ML20033G626
| ML20033G626 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| Issue date: | 03/30/1990 |
| From: | Stolz J Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20033G625 | List: |
| References | |
| NUDOCS 9004100417 | |
| Download: ML20033G626 (5) | |
Text
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DNITs0 STATES j
NUCLE AR REGULATORY COMMIS$10N n
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i NORTHEAST NOCLEAR ENERGY COMPANY l
i DOCKET NO. 50-245 MILLSTONE MOCLE_AR_ POWER STATION, UN11 NO.1 AMENCHENT TO FACILITY OPERATING LICENSE l
Amendment No. 43 License No. DPR-21 l
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1.
The Nuclear Regulatory Comission (the Comission) has found thatt f
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A.
The application for amendment by Northeast Nuclear Energy Company l
(thelicensee),datedNovember 21,1989, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Comission's rules and regulations set forth in 10 CFR Chapter It 1
l B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Comissient I
C.
Thereisreasonableassurance(1)thattheactivitiesauthorizedby i
this amendnent 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 i
defense and security or to the health and safety of the publict and E.
The issuance of this amendrent is in accordance with 10 CFR part 51 of the Comission's regulations and all applicable requirements have been satisfied.
9004100417 90033o f
F*F,DR ADOCK 05000245 PDC i
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l i 2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, l
andparagraph2.C.(2)ofFacilityOperatingLicenseNo.DPR21ishereby l
j amended to read as follows:
l (2) Technical specifications j
The Technical Specifications contained in Appendix A, as revised i
through Amendment No. 43, are hereby incorporated in the license.
1 The licensee shall operate the facility in eccordance with the i
)I Technical Specifications.
l 3.
This license amendrent is effective as of the date of issuance, to be t
l implenented within 30 days of issuance.
I FOR THE NUCLEAR REGULATORY COW,1$$10N 1
O i
J hn h Stolz, Director froSectDirectorateI-4" i
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Elvision of Reactor Projects - 1/11 Office of Nuclear Reactor Regulation i
Attachn+nt l
Changes to the Technical Specifications Date of issuance:
March 30,1990 l
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ATTACHMENT TO LICENSE AMENDNENT NO. 43 l
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FACILITY OPERATING LICENSE N0. DPR-21 i
DOCKET NO. 50 745 t
1 Replace the following pages of the Appendix 'A' Technical Specifications with i
the enclosed pages. The revised pages are identified by amendment number and contain vertical lines indicating the areas of change.
I Remove Insert I
5-1 5-1 5-3 i
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5.0 ' DESIGN FEATURES d
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5.I liit i
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The Unit I reactor building is located on the site at Millstone Point in l
Waterford, Connecticut.
The nearest site boundary on land is 2063 feet l
northeast of the reactor building (1620 feet northeast of the elevated I
stack), which is the minimum dis"ance to the boundary of the exclusion i
areaasdescribedin10CFR100.3(a).
No part of the site that is closer to the reactor building than 2063 feet shall be sold or leased except to I
j The Connecticut Light and Power Company, Western Massachusetts Electric l
Company or the Northeast Nuclear Energy Company or their corporate affiliates for use in conjunction with normal utility operations.
5.2 Reactor r
A.
The core shall consist of $80 fuel assemblies.
B.
The reactor core shall contain 145 cruciform shaped control rods, i
The control material shall be hafnium and/or boron carbide powder (8 C) compacted to approximately 70% of theoretical density.
4 5.3 Reactor vessel l
The reactor vessel shall be as described in Table IV-1 of the FSAR. The l
applicable design codes shall be as described in Table IV 1 of the FSAR.
5.4 Containment l
A.
The principal design parameters and applicable design codes for the primary containment $1all be as given in Table V 1 of the FSAR.
i B.
The secondary containment shall be as described in Section V 3 of the FSAR and the applicable codes shall be as described in Section Xil of the FSAR, C.
Penetrations to the primary containment and piping passing through such penetrations shall be designed in accordance with standards set forth in Section V 2 of the FSAR.
5.5 Fuel Storace A.
The new fuel storage facility shall be such that the K,ff dry is less than 0.90 and flooded is less than 0.95.
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B.
The K to 0.IN of the spent fuel storage pool shall be less than or equal This K value is satisfied if the minimum gadolinium loading in a min @m of three fuel rods per fuel assembly lattice type versus the initial U 235 enrichment is within the acceptable region of Figure 51.
I C.
The number of fuel assemblies stored in the spent fuel storage pool shall not exceed 3229 bundles, i
MILLSTONE UNIT 1 5-1 AmendmentNo.#,/,43 i
I MILLSTONE UNIT 1
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FIGURE 5 1 MINIMUM 4ADOLINIUM LOADING, AS Gd203, 1
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ASSEMBLY LATTICE TYPE t
l Millstone Unit I 53 Amendment No. 43 J.
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