-2 Amendment No. #,Ep.77,#,U,90

The Annual Radiological Environmental Operating Reports I shall include sumarized 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 Semiannual Radioactive Effluent Release Report Routine Radioactive Effluent Release Reports covering the

, operating of the unit during the previous 6 months of operation shall be submitted within 60 days after January 1 and July 1 of each year.

The Radioactive Effluent Release Reports shall include a summary of the quantities of radioactive liquid and gaseous effluents and solid waste released from the unit with data fumarized on a quarterly basis.

In addition, the Radioactive Effluent Release Report to be submitted 60 days after January 1 of each year shall include an annual summary of hourly meteorological data collected over the previous year. This annual summary may be either in the form of an hour-by-hour listing on magnetic tape of wind speed, wind direction, atmospheric stability, and precipitation (if measured), or in the form of joint frequency distributions of wind speed, wind direction, and atmcspheric stability.*

. The Radioactive Effluent Release Report to be submitted 60 i days after January 1 of each year shall also include an estimate of the maximum potential radiation doses to the memter(s) of the public fron reactor releases for the previous calendar year. The assessment of radiation doses shall be perfonned in accordance with the Off-Site Dose Calculation Manual (0DCM).

In lieu of submission with the first half year Radioactive Effluent Release Report, the licensee has the options of retaining this senmary of required meteorological data in a file that shall be provided to the NRC upon request.

5.9-3 Amendment No. #,50,77,79,$$,90

9 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 (s ecify whether detennined by measurement or estimate .

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

d. Source waste and p'rocessing 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, asphalt, "Dow").

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 during the reporting period.

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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 Reports shall include changes to the ODCM for information.

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 bc submitted concerning the activities identified below pursuant to the requirements of the applicable specification j or rule.

a. Reactivity anomalies, Specification 3.15.

b. Excessive radioactive release, Specifications 3.16A2 and 3.17A2.

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

d. Total Dose, Specifications 3.16 and 3.17. I I

5.9-4 Amendnent No. #,50.77,79.86,90

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ML20197B600

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