ML20210R475

Amend 89 to License DPR-61,revising Tech Spec 4.3 by Deleting Requirement That Surveillance Tests of Diesel Generators Include Automatic Loading of Charging Pumps

ML20210R475
Person / Time
Site:	Haddam Neck File:Connecticut Yankee Atomic Power Co icon.png
Issue date:	02/09/1987
From:	Charemagne Grimes Office of Nuclear Reactor Regulation
To:
Shared Package
ML20210R429	List: ML20210R424 ML20210R475 ML20210R514
References
NUDOCS 8702170420
Download: ML20210R475 (4)

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UNITED STATES 8 n NUCLEAR REGULATORY COMMISSION

,- f ,1 WASHINGTON, D. C. 20555

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CONNECTICUT YANKEE ATOMIC POWER COMPANY HADDAM NECK PLANT DOCKET NO. 50-213 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 89 License No. DPR-61

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

. A. The application for amendment by Connecticut Yankee Atomic Power Company (the licensee), dated October 20, 1931, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations as set forth in 10 CFR Chapter I; B. The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations 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 the public; and (ii) that such activities will be conducted in compliance with the Commission's regulations; D. The issuance of this amendment will not be inimical to the common 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 Commission's regulations and all applicable requirements have been satisfied.

8702170420 870209 DR ADOCK0500g3

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 Appendix A, as revised through Amendment No. , are hereby incorporated in the license.

The licensee shall operate the facility in accordance with the technical specifications.

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

FOR THE NUCLEAR REGULATORY COMMISSION W,uT . S u. i Christopher I. Grimes, Director Integrated Safety Assessment Project Directorate Division of PWR Licensing - B

Attachment:

Changes to the Technical Specifications Date of Issuance: February 9,1987 O

4s ATTACHMENT TO LICENSE AMENDMENT N0. 89 FACILITY OPERATING LICENSE NO. DPR-61 DOCKET NO. 50-213 Replace the following page of the Appendix.A technical specifications with the enclosed page as indicated. The revised page is-identified by the

. captioned amendment number and contains a vertical line indicating the area of change.

REMOVE INSERT 4-3 4-3 l

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4.3 Cr)RE COOLING SYSTEL*S - PERIODIC TESTING

• Appilcabili tu: Applies to periodic testing requirements for the core cooling system.

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

Soecifica tion: 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 sum:.arized below:

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

2) Verification shall be made that the diesel gen-erator and its. associated pumps,have started in the.

proper sequence and that the high pressure safety injection and low pressure safety injection (core deluge) attain required discharge heads of i392 psig and 322 psig respectively. Following this check of the automatic sequence, one of the safety injection pumps will be secured and the associated charging pump will be started manually. Verification shall be made that the charging pump attains the required discharge head of 2150 psig. The next step will be to secure either the charging pump or the remaining safety, injection pump and manually start the associated RNR pump. Verification will be made that the RHR pump attains the required discharge head of 145 psig.

3) The test will be considered satisfactory ii 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 l

b) a minimum of two three inch openings shall be used for venting if both trains of the RCS OPS are out of service.'

4-3

[ 89 Amendment No. [

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