ML20128L749

Amend 97 to License DPR-21,removing TS Figure 5.1 & Substitutes Defined Requirement for Max Koo for Fuel Placed in Plant Spent Fuel Pool

ML20128L749
Person / Time
Site:	Millstone
Issue date:	10/04/1996
From:	Mckee P NRC (Affiliation Not Assigned)
To:
Shared Package
ML20128L711	List: ML20128L707 ML20128L749 ML20128L754
References
NUDOCS 9610150179
Download: ML20128L749 (5)

Text

.- . _ . - . . . -. . .

jp2" %g4 UNITED STATES g*

< S NUCLEAR REGULATORY COMMISSION

, If WASHINGTON, D.C. 2068H001 k...../ NORTHEAST NUCLEAR ENERGY COMPANY DOCKET NO. 50-245 MILLSTONE NUCLEAR POWER STATION. UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 97 License No. DPR-21

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

A. The application for amendment by Northeast Nuclear Energy Company (the licensee) dated May 2, 1996, as supplemented by letter dated August 30, 1996, 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 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.

I I

9610150179 961004 PDR ADOCK 05000245 P pon

. 1

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-21 is hereby amended to read as follows:

(2) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 97 , 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 issuance, to be implemented within 60 days of issuance. l l

FOR THE NUCLEAR REGULATORY COMMISSION

'Phillip F. cKee, Director Northeast Utilities Project Directorate Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications Date of Issuance: October 4, 1996

. ATTACHMENT TO LICENSE AMENDMENT NO. 97 FACILITY OPERATING LICENSE NO. DPR-21 DOCKET NO. 50-245 Replace the following pages of the Appendix A, Technical Specifications, with the attached pages. The revised pages are identified by amendment number and contain vertical lines indicating the areas of change.

Remove Insert 5-1 5-1 5-3 5-3

l

', 5.0 DESIGN FEATURES 5.1 Sit.g The Unit I reactor building is located on the site at Millstone Point in Waterford, Connecticut. The nearest site boundary on land is 2063 feet northeast of the reactor building (1620 feet northeast of the elevated stack), which is the minimum distance to the boundary of the exclusion area as described in 10 CFR 100.3(a). No part of the site that is closer to the reactor building than 2063 feet shall be sold or leased except to The Connecticut Light and Power Company, Western Massachusetts Electric Company or the Northeast Nuclear Energy Company or their corporate affiliates for use in conjunction with normal utility operations.

5.2 Reactor A. The core shall consist of 580 fuel assemblies.

B. The reactor core shall contain 145 cruciform-shaped control rods.

The control material shall be hafnium and/or boron carbide powder (B4 C) compacted to approximately 70% of theoretical density.

5.3 Reactor Vessel The reactor vessel shall bc as described in Section 5.3 of the UFSAR.

The applicable design codes shall be as described in Section 5.3 of the UFSAR.

5.4 Containment A. The principal design parameters and applicable design codes for the primary containment shall be as given in Table 6.2-1 and Section 3.8 of the UFSAR.

B. The secondary containment shall be as described in Section 6.2 of the UFSAR and the applicable codes shall be as described in Section 3.8 of the UFSAR.

C. Penetrations to the primary containment and piping passing through such penetrations shall be designed in accordance with standards set forth in Section 6.2 of the UFSAR.

5.5 Fuel Storaae A. The new fuel storage facility shall be such that the K, dry is less than 0.90 and flooded is less than 0.95.

B. The K, of the spent fuel storage pool shall be less than or equal to 0.90. This K, value is satisfied with fuel assemblies having a maximum K-infinity of 1.24 in the normal reactor configuration at cold conditions, and an average U-235 enrichment of 3.8 weight percent or less.

C. The number of fuel assemblies stored in the spent fuel storage pool shall not exceed 3229 bundles.

Millstone Unit 1 5-1 Amendment No. # , Q , M , Q ,97 0238

e l

l l

THIS PAGE INTENTIONALLY DELETED NI o)3,lstoneUnit1 5-3 Amendment No. JJ, 97