ML19290A375
| ML19290A375 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 06/06/1975 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML19290A373 | List: |
| References | |
| NUDOCS 7911060614 | |
| Download: ML19290A375 (2) | |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION W ASHINGToN. o. C.
20555 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION SUPPORTING AMENDffENT NO. 7 TO FACILITY OPERATING LICENSE NO. DPR-50 (CHANGE NO. 7 TO THE TECHNICAL SPECIFICATIONS)
METROPOLITAN EDISON CCMPANY THREE MILE ISLAND NUCLEAR STATION, UNIT 1 Introduction On April 16, 1975, Metropolitan Edison Company (Meted) made application to amend the operating license for Three Mile Island Unit 1.
The proposed amendment changes Technical Specifications 3.1.3.5 and 3.5.2.5 which provide for revised control rod withdrawal limits. These revised limits are required to assure that the maximum hypothetical, ejected control rod reactivity worth will not exceed the values contained in Technical Specification 3.5.2.3; these values of rod worth are 0.65t, 2K/K and 1.00's AK/K for conditions of full power and hot zero power, respectively.
Discussion By Ictter dated March 31, 1975, the Nuclear Regulatory Co: mission (NRC) informed Meted that deficiencies had been identified in the ejected rod worth calculation on which the control rod withdrawal limits for Three Mile Island Unit I had been based. This letter further stated that following control rod interchange *, potential ejected control rods might exist which would violate the limits specified in Technical Specification 3.5.2.3.
On April 9, 1975, Meted submitted a Nonroutine 30 Day Report 74-04 which confirmed the existence of a deficiency in the control rod withdrawal limits.
Evaluation Meted has provided additional information via a letter' dated May 29, 1975, in response to our request dated May 7, 1975. Meted indicated that their proposed changes in Technical Specifications provide control rod withdrawal
' Control rod interchange is x process by which the control rods are re-sequenced for operation during the latter part of the fuel cycle.
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i 2-limits which assure that the ejected control red worth limits, as specified in Technical Specification 3.5.2.3, will not be violated. Moreover, by adoption of the revised control rod withdrawal limits, additional shutdown margin is provided in the event of the hypothetical ejected control rod accident.
With regard to that portion of the revised control rod withdrawal limit curves in which ECCS considerations are limiting, above 82.5% of rated full power, the restrictions provided are at least as conservative as those presently provided for Three Mile Island Unit 1.
Therefore, no reduction in operating margin relative to the ECCS limits will result upon adoption of the revised control rod withdrawal limits.
Conclusion We have concluded, based on the considerations discussed above, that:
(1) there is reasonable assurance that the health and safety of the public will not be endnagered by operation in the proposed manner, and (2) 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.
1975 Dated:
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UNITED STATES NUCLE!.R REGULATORY CCSO!ISSION DOCKET NO. 50-289 METROPOLITA': EDISON CC:'P A'?Y JERSEY CE: TRAL PC'.CR X;D LIGliT COMPA';Y PENNSYLVA';IA ELECTRIC COMPA'iY NOTICE OF ISSUX;CE OF APENDMENT TO FACILITY OPERATING LICENSE Notice is hereby given that the U. S. Nuclear Regulatory Co= mission (the Commission) has issued Amendment No. 7 to Facility Operating License No. DPR-50 issued to Metropolitan Edison Company, Jersey Central Power and Light Company and Pennsylvania Electric Ccmpany which revised Technical Specifications for operation of the Three Mile Island :uclear Station, Unit 1, located in Dauphin County, Pennsylvania. The acendment is effective as of its date of issuance.
The amendment modifies the Technical Specifications to incorporate revised Rod Withdrawal Limit Curves that decrease the worth (calculated neutron absorbing capability) of the worst hypothetical ejected control rod.
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. The application for the amendment co= plies 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 appropriate findings as required by the Act and the Commission's rules and regulations' in 10 CFR Chapter I, which are set forth in the license amend =ent.
Notice of Proposed Issuance of A=endment to Facility Operating License in
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connection with this action was published in the FEDERAI. REGISTER on May 5, 19 75 (40 F. R. 19546). No request for a hearing er petition for leave to intervene was filed following notice of the prcposed action.
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_2-For further details with respect to this action, see (1) the application for amendment dated April 16, 1975, and supple =ent dated May 29, 1975, (2) Amendment No. 7 to License No. DPR-50, with Change No. 7 and (3) the Commission's related' Safety Evaluation. All of these ite=s 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 Cocmission, Washington, D. C. 20555, Attention:
Director, Division of Reactor Licensing.
Dated at Bethesda, Maryland, this 6th day of June,197S.
IDR THE NUCLEAR REGULATORY COM:!ISSION George Le Chief Operating Reactors Branch No. 3
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