ML20027C640
| ML20027C640 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 09/24/1982 |
| From: | Case E Office of Nuclear Reactor Regulation |
| To: | GENERAL PUBLIC UTILITIES CORP. |
| Shared Package | |
| ML20027C639 | List: |
| References | |
| NUDOCS 8210260538 | |
| Download: ML20027C640 (4) | |
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UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION
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In the Matter of
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Docket No. 50-320 OLA METROPOLITAN EDISON COMPANY, et, al.))
(Three Mile Island Nuclear Station, ))
Unit 2)
AMENDMENT OF ORDER I.
GPU Nuclear Corporation, Metropolitan Edison Company, Jersey Central Power and Light Company and Pennsylvania Electric Company (collectively, th are the holders of Facility Operating License No. OPR-73, which had author operation of the Three Mile Island Nuclear Station, Unit 2 (TMI-2) at power The facility, which is located in levels up to 2772 megawatts thermal.
Londonderry Township, Dauphin County, Pennsylvania, is a pressurized water reactor previously used for the commercial generation of electricity.
20, 1979, the Licensee's By Order for Modification of License, dated July authority to operate the facility was suspended and the Licensee's authority was limited to maintenance of the facility in the present shutdown cooling By further Order of the Director, Office of Nuclear Reactor i
a new set of formal license requirements was Regulation, dated February 11, 1980, imposed to reflect the post-accident condition of the facility and to as t
continued maintenance of the current safe, stable, long-term cooling co f
of the facility (45 Fed. Reg,11282).
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t Although these requirements were imposed on the licensee by an;0rder of the Director of Nuclear Reactor Regulation,, dated February 11,1980,..
the TM D P
.,s license has not been formally amended.
Tt[e requirements are reflected'in'
.s the proposed Recovery Mode Technical Specifications presently pendio{'before the Atomic Safety and Licensing Board. Hereaf ter in this A'n.egdment';of dr'd'cr,
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- ye the requirements in question {re identified by the applicable proposed Technical Speci fication.
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j By letters dated April 19, 1982 and July 7,1982, the licens,e requested changes e
3 to the proposed Technical Specifications, Appendix A for Thre'e Mile Island, The licensee has requested NRC staff approval foh the: separation Unit 2 (TMI-2).
.r of the Auxiliary Byilding and Fuel Handling Building Air C}i3 nun Exhaust System Technical Specifications. The proposed change would provide separate Technical e
a Specifications for, Auxiljary Building and Fuel Handling Buf1 ding Air Cleanup
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Presently section 3.9.12 contains the. combined Fuel Handlf ng/
Exhaust Systems.
The existing Auxiliary Building Air Cleanup Systems Technical Spacification.
N..v proposed Technical Specification coptained in section 3.9.12 does not accurately 3
reflect the existing design of eit er the. Fuel Handling Building or the Auxiliary Building Air Exhaust 5ystem.
The' staff agrees with the licensee that the changaL
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would more clearly define which equipment needs to4 be operating to provide adequate ventilation capability for the Fuel Handling and Auxiliar[PyQdings.
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The staff has reviewed the design of the Air Exha7st Systems for both the f
Auxiliary and Fuel Handling Buil' dings as' presented in the licensee's Final 2
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Safety Analysis Report (FSAR) and, fi.11s that the @oposed changes do not c3
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The c conflict with operational or design characteristics of either' system.'
changes would require corrective actions within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> if the ventilation t
I' flowrate is not within acceptable limits and suspension of operations involving the movement of liquid and gaseous radwastes in the affected building if the Air It Exhaust System is not returned to an operable condition within four hours.
should also be noted that the changes provide a definition of liquids that would be considered as liquid radioactive waste which would not be moved in the event of loss of the air cleanup system in the building.
This definition is necessary in order not to interfere with required makeup to the reactor coolant system The staff finds that the regardless of the status of the Air Exhaust Systems.
proposed amendment of section 3.9.12 of the proposed Technical Specifications is acceptable.
The staff's safety assessment of this matter is set forth in the concurrently issued Safety Evaluation.
This evaluation concluded, in material part, that the modification does not involve a significant hazards consideration and that there is reasonable assurance that the health and safety Prior of the public will not be endangered by operation in the modified manner.
public notice of this Amendment of Order is therefore not required and the action is effective upon issuance.
It was further determined that the modification 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 deter-mination, it was concluded that the instant action is insignificant from the standpoint of environmental impact and, pursuant to 10 CFR @51.5 (d)(4), that an environmental impact statement or environmental impact appraisal need not be prepared herewith.
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III.
Accordingly, pursuant to the Atomic Energy Act of 1954, as amended, the Director's Order of February 11, 1980, is hereby revised to incorporate the For deletions, additions, and modifications set forth in Attachment A hereto.
further details with respect to this action, see (1) Letter to B. Snyder, USNRC, from R. Arnold, Met Ed/GPU, Technical Specification Change Request No. 35 dated April 19, 1982, (2) Amendment to Technical Specification Change Request No. 35, dated July 7,1982, and (3) The Director's Order of February 11, 1980.
All of the above documents are available for inspection at the Commission's Public Document Room,1717 H Street, N.W., Washington, D.C., 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 l0 L
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Acting Director Edson G. Case, lear Reactor Regulation Office of Nuc Effective Date:
September 24, 1982 Dated at Bethesda, Maryland m