ML19290A335
| ML19290A335 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 05/12/1976 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML19290A331 | List: |
| References | |
| NUDOCS 7911060576 | |
| Download: ML19290A335 (3) | |
Text
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UNITED STATES O,
.i NUCLEAR REGULATORY COMMISSION 1
WASHINGTON, D. C. 20555
%..dj-SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION SUPPORTING AMENDSENT NO.16 TO FACILITY OPERATING LICENSE NO. DPR-50 SETROPOLITAN EDISON COMPANY JERSEY CENTRAL POWER A'iD LIGHT COMPANY PENNSYLVANIA ELECTRIC COMPANY THREE MILE ISLAND NUCLEAR STATION, UNIT 1 DOCKET NO. 50-289 Introduction By letter dated April 15, 1976, Metropolitan Edison Company (the licensee) prop.osed a license amendment to the Three Mile Island Nuclear Station Unit No. 1 Operating License No. DPR-50 to permit the use of type "C"
tests, as. defined in 10 CFR 50 Appendix J, to determine the leakage of valves served by the Fluid Block System. Although this change was submitted by the licensee as Amendment No. 1 to his previous Change Request No. 22, dated October 29, 1975, which is still under our generic review, the licensee requested that his change proposed April 15, 1976, be acted upon in a time'ly manner. This change will allow the licensee the option of local leakage testing of the valves, served by the Fluid Block System, with air / nitrogen when excessive maintenance is required to satisfy the Fluid Block System inventory require =ent.
Evaluation Appendix J to 10 CFR 50 requires, in part, that all isolation valves be locally leak tested with air (Type C test), except for those valves which are sealed with the fluid from a seal system. Seal systens must be leak tested to demonstrate a sufficient fluid inventory to assure the sealing function for at least thirty (30) days if credit is to be taken for the use of the seal system. This exception recognizes that seal systems can effectively eliminate the leakage through specific isolation valves, and therefore the leakage through these valves need not be considered when determining a combined local leakage rate.
1555 273 7911060 $76 The proposed change to the Technical Specifications for the Three >dle Island Nuclear Station would, as alternatives, allow the licensee to either (a) leak test the Fluid Block Syste= (seal water systc=),and demonstrate a thirty day fluid inventory, or (b) locally leak test all of the isolation valves served by the Fluid Block System with air / nitrogen and demonstrate that the' combined local leakage, including the leakage of the isolation valves served by the Fluid Block System, is below the allowable limit.
The proposed change to the Technical Specifications does not change the design basis for containment leakage. The only effect of the proposed a=and:ent is to require the licensee to include the leakage of isolation valves served by the Fluid Block System in determining the co=bined local leakage rate when credit is not taken for the Fluid Block System.
The proposed change to the Technical Specifications for the Three Mila Island Nuclear Station doe; not increase either the probability of occurrence or the consequences of an accident. Since the allowable leakage limits, both integrated (.75La) and local (.6La), have not been changed, the consequences of an accident re=ain unchanged from those evaluated in the Final Safety Analysis Report.
In additicn type "C" testing of valves served by the Fluid Block System is in agreement with the requirements of Appendix J.
Therefore, we find the Technical Specification revision acceptable.
'We have determined that the amend:ent 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 cade this determination, we have further concluded that the amendment involves an action which is insignificant from the standpoint of environmental i= pact and pursuant to 10 CFR 951.5(d)(4) that an environmental impact appraisal need not be prepared in connection with the issuance of this amend:ent.
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Conclusion We have concluded, based on the considerations discussed above, that:
(1) because the. change does not involve a significant increase in the probability or consequences of accidents prqviously considered and does not involve a significant decrease in a safety margin, the change does not involve a significant hazards con, sideration, (2),there is reasonable, assurance that the health and safety of the public will not be endangered by operation Jn the proposed =anner, and (3) such activities.will be conducted in compliance with the Commission's regulations and the issuance of this amend:ent will not be ini=1 cal to the coc=on defense and security or to the health and safety of the public.
Dated: gprlarm 1555 275 e
UNITED ' STATES NUCLEAR REGULATORY COS}!ISS105 DCCKET :;0. 50-289 METROPOLITAN EDISON COMPANY JERSEY CENTRAL P0t?ER AND LIGHT COMPANY PENNSYLVANIA ELECTRIC COMPANY NOTICE OF ISSUANCE OF. AMENDMENT TO FACILI"Y OPERATING LICENSE Notice is hereby given that the U. S. Nuclear Regulatory Co=cission (the Commission) has issued A=endment No. 16 to Facility Operating License No. DPR-50 issued to Metropolitan Edison Company, Jersey Central Power and Light Company, and Pennsylvania Electric Company which revised Technical Specifications for operation of the Three Mile Island Nuclear Station, Unit No. 1, located in Dauphin County, Pennsylvania. The amendment is effective as of its date of issuance.
This amendment modifies the Technical Specifications to per=it the use of type "C" tests, as defined in 10 CFP. 50 Appendix J, to determine the leakage of valves served by the Fluid Block System.
The application for the amend =ent complies with the standards and requirecents of the Atomic Energy Act of 1954, as amended (the Act),
a.nd the Co= mission's rules and regulations. The Coc=ission has cade appropriate findings as required by the Act and the Co==ission's rules and regulations in 10 CFR Chapter I, which are set forth in the license amendment. Prior public notice of this amendment is not required since the amendment does not involve a significant hazards consideration.
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The Co==ission has determined that the issuance of this a=end=ent will not result in any significant environmental i= pact and that pursuant to 10 CFR 951.5(d)(4) an environ = ental state =ent, negative declaration or environ = ental i= pact appraisal need not be prepared in connection with issuance of this a=end=ent.
For further details with respect to this action, see (1) the applicati.on for amend =ent dated' April 15, 1976, (2) Amend =ent No.16 to License No. DPR-50, and (3) the Co= mission's related Safety Evaluation.
All of these ite=s are available for public inspection at the Coc=ission's Public Docu=ent Room, 1717 H Street, N.W., Washington, D.C., and at the Govern =ent Publications Section, State Library of Pennsylvania, Box 1601 (Education Building), Harrisburg, Pennsylvania.
A copy of ite=s (2) and (3). may be obtained upon request addressed to the U. S. Nuclear Regulatory Commission, Washington, D.C.
- 20555, Attention: Director, Division of Operating Reactors.
. Dated at Bethesda, Maryland, this 12th day of May 1976.
FOR THE NUCLEAR REGULATORY COMh1SSION h
Vernon L. Rooney, Ac ing Chief Operating Reactors ranch #4 Division of Operating Reactors 1555 277
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