ML20066F348

Application for Amend to License R-125,changing Description of Tech Spec Section 3.3, Reactor Safety Sys & Removing Pool Water Level from List of Measuring Channels Required in Section 3.2

ML20066F348
Person / Time
Site:	University of Lowell
Issue date:	01/15/1991
From:	Beghian L MASSACHUSETTS, UNIV. OF, LOWELL, MA (FORMERLY LOWELL
To:	Michaels T Office of Nuclear Reactor Regulation
Shared Package
ML20066F350	List: ML20066F348 ML20066F352
References
NUDOCS 9101230272
Download: ML20066F348 (2)

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$<w$ 1JJacktJcNs 0/854 I (508) 452 5000- 3 January -15,1991 Docket No. 50-223 Reactor R-125 Document Control Desk U.S. Nuclear Regulatory Commision Washington, DC. 20555 Gentlemen, ,

The University of Lowell ~ Reactor wishes' to submit the following changes ~ to our Reactor License-(R-125) Technical--

Specifications These changes -are as follows:'

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l. Change the description of 3.3, ReactoriSafety . System', page IV-18 concerning the . function of thel Reactor; Period from:

" Automatic reactor scram" with <3 sece period, &-

Reg Rod prohibit <l5 se'c period" to:

" Automatic reactor scram with; <3 sec period, &

control blade inhibit with < 15 -sec period.~"

The Regulating Rod has. never 'had- any automatic safety features and, in fact, is not considered 'part of the safety system..This is a description error missed- when we rewrote. our license in 1984.

This automatic withdrawal inhibit .has always -been a function' of the l_ control blades, which are part of the Reactor- Safety System.

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2. Remove the " Pool Water Level" from the list of measuring channels required in section 3.2 Reactor Instrumentation, page IV-17. The pool water level channel is a' float operated device which causes a reactor scram when the pool is below a certain level. Since it is required by Section 3.3 Reactor ,

Safety System, page IV-19, and because it is not a measuring channel, it should. be removed - from this section. >

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-, .,' 1 These' changes l have- been: reviewed by the- Universi.ty. of Lowell-

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__ Reactor Ssfety' Subcommittee and th'ey have determ'.ned that these-changes do not ;c_onstitute .a reduction in- reactor ~ safety 'and actually revert to the ' original _-intent _ of these. systems.

Sincerely yours,

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- Dr,l. Leon Beg ian, . _

Assoc;1Vice President. i for'.' Research -

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