ML20212C028

Proposed Tech Specs Re Reporting Requirements for Primary Coolant Sys Iodine Spikes

ML20212C028
Person / Time
Site:	Maine Yankee
Issue date:	07/29/1986
From:	Maine Yankee
To:
Shared Package
ML20212C025	List: ML20212C021 ML20212C028
References
NUDOCS 8608070304
Download: ML20212C028 (8)

Text

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M AINE YANKEE ATOMIC POWEQ COMPANV PAGE CHANGE LIST Remove the following pages from the existing Technical Specifications and replace with new pages of the same number contained herein.

Page 3.2-1 3.2-2 5.9-1 5.9-2 5.9-3 5.9-4

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3.2 REACTOR COOLANT SYSTEM ACTIVITY apolicability:

Applies to measured maximum activity in the reactor coolant system.

Objective:

To ensure that the reactor coolant activity does not exceed a level commensurate 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 C1/ gram DOSE EQUIVALENT I-131.

Remedial Action: If the specific activity of the primary coolant is ]

greater than 1.0 micro C1/ gram DOSE EQUIVALENT I-131 for more than ]

48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> during one continuous time interval or exceeds the limit ]

line shown on Figure 3.2-1, the reactor must be made subtritical with ]

Tavg less than 500*F within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> (Condition 4, Transthermal). ]

B. The specific activity _of the primary coolant shall be 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/E micro C1/ gram, the reactor must be made subtritical ]

with Tavg less than 500*F within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> (Condition 4 Transthermal). ]

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 C1/ gram, the sampling and analysis requirements of Item 1 of Table 4.2-1 shall be performed until the specific activity of the primary coolant is restored to within its limits. ]

]

BASIS:

The limitaticas on the specific activity of the primary coolant ensure that th resulting 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> 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 07/29/86 7650L-SDE

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ll 0 20 30 40 50 60 70 80 90 100 PERCENT OF RATED THERMAL POWER FIGURE 3.2-1 DOSE EQUIVALENT l-131 Primary Coolant Specific Activity Limit Versus Percent of RATED THERMAL POWER with the Primary Coolant Specific Activity >1.0gCi/ gram Dose Equivalent 1-131 a'

• 3.2-2 I

r MAINE YANKEE ATOMIC POWER COMPANY

• ATTACHMENT A 5.9 REPORTING REOUIREMENTS 1

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.

STARTUP REPORT 5.9.1.1 A summary report of plant startup and power escalation 1

testing shall be submitted following (1) receipt of an i 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 actions that were required to obtain satisfactory operation 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 criticality, 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.

ANNUAL REPORTS ]

5.9.1.3 Annual Reports covering activities as described below ]

for the previous calendar year shall include: ]

A. A tabulation on an annual basis of the number of ]

station, utility and other personnel (including i contractors) receiving exposures greater than 100 mrem /yr and their associated man rem exposure I according to work and job functions,* e.g., l reactor operations and surveillance, inservice This tabulation supplements the requirement of $20.407 of 10 CFR Part 20.

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MAINE YANKEE ATOMIC POWER COMPANY

. inspecticn, rcutine maintenance, special maintenance, (describe maintenance), waste processing, and refueling. The dose assignment to various duty functions may be 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 ] j which the primary coolant exceeded the limits of ]

Specification 3.2. The following information ]

shall be included: (1) Reactor power history ']

starting 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> prior to the first sample in ]

which the limit was exceeded; (2) Results of the ]

last isotopic analysis for radioiodine performed ]

prior to exceeding the limit, results of analysis ]

while limit was exceeded and results of one ]

analysis after the radioiodine 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 <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> prior to the first ]

sample in which the limit was exceeded; (4) Graph ]

of the I-131 concentration and one other ]

radioiodine 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 radioiodine 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 Information Branch of the Office of Resource Management, U. S. Nuclear Regulatory Commission, Washington, D. C. 20555, with a copy to l

the Regional Office, to arrive no later than the fifteenth of each month following the calendar month covered by the report.

UNIOUE REPORTING RE0UIREMENTS l

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

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MAINE VANKEE ATOMIC POWER COMPANY t

The Annual Radiological Environmental Operating Reports shall include summaries, interpretations, and an analysis of trends of the results of the radiological environmental surveillance activities for the report period, and an assessment 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.

The Annual Radiological Environmental Operating Reports shall include summarized and tabulated results of, radiological 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 Reoort 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 summarized 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 cf wind speed, wind direction, atmospheric stability, and precipitation (if measured), or in the form of joint frequency distributions of wind speed, wind direction. and atmospheric stability.*

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

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l l 7650L-SDE

MAINE YoNKEE ATOMIC POWER COMPANY l a 'r The Radi@ active Effluent Release Report to be submitted 60 days after January 1 of each year shall also include an estimate of the maximum potential radiation doses to the member (s) of the public from reactor releases for the previous calendar year. The assessment of radiation l doses shall be performed in accordance with the Off-Site Dose i

Calculation Manual (ODCH).

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.

I

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

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

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, 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.

The Radioactive Effluent Release Reports shall include a listing of l new locations for dose calculations and/or environmental monitoring l

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 Soecial Reports Special reports shall be submitted to the Regional Administrator of the Regional Office of the NRC within the time period specified for each report. These reports shall be submitted concerning the activities identified below pursuant to the requirements of the applicable specification 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, Specification 3.12.

d. Total Dose, Specification 3.16 and 3.17.

]

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