ML20108C976
| ML20108C976 | |
| Person / Time | |
|---|---|
| Site: | Monticello  |
| Issue date: | 11/02/1984 |
| From: | Vassallo D Office of Nuclear Reactor Regulation |
| To: | Northern States Power Co |
| Shared Package | |
| ML20108C978 | List: |
| References | |
| DPR-22-A-028 NUDOCS 8411190159 | |
| Download: ML20108C976 (4) | |
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UNITED STATES j
g NUCLEAR REGULATORY COMMISSION -
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. NORTHERN STATES POWER COMPANY 3
DOCKET NO. 50-263 p
MONTICELLO-NUCLEAR GENERATING PLANT AMEN 0 MENT TO FACILITY OPERATING LICENSE Amendment No. 28
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License No.;DPR-22 1.
The Nuclear Regulatory Commission (the Connission) has found that:
l' A.
The application for ~ amendment by Northern States. Power Company (the -
licensee)datedAugust 17, 1904, complies with the-standards and requirements of the Atomic Energy Act of 1954, as amended (the Act),
and the Connission's rules and regulations set forth in 10 CFR j
Chapter I; t
i B.
The facility will operate in conformity with the application, the-provisions of the Act, and the rules and regulations of the,
Connission;
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C.
There is reasonable assurance (1) that the activities authorized by this amendment can be conducted withcut endangering the health and safety of the public'and (ii)' that such activities will be 4
i conducted in compliance with the Consission's regulations; D.
The issuance of this amendment will not b'e 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 i
51 of the Ccmmission's regulations and all applicable requirements l
have been satisfied.
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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-22 is hereby amended to read as follows:
2 Technical Specifications i
The Technical Specifications contained in Appendix A as revised through Amendment No. 28, are hereby incorporated in the license, The licensee shall operate the facility in accordance with the l
Technical Specifications.-
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3.
This license amendment is effective as of the date of-its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION i -
Domenic B. Vassallo, Chief Operating Reactors Branch #2 Division of Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance:
November 2,1984 O
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ATTACHMENT TO LICENSE AMENDMENT NO. 28 FACILITY OPERATING LICENSE NO. DPR-22 DOCKET NO. 50-263 Replace page 230 of the Appendix "A" Technical Specifications with the enclosed page 230. The revised page is identified by Amendment number and contains vertical lines indicating the areas of change.
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5.0 DESICH FEA111NES 51 Site, A.
The reactor center line la located at approulmately 850,810 feet flerth and 2,038,920 feet East se determined on the Blinnesota State Grid, South Zone.
1630 feet 8 30" W of the reactor center line and thelenclueton " area is defined by the minimumThe nea
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fenced area shown in FSAR Figure 2.2.2a.
Due to the prevailing wind pattern.'the direction of neutnum integrated dosage le SSR. The southern property line follows the northern boundary of the right-of-way for flie surlington Northern Railway.
5.2 Reactor 1
A. The reactor cara shall consist of not more than*484 fuel semenblieu.
B. The reactor core shall contain 125 cruciform-ehaped control rode.
be baron cathida powder (B C The control rod materiet shalt 4
Hybrid I control rods whic)h contain approximhtely 15% hafniunicompacted to approulmetely l
53 Reactor Vessel g
A. The preemure vesset shall be designed for a pressure of $250 pela and a temperature of 562*F...
the coolant recirculation mystem shall be designed for a pressure of Il48 pela on euction side of pump and 1248 pels at pump discharge.
The applicable design codes shall be as described in Sectione 4.2.3 and 4.3.1 of the Monticello Final Safety Analysis Report.
54 containment i
A. The primary containment shall be of the pressure suppresulon type having e drywall and am ghmorption chenher constructed of steel.
The drywell shelt have a volume of appreslaately 134,200 ft and le designed to conform to ASHE tulier and Pressure Vessel Code Section III Clama B for en-internal pressure of 56 pela at 288"F sud an esternal pressure of 2 pegg at 28l F.
The absorption chenhor shall have a total volume of approulmately 176.250 it I
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t 5'0 230 Anendnent No.
17, 28 i
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