ML20211C342

Proposed Tech Specs Pages 3.8-3.9b to TS Section 3.1.4 Providing More Restrictive Limit of 0.35 Uci/Gram Dose Equivalent I-131 & Clarifying UFSAR Analysis

ML20211C342
Person / Time
Site:	Three Mile Island
Issue date:	09/19/1997
From:	GENERAL PUBLIC UTILITIES CORP.
To:
Shared Package
ML20211C326	List: ML20211C321 ML20211C342
References
NUDOCS 9709260164
Download: ML20211C342 (7)

Text

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ENCL,OSilitE 1 SUPPLEMENTAL TMI-l TECIINICAL SPECIFICATION /UFSAR REVISED PAGES 5

9709260164 970919 PD4 ADOCK 05000289 P PDR:

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-3.1.4 REACTOR COOLANT SYSTEM ACTIVITY

-g 3.1 A.1 : LIMITING CONDITION FOR OPERATION The specific activity of the primary coolant shall be limited to:

' a. - Less than or equal to 0.35 microcuric/ gram DOSE EQUIVALENT l-131, and l

b. Less than or equal to 100/E microcuries/ gram

• 3.1.4.2 AINCABILITY: at all times except refueling 3.1.4.3 ACTION:

MODES: Power Operation, Start-Up, Hot Standby

a. With the specific activity of the primary coolant greater than 0.35 microcurie / gram DOSE- l EQUIVALENT l 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 exceeding the limit line shown on Figure 3.1-2a, be in at least 110T SilUTDOWN within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />. Power operation .nay continue when DOSE EQUIVALENT l-131 is below j

' 8 O 35 microcurie / gram.

b. With the specific activity of the primary coolant greater than 100/E microcuries/ gram be

in at least 110T SHUTDOWN within 6 h_ours. Power operation may continue when primary coolant activity is less than 100/E microcuries/ gram.

MODES: At all times except refueling.

c. With the specific activity of the primary coolant greater than 0.35 microcurie / gram DOSE l

- EQUIVALENT l-131 or greater than 100/E microcuries/ gram perform the sampling and analysis requirements of Table 4.1-3 until the specific activity of the primary coolant is restored to withit. its limits.

IMEO The limitations on the specific activity of the primary coolant ensure that the 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 be well within the Part 100 limit following a steam generator tube rupture accident or steam line break accident with postulated accident induced steam generator tube leakage in conjunction with an assumed steady state primary-to-secoadary steam generator leakage rate of 1.0 GPM. He values -

. for the limits on specific activity represent limits based on a parametric evaluation by the NRC of typical site locations. These values are conservative, in that the specific site parameters of TMI-1, such as site boundary, location and meteorological conditions, were not considered in this evaluation.

• - E shall be the average (weighted in proportion to the concentration of each radionuclide in the reactor coolant at the time of sampling) of the sum of the average beta and gamma energies per -

disintegration (in MeV) for isotopes, other than iodines with halflives greater than 15 minutes, making up at least 95% of the total non-iodine activity in the coolant.

- " The time period begins from the time the sample is taken.

3-8 Amendment No. IM WI

%c ACTION statement permitting POWER OPERATION to continue for limited time periods with the primary coolant's specine activity greater than 0.35 microcuric/ gram DOSE EQUIVALENT l-131, but l l

within the allowable limit shown on Figure 3.1-2a, accommodates possible iodine spiking phenomenon which may occur following changes in TilERMAL POWER.

Proceeding to 110T SillRDOWN prevents the release of activity should a steam generator tube rupture since the saturation pressure of the primary coolant is below the lifi pressure of the atmospheric steam relief valves.

The surveillance requirements provide adequate assurance that excessive specine activity levels in the primary coolant wil) be detected in sulTicient time to take corrective action. Information obtained on iodine spiking will be used to assess the parameters associated with spiking phenomena. A reduction in frequency ofisotopic analyses following power changes may be permissible ifjusti6ed by the data obtained.

The NRC stafThas performed a generic analysis of airborne radiation released via the Reactor Building Purge Isolation Valves. The dose contribution due to the radiation contained in the air and steam released through the purge isolation valves prior to closure was found to be acceptable provided that the requirements of Specincations 3.1.4.1,3.1.4.2 and 3.1.4.3 are met.

3-9 Amendment No d, d

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e 40 50 80 70 $0 90 100 20 30 F1RCE,NT OF RATED THERMAL POWER FIGURE 3.1-2a Dose equivalent 1-131 Primary Coolant Specific Activity Limit Versus Percent of RATED TlIERMAL POWER (with the Primary Coolant Specific Activity >0.35 pCi/ gram Dose Equivalent 1-131).

Amendment No. Ikd, J[7 3-9b

TMI-1/FSAR The analysis ofIntermediate Building environment following a postulated main steam break is discussed in Reference 9. The consideration of etTects of piping system breaks outside containment is presented in Aplandix A. The primary system response is essentially the same for breaks inside or outside containment.

Breaks inside containment pressurize the Containment Building, whereas breaks outside containment can result in higher dose rates.

c. Environmental Consequences The environmental consequences from this accident are calculated by assuming that:

1) The unit has been operating with an RCS dose equivalent iodine activity of 1.0 pCi/g for the accident induced iodine spike analysis. This is more conservative than the limit in Technical Specincation 3.1.4. At the onset of the steam line break, the release rate ofiodine from the fuel rods to the RCS is assumed to spike by a factor of 500.

2) Some credit is taken for partitioning and mdioactive decay after the break.

3) The steam line break occurs between the Reactor Building and a turbine stop valve.

4) Reactor coolant leakage into the steam generator continues until the Reactor Coolant System can be cooled down and the leakage terminated.

5) The total primary-to-secondary leakage assumption is int. grated over the cooldown time to account for accident induced OTSG tube leakage.

The steam line break is assumed to result in the release of the activity contained in the steam generator inventory, the activity contained in feedwater, and the activity contained in reactor coolant leakage (see Table 14.1-18). Using these assumptions, the total integrated dose to the thyroid and the whole body dose have been calculated and are tabulated in Table 14.1-18 (Reference 77).

14.1-32 UPDATE-

/98

a ENCLOSURE II Certificate of Service for Supplement to TMI-l License Amendment Request No. 269 l

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UNITED STATES OF AMERICA

, NUCLEAR REGULATORY COMMISSION IN TIIE MATTER OF DOCKET NO. 50-289 GPU NUCLEAR INC. LICENSE NO. DPR-50 CERTIFICATE OF SERVICE This is t( certify that a copy of the Supplement to License Amendment Request No. 269 for Three Mile Island Nuclear Station Unit 1, has, on the date given below, been filed with executives of Londonderry Township, Dauphin County, Pennsylvania; Dauphin County, Pennsylvania; and the Pennsylvania Department of Environmental Resources, Bureau of Radiation Protection, by deposit in the United States mail, addressed as follows:

Mr. Darryl LeHew, Chairman Ms. Sally S. Klein, Chairman Board of Supervisors of Board of County Commissioners Londonderry Township of Dauphin County R. D. #1, Geyers Church Road Dauphin County Courthouse Middletown, PA 17057 Harrisburg, PA 17120 Director, Bureau of Radiation Protection PA Dept. of Environmental Resources Rachael Carson State Oflice Building P.O. Box 8469 Ilarrisburg, PA 17105-8469 Att: Mr. Stan Maingi GPU NUCLEAR INC.

BY: bat 4 g" ice President agirector,Tul DATE: /7 7

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