ML20031A882
| ML20031A882 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 09/23/1981 |
| From: | Harold Denton Office of Nuclear Reactor Regulation |
| To: | METROPOLITAN EDISON CO. |
| Shared Package | |
| ML20031A879 | List: |
| References | |
| ISSUANCES-OLA, NUDOCS 8109280344 | |
| Download: ML20031A882 (4) | |
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7590-01 UNITED STATES OF /J1 ERICA NUCLEAR REGULATORY C0!!l41SSION In the liatter of
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fiETROPOLITAN EDIS0N C0f!PANY, et al.
Docket No. 50-320 OLA (Three lille Island Nuclear Station, Unit 2)
)
liODIFICATION OF ORDER I.
lietropolitan Edison Company, Jersey Central Power and Light Company and Pennsylvania Electric Company (collectively, the Licensee) are the holders of Facility Operating License No. DPR-73, which had authorized operation of the Three Mile Island Nuclear Station, Unit 2 (TMI-2) at power levels up to 2772 degawatts thermal. The facility, which is located in Londonderry Township, Dauphin County, Pennsylvania, is a pressurized water reactor previously used for the commercial generation of el ectricity.
By Order of the Director, Office of Nuclear Reactor Regulation, dated February 11, 1980, a new set of license requirements was imposed to reflect the condition of the facility following the accident of !1 arch 28, 1979, and to assure the continued maintenance of the current safe, stable, long-term cooling condition of the facility. 45 Fed. Reg. 11282 (Februr y 20,1980).
II.
The Licensee has undertaken containment entries as parc of its naintenance ind recovery effort at TMI-2.
In order to facilitate certain (8109200344810924 9 83 E PDR ADOCK 05000320 h0 xG PDR
7590-01 activities which it needs to conduct within containment, the Licensee applied on August 20, 1981, for approval of a change to the requirement set forth in Technical Specification 3.6.1.3 that it maintain at least one door in each of its containment air locks closed at all times.
The change proposed by the Licensee would pennit both doors of the containn.ent air locks to be open simultaneously when necessary to pe'rmit the passage of tools and equin cat, provided that these operations are undertaken in accordance with procedures approved pursuant to the requirements reflected in Technical Specification 6.8.2.
The NRC Staff has prepared a Safety Evaluation of the proposed change in which it has found that the change will give the Licensee needed additional flexibility in the design of tools and equipment for the conduct of activities inside containment and will reduce the exposure of workers by lessening the time spent inside containnent assembling such tools and equipment.
Based upon its Evaluation, the Staff has concluded that:
(1) conditions that the Staff will require to be incorporated in the implementing procedures will assure that no significant releases 'f radioactive materials will occur in the event of an
- accident, (2) the proposed change will not result in a significant increase in the probability or consequences of accidents previously considered, nor a significant reduction in a margin of safety, and does not, therefore, involve a significant hazards consideration, (3) there is reasonable assurance that the activities that would be authorized under the changed Technical Specification can be
7590-01 conducted without endangering the health and safety of the public, and in compliance with the Commission's regulations, and (4) approval of the proposed change will not be inimical to the common d2fense and security or to the public health and safety.
The Staff has further concluded that approval of the proposed change 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.
In light of this determination, it has concluded, pursuant to 10 C.F.R. G 51.5(d)(4), that the approval of this change does not require the preparation of an environmental impact statement or negative declaration and environmental impact appraisal.
III.
Accordingly, pursuant te the Atomic Energy Act cf 1954, as amended, the Director's Order of February 11, 1980, is hereby nodified to incorporate the requested change to Technical Specification 3.6.1.3.
The revised Specification is set forth in Attachnent A hereto. This action does not amend Operating License No. DPR-73 to incorporate revised l
Technical Specification 3.6.1.3 therein.
The question of whether to amend the License to incorporate the Recovery Mode Technical Specifications, of which Technical Specification 3.6.1.3 is a part, is presently pending before an Atomic Safety and Licensing Board.
The Licensee is, however, authorized to act in accordance with the revised j
requirements reflected in Technical Specification 3.6.1.3.
For further details with respect to this action, see (1) Letter to B. Snyder, USNRC, from G. K. Hovey, Met. Ed/GPU, Technical Specification t
Change Request No. 29, dated August 20,1981,(LL2-81-0192);(2) Letter l
7590-01
. to G. K. Hovey, Met. Ed/GPU, fran B. J. 'nyder, USi;RC, dated o
September 23, 1981: and (3) the Director's Order of February 11, 1980.
All of the above dor.uments are available fo'F inspection at the Commission's Public Document Room,1717 H Street, NW, Washington, DC, and at the Commission's Local Public Document Room at the State Library of Pennsylvania, Government Publications Section, Education Building, Commonwealth and Walnut Streets, Harrisburg, Pennsylvania 17126.
FOR THE NUCLEAR REGULATORY COMMISSION
/2 MNb k
Harold R. Denton, Director Office of Nuclear Reactor Regulation Effective date:
September 23. 1981 Dated at Bethesda, Maryland, this 23 day of September, 1981.
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