ML20040G434

From kanterella
Jump to navigation Jump to search
Amend 63 to License DPR-59,revising Tech Specs to Define Max Allowable Enrichment of Fuel Kept in Spent Fuel Racks
ML20040G434
Person / Time
Site: FitzPatrick 
Issue date: 01/29/1982
From: Vassallo D
Office of Nuclear Reactor Regulation
To:
Power Authority of the State of New York
Shared Package
ML20040G435 List:
References
DPR-59-A-063 NUDOCS 8202160024
Download: ML20040G434 (4)


Text

-_

. #'"4%

UNITED STATES p

'k NUCLEAR REEULATERY COMMISSION g

WAS9tNGTON, D. C. 20E36

%,*****/

POWER AUTHORITY OF THE STATE OF NEW YORK l

DOCKET NO. 50-333 JAMES A. FITZPATRICK NUCLEAR POWER PLANT AMENDMENT TO FACILITY OPERATING LICENSE Amendnent Jio. 63 License No. DPR-59 1.

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

A.

The' application for amendment by the Power Authority of the State of New York (the licensee) dated September 28, 1981, 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; B.

The facility will operate in confomity with the application, the provisions of the Act, and the rules and regulations of the Comission; C.

There is reasonable assurance (1) 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. 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 CPR Part 51 of the Comission's regulations and all applicable mquirements have been satisfied.

2.

Accordingly, the license is amended by changes' to the Technical Specifications as indicated in-the attachment to this license f

amendment and paragraph 2.C.(2) of Facility Operating License No.

DPR-59 is' hereby amended to read as.follows:

(2) Technical Specificat' ions The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 63, are hereby incorporated in the license. The licensee shall operate the facility in accordance

, with the Technical Specifications.

0202160024 820129

~

PDR ADOCK 05000333 P

PDR

2-3.

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

FOR THE NUCLEAR REGULATORY COMMISSION

_m b Domenic B. Vassallo, Chief Operating Reactors Branch #2~

Division of Licensing

Attachment:

Changes to the Technical Specifications Date of Issuance:

January 29, 1982 O

O e

G e

1 l

l l

1 l

l

ATTACHMENT TO LICENSE AMENDMENT NO. 63 FACILITY OPERATING LICENSE NO. DPR-59 DOCKET NO. 50-333

~

Revise Appendix A by removing' page 246 and inserting revised page 246.

[;

~

1

.,s' e

4 g

e O

4 0

m e

9 e-e e

f l

0 y..,,.

, -+

c

-r-

1 e*

5.5 (cont'd)

JAFNNP B.

The spent fuel storage pool is designed to maintain K gg less e

than.95 under all conditions as described in the Authority's application for spent fuel storage modification transmitted to NRC July 26, 1978.

In order to assure that the criteria is' met, new fuel

'will be will be limited.to an axial loading of 16.28 gm.

U-235/ axial cm, or equivalent..

The number of fuel assemblies stored in the spent fuel pool shall not exceed 22,44.

  • l 5.6 SEISMIC DESIGN The reactor building and all engineered safeguards are designed on a basis of dynamic analysis using l'

acceleration response spectrum curves which are normalized to a ground motion of 0.08 g for the Operating Basis Earthquake, and 0.15 g, from the Design Basis Earthquake.

e t.

t

-Amendment No. pf 63 l

t i

.