ML17055E484

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Amend 103 to License DPR-63,eliminating Contradiction Between Tech Specs 3.1.1.b(3)(b) & 3.1.1.e & Requiring Verification in Spec 3.1.1.b(3)(b) Re Control Rod Program
ML17055E484
Person / Time
Site: Nine Mile Point Constellation icon.png
Issue date: 01/26/1989
From: Capra R
Office of Nuclear Reactor Regulation
To:
Shared Package
ML17055E485 List:
References
TAC-67175, NUDOCS 8902020379
Download: ML17055E484 (8)


Text

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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, O. C. 20555 NIAGARA MOHAWK POWER CORPORATION DOCKET NO. 50-2?0 NINE MILE POINT NUCLEAR STATION, UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.

>p3 License No.

DPR-63 1.

The Nuclear Regulatory Commission (the Commission) has found that:

A.

The application for amendment by Niagara Mohawk Power Corporation (the licensee) dated January 14, 1988, complies with the standards

. and requirements 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; R.

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 he 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.

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-63 is hereby amended to read as follows:

8V020203W Bros C

PDR ADOCK 05000220 P

PDC

(2)

Technical S ecifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 103, 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 the date of its issuance.

FOR THE NUCLEAR REGULATORY COMMISSION ober A. Capra, Director Proiect Directorate I-I Division of Reactor Prospects, I/II

Attachment:

Changes to the Technical Specifications Date of Issuance:

January 26, 1989

ATTACHMENT TO LICENSE AMENDMENT AMENDMENT NO.

1O3 TO FACILITY OPERATING LICENSE NO.

DPR-63 DOCKET NO. 50-220 Revise Appendix A as fo11ows:

Remove Pa e

29 Insert Pa e

29

LI HITING CONDITION FOR OPERATION SURVEILLANCE REQUIREMENT (iv) The rod block function of the rod.worth minimizer shall be verified by attempting to withdra'w an out-of-sequence control rod beyond the block point.

(b)

Hhenever the reactor is in the startup or run mode below 20L rated thermal

power, no control rods shall be moved unless the rod worth minimizer is operable, except as noted in 4.1.1.b(3)(a)(iv), or a second independent operator or engineer verifies that the operator at the reactor console is following the control rod program.

The second operator may be used as a substitute for an inoperable rod worth minimizer during a startup only if the rod worth minimizer fails after withdrawal of at least twelve control rods.

(b)

If the rod worth minimizer is inoperable while the reactor is in the startup or run mode below 20K rated thermal power and a

second independent operator or engineer is being used he shall verify that all rod positions are correct prior to commencing withdrawal of each rod group.

If the rod worth minimizer fails prior to the complete withdrawal of the first twelve

rods, then the. withdrawn rods shall be inserted in the reverse order in which they

'ere withdrawn.

A second independent operator or engineer shall verify that the operator at the reactor controls is following the control rod program in reverse order.

(4) Control rods shall not be withdrawn for approach to criticality unless at least three source range channels have an observed count rate equal to or greater than three counts per second.

Amendment No. PÃ, 103 29