ML20236N414
| ML20236N414 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 11/09/1987 |
| From: | Standerfer F GENERAL PUBLIC UTILITIES CORP. |
| To: | |
| Shared Package | |
| ML20236N402 | List: |
| References | |
| NUDOCS 8711160152 | |
| Download: ML20236N414 (4) | |
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METROPOLITAN EDISON' COMPANY h:
JERSEY' CENTRAL ~ POWER AND LIGHT COMPANY PENNSYLVANIA ELECTRIC COMPANY l
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.GPU NUCLEAR' l
THREE MILE ISLAND NUCLEAR STATION UNIT.II 4
i Operating License No. DPR-73
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Docket No. 50-320 l'
Technical Specification Change Request No. 53 - Revision 2 i
l-This Technical Specification Change Request is submitted in support of.
j Licensee's' request to change Operating License No. DPR-73.for Three Mile.
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. Island Nuclear Station Unit 2.
As a part of this. request, proposed replacement pages for Appendix A are also included.-
1 GPU NUCLEAR l
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' Director, TMI-2.
7 Sworn and subscribed to me this day of N //gN4h-4.,1987. ;
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UNITED STATES OF AMERICA
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~ UCLEAR REGULATORY COMMISSION N
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~This is to certify that a copy of Revision 2 to Technical Specification Change Request No. 53 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. Jay H. Kopp, Chairman Mr. Fred Rice, Chairman Board of Supervisors of Board of County Commissioners Londonderry Township of Dauphin County R. D. #1, Geyers Church Road Dauphin County Court House Middletcwn, Pennsylvania 17057 riocrisburg, Pennsylvania 17120 Mr. Thomas M. Gerusky, Director Bureau of Radiation Protection PA Dept. of Environmental Resources P.O. Box 2063 Harrisburg, PA 17120 GPU NUCLEAR
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Director, TMI-2
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L Three Mile Island Nuclear Station, Unit 2 (TMI-2)
Operating License No. DPR-73 Docket No. 50-320 Technical Specification Change Request (TSCR) No. 53 - Revision 2 The licensee requests that the attached changed pages (i.e, pages 3.9-5 and
-3/4.9-1) replace the corresponding pages previously submitted for NRC review and approval via GPU Nuclear lotters 4410-87-L-0042 dated April 23,1987, and 4410-87-L-0152 dated October 26, 1987.
Purpose of Chang The above referenced CPU Nuclear letters submitted Revisions 0 and 1, respectively, of TSCR 53.
Comments from the NRC TMICPD were received via letter NRC/TMI-87-0073 dated September 25,198/. The referenced GPU Nuclear letter of October 26, 1987, responded to five (5) of the six (6) NRC comments. The attachment provides GPU Nuclear's response to the remaining NRC comment and the Safety Evaluation Justifying Change for the proposed revision.
No Significant Hazards Determination 10 CFR paragraph 50.92 provides the criteria which tne Commission uses to evaluate a No Significant Hazards consideration.
10 CFR 50.92 states that an amendment to a facility license involves No Significant Hazards if operation of the facility in accordance with the proposed amendment would not:
1.
Involve a significant increase in the probability or consequences of an accident previously evaluated; or 2.
Create the possibility of a new or different kind of accident from any accident previously evaluated; or 3.
Involve a significant reduction in a margin of safety.
The proposed change is within the scope of the No Significant Hazards Determinate analysis originally submitted in TSC9 53 via GPU Nuclear letter 4410-87-L-0152, dated October 26, 1987. However, each of the above criteria is evaluated below specifically concerning this proposed change, o
Does the change involve a significant increase in the probability or consequences of an accident previously evaluated?
In response to an NRC Comment, the proposed change deletes the reference to " gaseous radioactive waste" and adds a reference to solid radioactive wastes in the action statements for Specifications 3.9.12.1 and 3.9.12.2.'
Additionally, the proposed change provides quantitative criteria for the suspension of movement of liquid and solid radioactive waste in.either the Auxiliary Building or Fuel Handling Building (FHB) whenever the associated air cleanup exhaust system is inoperable for a period greater than four (4) hours.
The deletion of gaseous radioactive wastes from the above referenced action statements reflects that the gaseous radioactive source term has essentially been eliminated from THI-2.
The addition of a restriction on solid radioactive wastes is conservative in that it reduces the probability for an unfiltered release to the environment.
A quantitative criteria for the suspension of liquid and solid radioactive handling when a ventilation system is not operable has been established at one-half of the instantaneous release rate limit for gaseous effluents specified by the Appendix B Technical Specifications
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(Tech. Specs.). The basis for the instantaneous release rate in the Appendix B Tech. Specs. (i.e., 0.3 UCi/cc for particulate with half lives greater than 8 days) is to ensure that off-site releases will be within the limits of 10 CFR 20 and 10 CFR 50 Appendix I.
Calculations were performed based on credible accident scenarios associated with the drop of a package containing solid defueling waste (e.g., trash) and the spill of Reactor Coolant System (RCS) and Reactor Building (RB) basement water. These calculations determine that the resultant release rate for the solid waste and RCS grade water are within the proposed criteria.
Similarly, the movement of RB basement water would be prohibited in the Auxiliary and Fuel Handling Building when the respective ventilation system is inoperable based on these calcW.ations.
These releases are much less than that associated with the drop of a defueling canister analyzed in the Defueling Safety Evaluation Report, Revision 10 dated May 18, 1987.
Thus, GPU Nuclear concludes that the proposed change does not involve a significant increase in the probability or consequence of an accident previously evaluated, o
Does the proposed change create the possibility of a new or different kind of accident from any accident previously evaluated?
l The accident scenarios analyzed involve either a drop of a package containing solid radioactive waste or leakage of a radioactive licuid from a system. Both types of accidents have been analyzed in numerous other documents submitted by GPU Nuclear, o
Does the proposed change involve a reduction in a margin safety?
The proposed change restricts the movement of liquid and solid radioactive wastes during periods when a ventilation system is inoperable such that in the event of a release, the criteria for an instantaneous release as specified in Appendix B Tech. Specs, would not be exceeded.
Thus, the proposed change does not involve a reduction in a margin of safety.
From the above review, it is concluded that the proposed change involves No Significant Hazards Consideration.
Amendment Class An application fee, per the requirements for 10 CFR 170, was previously submitted for TSCR 53 and Recovery Operations Plan Change Request 38.
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