ML19325C547
| ML19325C547 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 10/10/1989 |
| From: | Roche M GENERAL PUBLIC UTILITIES CORP. |
| To: | |
| Shared Package | |
| ML19325C544 | List: |
| References | |
| NUDOCS 8910170036 | |
| Download: ML19325C547 (4) | |
Text
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ETROPC1.ITAN EDISON COMPANY JERSEY CENTRAL POWER AND LIGHT COMPANY l
PENNSYLVANIA El.ECTRIC COMPANY GPU NUC1. EAR THREE MILE ISLAND NUCLEAR STATION UNIT II i
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Operating License No. OPR-73 Docket No. 50-320 Technical Specification Change Reouest No. 66 The Technical Specification Change Reouest is submitted in support of i.
Licensee's reovest to change Operating License No. DPR-73 for Three Mile Island Nuclear Station Unit 2.
As a part of this request, proposed replacement pages for Appendix B are also incluoed.
GPU NUCl. EAR t
i By Nb Director, THI-2 Sworn and subscribed to me this lO dayof(
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, 1989.
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UNITED STATES OF AMERICA l-NUQ. EAR REGu.ATORY COMMISSION i
1 IN THE MATTER OF j
DOCKET NO. 50-320 LICENSE NO. DPR-73 GPU NUQ. EAR This is to certify that a copy of Technical Specification Change Reguest No. 66 to Operating License DPR-73 for Three Mile Island Nuclear Station Unit 2 has been' filed with the U.S. Nuclear Regulatory Commission and served to the chief executives of 1) Londonderry Township, Dauphin County, Pennsylvania; 2) Dauphin County, Pennsylvania; and 3) the designated official of the Commonwealth of Pennsylvania by deposit in the United States mail, addressed as follows:
)
Mr. Say H. Kopp, Chairman Ms. Sally Klein, Chairperson Board of Supervisors of Board of County Commissioners Londonderry Township -
of Dauphin County R. D. fl, Geyers Church Road Dauphin County Court House Middletown, PA 17057 Harrisburg, PA 17120 j
Mr. Thomas M. Gerusky, Director Bureau of Radiation Protection i
PA Dept. of Environmental Resources P.O. Box 2063 t
Harrisburg, PA 17120 4
GPU NUQ. EAR b
By Director, TMI-2 4
October 10. 1989 Date i
.:t 4
pN Three Mila Island Nuclear Station, Unit 2 (TMI-2)
Oper: ting License DPR-73 i
Docket No. 50-320 i
Technical Specification Change Reouest (TSCR) No. 66 The Licensee nouests that the attached changed pages of the Appendix B Technical Specification (Tech. Specs.) (i.e., pages 2-4 and 2-11) replace the l
corresponding pages in the Appendix B Tech. Specs.
~
Description of Change The Appendix B Tech. Specs. Ieoui m ments related to radioactive liould and gaseous' waste sampling and analysis of Strontium-89 (Sr-89) are being removed.
t Reason for Change The Appendix B Tech. Specs, reouire sampling and analysis for Sr-89 in both liould and gaseous radioactive waste.
Sr-89 is produced as a result of nuclear fission during reactor operation and has a 50.52 day half-life.
The TMI-2 reactor has been shut down since the March 28, 1979, accident.
Therefore, the Sr-89 generation has ceased and the SI-89 concentration present
~;
. at that time has decayed to less than detectable levels.
In summary, there no 21onger exists a need to monitor' Sr-89 and the Tech. Spec. reouirements can be deleted.
Safety Evaluation Justifying Change r
Sr-89 has decayed since the March 28, 1979, accident to the extent that tnis radionuclide is no longer present in measurable cuantities. Therefore, it is no longer necessary to monitor this particular radionuclide.' We will continue to monitor radioactive 11ould and gaseous wastes in accordance with Tables 2.3-1 and 2.3-2, however, which will ensure that the health and safety of the public is not jeopardized, i
No Significant Hazards Consideration
-10 T R 50.92 provides the criteria which the Commission uses to evaluate a No Significant Hazards Consideration. 10 WR 50.92 states that an amendment to a facility license involves No Significant Hazards if operation of the facility j
in accordance with the proposed amendment would not:
1.
Involve a significant increase in the probability or consecuences of an accident previously evaluated, or l.
2.
Create the possibility of a new or dif ferent kind of accident from any accident previously evaluated, or Involve a significant reduction in a margin of safety.
3.
j.
The proposed change to delete the sampling and analysis requirements for Sr-89 in both liould and gaseous radioactive waste from the THI-2 Recovery Technical Specifications has no impact on the safety of the evolutions occurring at
~TMI-2.
Since Sr-89 has a 50.52 day half-life and its production ceased on March 28, 1979, the cuantity of Sr-89 present at that time has decJyed to less i
than detectable levels over the more thin 75 half-lives.
=
+.,v.,
W Therefore, the proposed changes do not 1.
Involve a significant increase in the probability or consecuences of an accident previously evaluated. The deletion of St-09 sampling and
[
.nnalysis reouirements has no effect on the probability of an accident.
The consecuences of an accident cannot be increased by a radionuclide that is present -in less than detectable levels.
2.
Create the possibility of a new or different kind of accident from any accident previously evaluated. The deletion of St-89 sampling and analysis reouirements has no potential to create a new or different kind of accident.
3.
Involve a significant reduction in a margin of safety. There is no impact on any margin of safety since the cuantity of St-89 is at less than detectable levels.
Based on the above analysis, it is concluded that the proposed changes involve -
no significant hazards considerations as defined by 10 CFR 50.92.
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