ML19347E762

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Safety Evaluation Supporting Amend 15 to License DPR-73
ML19347E762
Person / Time
Site: Crane 
Issue date: 05/06/1981
From:
Office of Nuclear Reactor Regulation
To:
Shared Package
ML19347E758 List:
References
NUDOCS 8105130337
Download: ML19347E762 (5)


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SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION METROPOLITAN EDISON COMPANY JERSEY CENTRAL POWER AND LIGHT COMPANY PENNSYLVANIA ELECTRIC COMPANY DOCKET NO. 50-320 THREE MILE ISLAND NUCLEAR STATION, UNIT NO. 2 Introduction By letters dated February 23 and March 18,1981, (reference 1, 2) the Metropolitan Edison Company (licensee) requested amendments to the Technical Specifications of Operating License No. DPR-73 for the Three Mile Island Nuclear Station, Unit 2.

This evaluation discusses the requested amendments to Appendix B of Operating License No. DPR-73, namely:

(1) Delete requirements to monitor for radioactive iodines in gaseous effluents; (2) Correct sampling locations for the Radioactive Gaseous Waste Sampling and Analysis Program (RGWSA); (3) Delete the Lower Limit of Detection (LLD) specification for gamma emitting gaseous emissions of the RGWSA; (4) Suspend the requirements for an Aerial Remote Monitoring Program to detect the environmental impact of salt drift from the cooling towers.

Evaluation (1) Requirement to monitor for radioactive iodines in gaseous effluents.

Section 2.1.2 and 2.1.3 of the Environmental Technical Specifications (ETS) limit the gaseous effluents of I-131 and require the monitoring of radio-active iodines (I-131, I-133 and I-135) in gaseous effluents.

I-131 is produced as a result of nuclear fission during reactor operation and these technical specifications ensure that the release of I-131 is within the regulatory limits.

Since the March 28,1979, accident, the reactor has been shutdown and I-131 generation has ceased. With a decay constant of 0.086 per day, the I-131 concentration present at the time of the accident has decayed to less than detectable levels. Weekly monitoring of the charcoal sampler in the unit exhaust for I-133 and I-135 also has indicated less than detectable levels.

The staff has reviewed the licensee's request to delete the requirement to monitor radioactive iodines in the gaseous effluents. These factors have been considered:

(a) Since the March 28, 1979, accident, I-131, I-133 and I-135 inventories have decayed, for approximately 80 half-lives in the case of I-131, to the extent that these radionuclides are no longer present in measurable quantities. For a total quantity of I-131, at the time of 81051303 3 7 f

. 7 of I-131 has decayed to less than 1 x 10-1ge 3), the present quantity reactor snutdown, of 6.6 x 10 C1 (referen pCi; (b) throughout the cleanup and defueling operations, provisions will be taken to ensure that recriticality of the nuclear fuel will not occur. Detection of recriticality will primarily be based on direct monitoring of parameters (e.g., neutron flux, temperature, pressure) other than radioactive iodine generation; (c) although the analysis for radioactive iodines may not be required, the charcoal sampler will still be in place and analysis can be performed should it be warranted. Monitoring of gaseous and particulates with half-lives greater than 8 days, except for I-131, is still required.

Based on the above considerations for the fact that I-131 is not present, in measurable quantities and generation of I-131 will not occur through-out the cleanup and defueling operations, the staff has concluded that the deletion of requirements in Section 2.1.2 and 2.1.3 of the ETS in reference to I-131 gaseous effluents limits and radioactive conitoring as proposed by the licensee is appropriate. Therefore, deletion of those ETS requirements is approved.

(2) Correction of sampling location for the RGWSA.

Table 2.1-1 of the ETS requires a monthly sample of the EPICOR-II ventilation exhaust. Note b of Table 2.1-1 specifics the sample location to be the ventilation exhaust of the spent fuel pool area. The ventilation system associated with the EPICOR-II system, however, vents through the exhaust of the Chemical Cleaning Building and, therefore, the proposed change merely corrects the Table to properly reflect the actual location for the sample. Therefore, the staff approves the change as proposed by the licensee to amend Note b of Table 2.1-1 to specify the sample location to be the ventilation exhaust of the Chemical Cleaning Building.

.(3) The LLO for principle gama emitters for the RGWSA.

Table 2.1-1 of the ETS specifies that an analysis for principle gama emitters be performed on the EPICOR-II ventilation of gaseous releases, and requires analyses fer specific gaseous and particulate emissions. The radionuclides which are specifically required to be monitored for gaseous emissions are: Kr-87, Kr-88, Xe-133, Xe-133m, Xe-135 and Xe-138. The staff has evaluated the request to delete the monitoring of these radio-nuclides in gaseous effluents and has considered the following factors:

(a) the longest half-life for these radionuclides is 5.27 days for Xe-133 and all these radionuclides have decaycd to less than detectaole levels.

None of these isotopes are being generated as daughter products from other isotopes that are likely to be present in any significant quantity; (b) the specification to monitor principle gama emitters fcr p:rticulate emissions is still required; (c) the specifications to monitor gross gaseous activity and to sample and monitor for tritium effluents are still required.

' Based upon the foregoing considerations, the staff has concluded that deletion of requirement in Table 2.1-1 of the ETS to analyze for specific gaseous emissions: Kr-87, Kr-88, Xe-133, Xe-133m and Xe-138, as proposed by the licensee, would be appropriate. Other airborne effluents from the EPICOR-II system that could be present in detectable quantities (i.e.,

particulates and tritium) as well as the gross gaseous activity would still be required to be monitored per Table 2.1-1 of the ETS. Therefore, the staff approves the deletion of the requirement in Table 2.1-1 of the ETS to specific analysis for principle gama emitters in gaseous effluents.

(4) Requirements for an Aerial Remote Monitoring Program Section 3.1.2.b(1) of the ETS requires an annual aerial photography program with correlating data from ground inspection surveys and drift modeling for purposes of interpretation and verification of the aerial photographs. The purpose of this surveillance program is to determine possible impacts to surrounding vegetative comunities that may result from the operation of Unit 2 cooling towers. Such impacts may be associated with either episodic high-level or chronic low-level chlorine dosages due to cooling tower drift deposition. The ETS requirement also stipulates that this program shall be continued to two years at initial attainment of Unit 2 normal operation, and at tnat time, the licensee may request modification or termination of this monitoring requirement.

The staff has reviewed the monitoring program results for Unit 2 (NUREG-0738,

" Investigation of Reported Plant and Animal Health Effects in the Three Mile Island Area") and has concluded that there has been no biological damage resulting from the routine operation of the Unit 2 cooling towers.

In addition, the design use of the cooling towers has been suspended since the shutdown after the accident and any operations of the towers during the cleanup operations will be at greatly reduced levels.

Based on the above considerations, the staff concludes that the licensee's request to amend the ETS to suspend the aerial remote sensing and drift monitoring program should be approved since no ill-ef4 cts have been attributed to drift deposition from full operation levels and none will be likely to occur from low, intermittent operational levels.

Environmental Consideration Based on the evaluation above, the proposed amendment to the ETS would not result in any environmental impact beyond those considered in the Final Programmatic Environmental Impact Statement, NUREG-0683 (reference 4) and the Final Supplement to the Final Environmental Statement for TMI Unit 2, NUREG-0112 (reference 5).

The staff has determined that this amendment does not authorize a change in effluent types or total amounts nor an increase in power level and will not result in any significant environmental impact. Having made this determination, the staff has further concluded that this amendment involves an action which is insignificant #mm the standpoint of environmental impact and, pursuant to 10 CFR 51.5(d)(4),t an environmental impact statement or negative declaration and environmental apact appraisal need not be prepared in connection with the issuance of this amendment.

. Conclusion Based upon the staff's review of the proposed amendments to the Environmental Technical Specifications, the staff finds the licensee's request to be accept-able and grants the request. Based on the review, the staff has concluded that:

(1) the modification does not authorize any significant change in the plant's operation, (2) the modification does not involve a significant increase in the probability or consequences of accidents previously considered or a significant reduction in a margin of safety and, therefore, does not involve a significant hazards consideration, (3) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the modified manner, and(4) such activities will be conducted in compliance with the Commission's regulations and the issuance of this modification will not be inimical to the common defense and security or to the health and safety of the public.

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REFERENCES:

1.

Technical Specification Change Request No. 26, Three Mile Island Nuclear f

Station, Unit 2, Docket No. 50-320, Metropolitan Edison Co., February 23, 1981.

2.

Techr.ical Specification Change Request No. 26, Addendum A. Three Mile Island Nuclear Station, Unit 2, Docket No. 50-320, Metropolitan Edison Co., March 18, 1981.

3.

Table 11-1, Volume II, Part 2, "Three Mile Island, A Report to the Commissioners and to the Public," NRC Special Inquiry Group, January 1980.

4.

Final Programmatic Environmental Impact Statement related to Decontamination and Disposal of Radioactive Wastes Resulting from March 28, 1979, Accident, Three Mile Island Nuclear Station, Unit 2, NUREG-0683, March 1981.

5.

Final Supplement to the Final Environmental Statement, Three Mile Island Nuclear Station, Unit 2, NUREG-Oll2, December 1976.

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