ML20244D493

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Application for Amend to License R-28,modifying Tech Specs Sections 3.1.6 & 6.1.6 Re Shutdown Margin During shim-safety Rod Insp & Licensed Senior Reactor Operator on Shift Whenever Reactor Operating,Respectively
ML20244D493
Person / Time
Site: University of Michigan
Issue date: 05/08/1989
From: Fleming R
MICHIGAN, UNIV. OF, ANN ARBOR, MI
To: Michaels T
Office of Nuclear Reactor Regulation
Shared Package
ML20244D497 List:
References
NUDOCS 8906190093
Download: ML20244D493 (2)


Text

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i University of Michigan y

o

.. Michigan. Memorial-Phoenix Project-l~

J Office of theLDirector Ann Arbor, Michigan 48109-2100

'May 8, 1989 Docket 50-2 i

l License R 28 United States Nuclear Regulatory Commission.

Attn: Theodore S. Michaels, Project Manager Standardization and Non-Power Reactor Project Directorate Division'of Reactor Projects III, IV, V, and Special Projects Office of. Nuclear' Reactor! Regulation Washington, D.C.

20555

Dear Mr..Michaels:

The University of Michigan hereby submits modifications to'the I

Ford Nuclear Reactor Technical Specifications.

Revised pages to the Technical Specifications are' enclosed.- The proposed changes in' Revision 1 are. underlined.and denoted in the right margin.

The majo'rity of-the changes are non-substantive..The substantive changes are:

Section 3.1.6.

A minimum required shutdown margin during a shim-safety rod inspection'is proposed that.is considerably

.l more conservative than the existing shutdown margin requirement.

.)

Section 6.1.6.

A licensed senior reactor. operator.is i

required to be on shift whenever the reactor is. operating, f

Ea._ge..Section Description 10 3.1.6 The existing shutdown margin requirement would t

permit removal of shim-safety rods with a shutdown margin, after' rod removal, of 0.011 delta-K/K with-the most reactive remaining rod-fully withdrawn..

1 The proposed change is the procedure we routinely l

l utilize.

It requires that the core shutdown inargin j

not be less than 0.10 delta K/K' prior to any rod

)

L removal for inspection.

This is accomplished by=

1 i

removal of fuel elements.

Each shim-safety rod has a reactivity of approximately 0.02 delta-K/K.

Even if all three. shim-safety rods were removed simultaneously, the reactor still would have a.

. shutdown margin of approximately 0.04 delta K/K which is considerably more conservative than the i

current specification.

j 1

10 3.1.7 The shutdown margin requirement'for heavy-water transfers was moved from Section 3.5.1 to group all core reactivity requirements into one section.

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S. Nuclear Regulatory-Commission May 8 -1989 Ea ste Sectj g1 Description 11 3.1.8 Renumbered from 3.1.7 and 3.1.8 3.1.9 11 Bases Basis for heavy. water tank shutdown margin moved from Section 3.5 15 Note (b) Reactor Manager title has been changed to Nuclear 36 6.1.2 Reactor Laboratory Manager.

There are two Assistant 36 6.1.3 Managers, one for operations and one.for research 36 6.1.4

. support activities.

38 Fig 6.1 39 6.2.7 40 6.3.1 1

41 6.4.8 42 6.6.6.a

.{

i 25 4.1.4 Reactivity surveillance specification for heavy water transfer moved from Section 4.5.

26 Bases Basis for heavy water surveillance specification 4

moved from Section'4.5.

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30 4.6.3 Abbreviation for argon is Ar.

33 5.1.1 Correction of typographical error from 50 to 500.

36 6.1.6 An operating crew of two people must have at least one licensed senior reactor operator.

36 6.1.7 Delete this section in its original form.

Requirement for a licensed senior reactor operator to be on shift added to section 6.1.6.

37 6.3.8 Changed to 6.1.7.

Added the requirement that the Nuclear Reactor Laboratory Manager or one of the two Assistant Managers be on-call 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> per day, seven days per week.

37 6.1.9 Renumbered. to 6.1.8 and 6.1.9 6.1.10 Sincerely, Subscribed and sworn before me, this day of A7Clu 19M a Nctmy Publia O

la and ior MY513If.tm i t 3 Coenty, i

/

Kchinen.

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Ron d F.

Fleming, Director g

Michigan Memoria)-Phoenix PrJ. lect gc,,.

N07AR/ FUSUC Enclosure

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