ML19290A314

From kanterella
Jump to navigation Jump to search
Safety Evaluation Supporting Amend 19 to DPR-50
ML19290A314
Person / Time
Site: Crane Constellation icon.png
Issue date: 08/23/1976
From:
Office of Nuclear Reactor Regulation
To:
Shared Package
ML19290A311 List:
References
NUDOCS 7911060555
Download: ML19290A314 (2)


Text

/

\\

UNITED $T ATES

[.,

NUCLEAR REGULATORY COMMISSION

'I WASHINGTON, D. C. 20555 j%d$f1

\\%,,,',, /

SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION SUPPORTING AMENDMENT NO.19 TO FACILITY OPERATING LICENSE NO. DPR-50 METROPOLITAN EDISON COMPANY JERSEY CENTRAL POWER At4D LIGHT COMPANY PENNSYLVANIA ELECTRIC CCMPANY THREE MILE ISLAND NUCLEAR STATION, UNIT NO. 1 DOCKET N0. 50-289 Introduction By letter dated July 12, 1976 Metropolitan Edison Company (Meted) requested a change in the Technical Specifications of License No.

DPR-50 for the Three Mile Island Nuclear Station. Unit No.1 (TMI-1).

The proposed changes would require positive blocking of electrical power to the Core Flood Tank vent valves except under specified conditions and would require periodic venting of the pumps and lines associated with the Low Pressure Injection and High Pressure Injection Systems.

Discussion By letter dated January 13, 1976, Meted requested a cnange in the Technical Specifications for TMI-l to permit operation as reloaded for the Cycle 2 fuel loading. In performing our review of this application, including review of the loss-of-coolant-accident (LOCA) analysis per-formed in accordance with Appendix K to 10 CFR 50, we identified in our Safety Evaluation, dated May 18, 1976, two conditions that could reduce the effectiveness of the Energency Core Cooling System (ECCS). One of these conditions was the potential for spurious operation of the motor-operated vent valves, CF-V3A and CF-V3B, serving the core flooding tank (CFT) with an attendant reduction of pressure in the CFT. The other condition was the potential for water hammer due to the presence of air pockets in the ECCS lines and pumps.

To correct these conditions we stated that the following measures were necessary:

1555 206 2 9n oso 56 (1) The normally closed motor-operated valves, CF-V3A and CF-V3B, shall have their power disconnected and the associated breakers locked open except when adjusting CFT pressure; and (2) The High and Low Pressure Injection pump casings and system high points shall be vented during each refueling outage.

The Safety Evaluation setting forth these requirements also noted that Meted, by letter dated May 14, 1976, had comitted to perform these actions prior to Cycle 2 power operation. The present application, proposes to incorporate these operating requirements into the Technical Specifications so that they will be routinely observed for all future operations.

Since the proposed changes were found necessary by our earlier review to provide ipcreased assurance of the operability of the Core Flooding, Low Pressure Injection and High Pressure Injection Systems, and since this amendment merely incorporates these changes in the Technical Specifications, we conclude that the proposed changes will maintain reactor safety and are therefore acceptable.

Environmental Consideration We have determined that the amendment 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 made this determination, we have further concluded that the amendment 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, negative declaration, or environmental impact appraisal need not be prepared in 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 reason-able assurance that the health and safety of the public will not be en-dangered by operation in the proposed manner, and (3) such activities will be conducted in compliance with the Comission'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 23, 1976 1555 207

UNITED STATES NUCLEAR REGULATORY COMMISSION DOCKET N0. 50-289 f tETROPOLITAN EDIS0N C0f1PANY JERSEY CENTRAL POWER AND LIGHT COMPANY PENNSYLVANIA ELECTRIC C0f tPANY NOTICE OF ISSUANCE OF Af1ENDMENT TO FACILITY OPERATING LICENSE The U. S. Nuclear Regulatory Commission (tne Commission) has issued Amendment No.19 to Facility Operating License No. OPR-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.

The amendment revises the Technical Specifications to require positive blocking of electrical power to the Core Flood Tank vent valves except under specified conditions and to require periodic venting of the pumps and lines associated with the Low Pressure Injection and High Pressure Injection Systems.

The application for the amendment complies with the standards and requirements of the Atomic Enercy Act of 1954, as amended (the Act), and the Commission's rules and requlations. 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 amendment. Prior public notice of this amendment was not required since the amendment does not involve a siqnificant hazards consideration.

208

UNITED STATES NUCLEAR REGULATORY COMMISSION DOCKET NO. 50-289 METROPOLITAN EDISON COMPANY JERSEY CENTRAL POWER AND LIGHT COMPANY PENNSYLVANIA ELECTRIC COMPANY NOTICE OF ISSUANCE OF AMENDMENT TO FACILITY OPERATING LICENSE The U. S. Nuclear Regulatory Commission (the Commission) has issued Amendment No.19 to Facility Operating License No. DPR-50, issued to Metropolitan Edison Comeany, 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 ef fective as of its date of issuance.

The amendment revises the Technical Specifications to require positive blocking of electrical power to the Core Flood Tank vent valves except under specified conditions and to require oeriodic venting of the pumps and lines associated with the Low Pressure Injection and High Pressure Injection Systems.

The application for the amendment complies with the standards and requirements of the Atomic Enerny Act of 1954, as amended (the Act), and the Commission's rules and requlations. 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 amendment. Prior public notice of this amendment was not required since the amendment does not involve a significant hazards consideration.

{l ll  ; 2 ; $ g g

e 2-The Commission has determined that the issuance of this amendment will not result in any significant environmental impact and that pursuant to 10 CFR !i51.5(d)(4) an environmental impact statement, negative declaration or 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 amendnent dated July 12, 1976, (2) Amendnent No.19 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 Rocm,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 23rd day of August 1976.

FOR THE NUCLEAR REGULATORY C0milSSION kW Robert W. Reid, Chief Operating Reactors Branch #4 Division of Operating Reactors 1555 210

.