ML20009E970

Tech Spec Change Request 106 Amending App a of License DPR-50.Certificate of Svc Encl

ML20009E970
Person / Time
Site:	Three Mile Island
Issue date:	07/23/1981
From:	Hukill H METROPOLITAN EDISON CO.
To:
Shared Package
ML20009E964	List: ML20009E963 ML20009E970 ML20009E977
References
NUDOCS 8107280578
Download: ML20009E970 (4)

Text

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c METROPOLITAN EDISON COMPANY JERSEY CENTRAL POWER & LIGHT COMPANY AND PENNSYLVANIA ELECTRIC COMPANY THREE MILE ISLAND NUCLEAR STATION, UNIT 1 Operating License No. DPR-50 Docket No. 50-289 Technical Specification Change Request No. 106 This Technical Specification Change Request is submitted in support of Licensee's request to change Appendix A to Operating License No.

DPR-50 for Three Mile Island Nuclear Station, Unit 1. As a part of this request, proposed replacement pages for Appe *ix A are also included.

METROPOLITAN EDISON COMPANY f

By

- ' Director, TMI-l Sworn and subscribed to me this ) 3 day of hei & , 1981.

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PAMELA JO L 'E ECHT, Natary Publ;c Mit.de,wn. Detrghin County, Pa.

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NUCLEAR REGULATORY CO>D11SSION IN THE MATTER OF DOCKET NO. 50-289 LICENSE NO. DPR-50 METROPOLITAN EDISON C WPANY This is to certify that a copy of Technical Specification' Change Request-No.106 to Appendix A of the Operating License for Three Mile Island Nuclear Station Unit 1, has, on the date given below, been filed with.

the U. S. Nuclear Regulatory Commission and been served on the chief executives of Londonderry Township, Dauphin County, Pennsylvania and i' Dauphin County, Pennsylvania by deposit in the. United States mail, addressed as follows:

Mr. Donald Hoover, Chairman M . John E. Minnich, Chairman Board of Supervisors of Board of County Commissioners-l Londonderry Township of Dauphin County-

! R.D. #1, Geyers Church Road Dauphin County Courthouse

! Middletown, PA 17057 Harrisburg, PA 17120 METROPOLITAN EDISON COMPANY

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By Director, TMI-l Dated: July 23.:1981 j

Three Mile Island Nuclear Station, Unit 1 Operating License No. DPR-50 Docket No. 50-289 Technical Specification Change Request No. 106 The Licensee requests that the attachee revised pages replace pages 3-32 and 3-37 of Table 3.5.1 of the existing Technical Specifications, Appendix A to the Operating License.

Reason for Change Request No. 106 This change will permit hot functional testing with reactor coolant pump heat prior to initial criticality for cycle 5 (Restart) and prior to completion of the rupture detection portion of the containment isolation modification for certain lines. Technical Spec _fication change request 103 submitted previously will cover the completed containment isolation n/ stem.

Safety Analysis Justifying Change Prior to Hot Functional Testing the High-High (30 psig) reactor building pressure instrument channels will be installed and tested. The Reactor Coolant Pump Seal return lines, Reactor Coolant Pump Motor Cooling Water (Nuclear Services closed cycle cooling water) and Intermediate Cooling water lines' isolation valves will receive closure signals from the 30 psig system and not the 4 psig system as current Technical Specifications require. These modifications are in accordance with the system described and approved by the staff in "UREG 0680 Supplement 3 Item 2.1.4 "Contain-ment Isolation".

This TSCR is to permit Hot Functional Testing prior to cycle 5 criticality

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with the above modifications to the containment isolation system completed with the exception of the line break detection system which will be installed and tested prior to restart. In the unlikely event that this system is not complete, the 4 psig signal vill be restored to the effected valves prior to initial criticality.

The reactor coolant pump seal return lines' isolation modification will be complete prior to hot functional testing since the line break detection system is not required per item 2.1.4 of NUREG 0680.

Hot functional testing with the Nuclear Services and Intermediate Closed Cooling water system having only the 30 psig isolation signal is justified on the basis that they are closed systems, thereby reducing the risk of release of radioactive caterials to the environment. In the unlikely event of a need for containment isolation and the failure of High-High reactor building pressure instrument channels to close the isolation valves, manual isolation will be accomplished. Existing procedures require that the operator respond to decreasing surge tank levels for Intermediate Cooling and Nuclear Services Cooling (indicating a loss of system integrity) and take appropriate actions to isolate the systems if necessary.

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j Implementation Licensee requests that the effective date be the date of issuance of this

amendment Licensee Fee (10 CFR Part 70.22) 4 The enclosed Technical Specification Change Request f.s submitted as an 9

Administrative Change and the check for the required fee will be trans-mitted under a seperate cover letter.

Implementation Time Period ,

4 i It is requested that this Technical Specification Change Request be approved

expeditiously in order that it may be implemented for Hot Functional Testing, which is currentiv scheduled for July 27, 1981.

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