ML20127J495

Amend 7 to License DPR-22,changing TS Re Reactor Vessel Matl Surveillance Program

ML20127J495
Person / Time
Site:	Monticello
Issue date:	02/03/1975
From:	Goller K Office of Nuclear Reactor Regulation
To:
Shared Package
ML20127J494	List: ML20127J492 ML20127J495 ML20127J513 ML20127J524
References
NUDOCS 9211190355
Download: ML20127J495 (4)

Text

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NORTilERN STATES POWER COMPANY DOCKET No. 50-263 MONTICELLO NUCLEAR GENERATING PLANT .

AMENDMENT 'ID PROVISIONAL OPERATING LICENSE Amendment No. 7 License No. DPR-22

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

A. The application for amendment by the Northern States Power Company (the licensee) dated November 15, 1974, 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 CPR Chapter I; B. The facility will operate in conformity with the application, the provisions of the Act, and the rulus_and reguistions of the Commission; ,

C. Thoro is reasont.ble assuranco (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 Connaission's regulations; D. The issuance of this amendment will not be inimical to the common defense and security or to the health and cafety of -the public; and C. Prior public notice of this amendment is not required since the

- amendment does not involve a significant hazards consideration.

2. Accordingly, the license is amended by a change to the Tecnnical Specifications as-indicated in the. attachment to this license amendment and Paragraph 3.D of Provisional Operating. License ;io.

JPR-22 is hereby anended to read as follows:

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Fann AEc.318 (Rev. 9 53) AECM 0240 # u. s. novanument eninvine orrics isra.sa ies 9211190355 750203 PDR ADOCK 05000263

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The Technical Specifications contained in Appendix A, as revised, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications, a as revised by issued changes thereto through

Change No. 16"

3. 7his license amendment is effective as of the date of its issuance.

IVR THE NUCLEAR PIGULATORY C012HSSION s

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N r) 2, " 7' Karl R. Goller, Assistant Director i for Operating Reactors j Division of Reactor Licensing

Attachment:

Change No. 16 co the Technical Specifications Date of Issuance: pgg 0 3 1975 I

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.w w ATIACIDENT TO LICENSE AMENDMENT NO. 7 l 4

CIIANCE HO. 16 TO THE TECHNICAL SPECIFICATIONS PROVISIONAL OPERATING LICENSE NO. DPR-22 NORTHERN STATES POWER COMPANY 4

s MONTICELLO NUCLEAR GENERATING PLANT DOCKRT NO. 50-263 I

The Technical Specifications contained in Appendix A, attached to Provisional Opert. ting License No. DPR-22, are hereby changed by replacing page 116 with the attached revised page. Changed areas on the revised page are reflected by marginal linas, r t.

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3.0 LIMITING CONDITIONS FOR OPERATION 4.0 SURVEILLANCE REQUIREMENTS ,

B. Pressurization Temperature B. Pressurization Temperature Reactor vessel shell temperature and l '. The reactor vessel shall be vented and 1.

reactor coolant pressure shall be power operation shall not be conducted unless the reactor vessel temperature is permanently recorded whenever the shell equal to or greater than'that shown in temperature is below 220*F and the Figure.4.6.1. ,

reactor vessel is not vented. ,

The reactor vessel head bolting studs shall 2. When the reactor vessel head bolting studs 2.

not be under tension unless the tempera- are tightened or loosened, the reactor ture of the vessel head flange and the vessel head flange and head temperature shall be permanently recorded.

. head are > 70*F.

3. A neutron flux dosimeter and raterial samples shall be installed it the reactor vessel adjacent to the vessel wall at the core midplane level. The j

material sample program shall conform  ;

to AST!1 E-85-66. The neutron flux L6 dosimeter shall be removed during l

the first refueling outage and tested to verify or adjust the calculated i

values of neutron fluence used to i

determine the vessel NDTT (Nil Ductility Transition Temperature) from  ;

Fig. 4.6.1. A material surveillance specimen  !

sample shall be removed when the estimated change in NDT temperature is 50*F, but prior gg to tge time when the estimated fluence is 10 4-n/cm , or at the 15 years operational interval whichever first occurs.

Coolant Chemistry C. Coolant Chemistry

. C.

The reactor coolant system radioactivity 1. (a) A reactor coolant sample shall be 1.

taken at least every 96 hours0.00111 days <br />0.0267 hours <br />1.587302e-4 weeks <br />3.6528e-5 months <br /> and

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