ML20128E000

Forwards Three Sections of ACRS Rept on Primary Coolant Sys, Including Leak Detection Sys,Reactor Vessel Matl Surveillance Program & Inservice Insp

ML20128E000
Person / Time
Site:	Monticello
Issue date:	11/06/1969
From:	Dromerick A US ATOMIC ENERGY COMMISSION (AEC)
To:	Boyd R US ATOMIC ENERGY COMMISSION (AEC)
References
NUDOCS 9212070443
Download: ML20128E000 (3)

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R. S. Boyd, A/D for RF, DRL THRU t S. Levine, A/D for RT, DE MONTICELLO NUCLEAR GENERATING ?LANT, UNIT 1 - N0kTHERN STATES POWER COMPANY - PRIMART COOLANT SYSTEM Emelooed are the three following sections of our ACRS report on the Primary Coolant Systems Leak Detection System, Reactor Yessel-Material Surveillance Program and Inservice Inspecties-for the steject plant.

A. W. Droneriek, Ch6e f RT-8281 Cantainment & Componest Technology Branch DRLIC&CTBtMBF Division of Reactor Licensing Enelesare 3 Sections for inclusion in ACRS Report cc w/ sect s D. Muller DRL D. Yassalle DE Dietribution Suppl i g

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R. DeYoung S. Imvine A. Drcaerick M. Fairtile i

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a ACRS REPORT H0ttrICELLO NUCLEAR CENERATING PLANT. UNIT 1 4

LE AK DETECTIQI SYSTEM This system is primarily based on monitoring leakage flows to an equipment drain sump and a floor drain sump. The rate at which the water-levels in the sumps change can accurately measure primary system leakages.

This is the only quantitstive leak detection system available at Monticello.

We will require the applicant to provide a system, at least equal to that to be provided in Dresden 2/3, within one year after Monticello Unit 1 commences operation. Operation in the interim with only the system presently installed is acceptable.

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The identified leakage limit of 25 spm and the unidentified leakage limit of 5 gpm prasented in the Draf t Technical Specifications are acceptable to us.

The applicant will shut down within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> if either limit is exceeded.

REACTOR VESSEL MATERIAL SURVEILLANCE PPDCRAM The estimated end-of-life fluence at the vessel is 5.4 x 10 nyt.

We consider the proposed program adequate for the estimated fluence even if the estimate proves low by about a factor of 2.0

4... INSERVICE INSPECTION The applicant has proposed a preservice base line inspection following l

the Draf t ASME Code for Inservice Inspection of Nuclear Reactor Coolant i

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Systems (N-45 Committee) as closely as possible. We are presently developing i

i the inservice inspection requirements for the Technical Specifications. We j

intend to implement an inservice inspection program at Monticello Nuclear i

Generating Plant Unit 1 equivalent to that at Dresden 2 and 3.

The program i

i will include main steam lines and fluid carrying emergency safety features as well as the primary coolant system.

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