ML19262A428
| ML19262A428 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 08/16/1978 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML19262A422 | List: |
| References | |
| NUDOCS 7910290521 | |
| Download: ML19262A428 (2) | |
Text
7 UNITED STATES 4
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SAFETY EVALUATION BY THE OFFICE OF ?!UCLEAR REACTOR REGULATIO !
FIENDMENT NO. 42 TO FACILITY OPERATING LICENSE NO. DPR-50 METROPOLITAt1 EDIS0N CCt' patly JERSEY CENTRAL PO'c'ER AND, LIGHT C0".PANY PENNSYLVANIA ELECTRIC C0i'PANY THREE MILE ISLAND NUCLEAR STATION, UNIT NO. 1 DOCKET NO. 50-289 Introduction By letter dated February 3,1978, as supplemented by letters dated April 18, and July 7,1978, Metropolitan Edison Company (Met Ed) requested changes to the Technical Specifications appended to Facility Operating License No. OPR-50 for Three Mile Island Nuclear Station, Unit No. 1 (Tl11-1).
The proposed amendment would change the method of surveillance testing of the reactor internal vent valves.
Evaluation The change proposed by Met Ed would specify a vertical force of 400 lbs. to be used in the surveillance testing of the reactor internal vent valves. Met Ed states this force is equivalent to an opening differential pressure for the reactor internal vent valves of 1.0 psid.
The present Technical Specification requires manual actuation of the vent valves to verify that the valve begins to open from the fully closed position with a force equivalent to 1 15 psid and is fully open with a force equivalent to 1 30 psid.
Met Ed has shown that: (1) the required pressure differential necessary to hold the vent valves full open is no more than 1.0 psid; (2) a force of 3400 lbs. aDolied vertically upward is the force equivalent of a pressure differential of 1.0 psid; (3) a time lag of 0.2 seconds will occur between onset of the limiting Loss of Cooling Accident (LOCA) and attainment of the full open position of the valve if the 1.0 psid force were required; and (4) the 0.2 second time delay has I
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2-only a small effect (i.e., <30F) on the peak cladding temperature (PCT) during the limiting LOCA; The present calculated PCT is 21460F. The additional 3oF temperature rise will increase the PCT to 21490F which does not cause the limiting LOCA PCT to exceed any of the 10 CFR 50.46 criteria, nor does this change affect which LOCA break is limiting.
We have reviewed the calculations which demonstrate the equivalence of a 400 lb. force applied vertically to the valve and a pressure differential of 1.0 psid. Based on this review, the information supplied by Met Ed, and the continued surveillance requirements on the reactor internal vent valves, we find this change to be acceptable.
Environmental Consideration We have determined that the amendment does not authorize a change in effluent types or total amounts nor an increase 'n powe-level and will not result in any significant environmental impact.
Having made this determination, we have further concluded that the omandment involves an action which is insignificant from the standpoint of environmental impact and, pursuant to 10 CFR 551.5(d)(4), that an environmental impact statement, or negat.ive declaration and environ-mental impact appraisal need not be prepared i, connection with the issuance of this amendment.
Conclusion We have concluded, based on the considerations discussed above, that:
(1) because the amendment does not involve a significant increase in the probability or consequences of accidents previously considered and does not involve a significant decrease in a safety margin, the amendment does not involve a significant hazards consideration, (2) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, and (3) such activities will be conducted in compliance with the Commission's regulations and the issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public.
Dated: August 16, 1978 8
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..e 7590-01 UNITED STATES NUCLEAR REGULATORY C0f' MISSION DOCKET N0. 50-289 METROPOLITAN EDISON COMPANY JERSEY CENTRAL POWER AND LIGHT COMPANY PENNSYLVANIA ELECTRIC COMPANY NOTICE OF ISSUANCE OF AMEND!iENT TO FACILITY OPERATING LICENSE The U. S. Nuclear Regulatory Commission (the Commission) has issued Amendment No. 42 to Facility Operating License No. DPR-50, issued to Metropolitan Edison Company, Jersey Central Power and Light Company and Pennsylvania Electric Company (the licensees), which revised Technical Specifications for operation of the Three Mile Island Nuclear Station, Unit No. 1 (the facility) located in Dauphin County, Pennsylvania. The amendment is effective as of its date of i
issuance.
The amendment revises the Technical Specifications to change the method of surveillance testing of the reactor internal vent valves.
The application for the amendment complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations.
The Commission has made apprcariat.e findings as required by the Act and the Comission's rules and regulations in 10 CFR Chapter I, which are set forth in the license amendment.
Prior public notice of this amendment was not required since the amendment does not involve a 4b significant hazards consideration.
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7590-01.
The Commission has determined that the issuance of this amendment will not result in any significant environmental impact and that pursuant to 10 CFR 551.5(d)(4) an environmental impact statement, or negative declaration and environmental impact appraisal need not be prepared in connection with issuance of this amendment.
For further details with respect to this action, see (1) the application for amendment dated February 3,1978, as supplemented April 18, and July 7,1978,(2) Amendment No. 42 to License No. DPR-50, and (3) the Commission's related Safety Evaluation.
All of these items are available for public inspection at the Commission's Public Document Room, 1717 H Street, N.W., Washington, D. C. and at the Government Publications Section, State Library of Pennsylvania, Box 1601 (Education Building),Harrisburg, Pennsylvania. A copy of items (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 16th day of August 1978.
FOR THE NUCLEAR REGULATORY COMT1ISSION h
))h JcY Robert W. Reid, Chief Operating Reactors Branch #4 Division of Operating Reactors 1484 178