ML20134P963

Amend 67 to License DPR-61,changing Tech Specs Re Discharge Pressure Requirements for ECCS Periodic Flow Testing to Reflect True Pump Performance W/Allowance for Pump Degradation Due to Normal Wear

ML20134P963
Person / Time
Site:	Haddam Neck File:Connecticut Yankee Atomic Power Co icon.png
Issue date:	09/03/1985
From:	Zwolinski J Office of Nuclear Reactor Regulation
To:
Shared Package
ML20134P953	List: ML20134P951 ML20134P963 ML20134P968
References
NUDOCS 8509090111
Download: ML20134P963 (4)

Text

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C07:NECTICUT YANKEE ATOMIC POWER COMPANY PADDAM NECK PLANT DOCKET NO. 50-213 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 67 License'No. OPR-61

1. The Nuclear Regulatory Comission (the Commission) has found that:

A. The application for amendment by Connecticut Yankee Atomic Power Company (the licensee) dated May 31, 1984, complies with the standards and requirenents of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations set forth in 10 CFR Chapter I; B. The facility will operate in co'nformity with the application, the provisions of the Act, and the rules and regulatiors of the Commission; C. There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of tha public; and (ii) that such activities will be conducted in comp 1_f ance with the Comission's regulations; D. The issuance of this amendment will not be inimical to the comon defense and security or to the health and safety of the public; and E. The issuance of this amendment is in accordance with 10 CFR Part 51 of the Comission's regulations and all applicable requirements have been satisfied.

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2. Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment and Paragraph 2.C.(2) of Facility Operating License

, No. DPR-61 is hereby amended to read as follows:

(2) Technical Specifications The Technical Specifications contained in Appendices A and B as revised through Amendment No. 67, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.

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3. This license amendment is effective as of the date of its issuance.

FOR THE NUCLEAR REGULATOPX COPMISSION i

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John A. Zwolinski, Chief Operatina Peactors Branch #5 Division of Licensing

Attachment:

Changes to the Technical Specifications Date of Issuance: September 3, 1985.

ATTACHMENT TO LICENSE AMENDt'EtiT t:0. 67 FACILITY OPERATING LICENSE N0. DPR-61 DOCKET tt0. 50-713

' Replace the following pace of the Appendix A Technical Specifications with ^

the enclosed page as indicated. The revised pace is identified by the i captioned amendment number and contains vertical lines indicating the area of change.

REMOVE INSERT 4-3 4-3 i

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4.3 CORE COOLING SYSTEMS - PERIODIC TESTING Applicability: Applies to periodic testing requirements for the core cooling system.

Obiective: To verify the operability of the core cooling systems.

Specification: A) During each refueling shutdown, a test shall be conducted to demonstrate proper automatic operation of the core cooling systems. The test shall be performed in accordance with written procedure as summarized below:

1) The two independent core cooling systmas will be tested separately. A test signal will be applied to initiate a loss of normal AC power to each of the energency power systems while a coincident signal is applied which initiates operation of the amergency core ' cooling equipment associated with the systen being tested.

2) Verification shall be made that the diesel generator and its associated pumps have started in the proper sequence and that the high pressure safety injection, low pressure safety injection (core deluge) and charging pump attain required discha'rge heads of 1392 psig, 322 psig and 2150 psig, respectively. Following this check of the automatic sequence, either a charging or safety injection pump will be secured and the associated RHR pump will be started manually. Verification will be made that the RHR pump attains the required discharge head of 145 psig.

3) The test will be considered satisfactory if

_ control board indication and visual observations indicate all components have operated and sequenced properly.

4) A prerequisite for this test shall be that either:

a) the RCS shall be vented by a 3" or larger opening and the RCS OPS shall be inservice, or 1

b) a minimum of two three inch openings shall be

, used for venting if both trains of the RCS OPS are out of service.

HADDAM HECK 4-3 AmendmentNo.g,pf,67

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