ML20147D925

Requests Amend of Tech Spec Sec 4.1.C Re Visual Inspec of boron-stainless Steel Safety Rods for Lic R-66.Amend Also Requested for Change in Tech Spec Sec 1.12d for Lic R-66 & Sec 1.15D for Lic R-123;wording Is Unnecessarily Vague

ML20147D925
Person / Time
Site:	University of Virginia
Issue date:	07/14/1978
From:	Williamson T VIRGINIA, UNIV. OF, CHARLOTTESVILLE, VA
To:	Lear G Office of Nuclear Reactor Regulation
References
NUDOCS 7812200222
Download: ML20147D925 (2)

Text

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e UNIVERSITY OF VIRGINI A GCl(OOL Of* I:N G IN f: E H i tJ G A tJ O A ppt t r o scit.rJ C t-LA.1,; Agmrt t k/ , C H A f.1 O I T L S V il I.F. 22901 pFyANTMtNr OF N U C t.f: A R ENGINLLHING AND E NGIN E LHING PHYSICS TELEPHONE: 804 924 7116 HaActOR F ACILITY 1

Division of Reactor Licensing .

I U.S. ,Nuc1 ca r Regula tory Commission Washington, D.C. 20555 Attention: Mr. George Lea r, Chief Operating Reactors Branch ll3 R F.: Docket No. 50-62, License No. R-66 Docket No. 50-396, License No. R-123 i

Ce n t I claen:

A. 'An amendment is here-by requested for Facilit.y License R-66, Docket No. l 50-62 to revisc Section 4.1.C of the Technical Specifications concerning  !

visual inspection of the boron-stainless steel safety rods. The present l requirement is for the visual inspection of the rods at intervals not to l exceed thirteen months or 50 Megawatt-days, whichever comes first.

l Over a period of seventeen years and about 275 Megawatt . days of operation, ,

I the yea rly visual inspection of these rods has shown no evidence of deterioration, swelling, or c racking. The visual inspection requires that each rod be physically removed from the guide tube and lowered int 6 the reactor pool where it is inspected under several feet of water. During the short interval the rod is being removed from the guide tube and prior to being lowered in the water the individual handling the rod is exposed to radiation from the rod.

In the past activity from the rods have been 150-200 REM /hr at contact with the individual recieving an exposure of approximately 0.010_ Man-rem.

In the near future we expect to be operating on a shif t basis for a special series of experiments. Each series of experiments will involve 70 Megawatt-days of operation. Under our present surveillance requirements we would have to shut-down the reactor prior to the completion of an experiment to inspect the rods.

Due to the increased power history the rods would have. a much higher radiation 1cvel than we have experienced previously.

In order to keep exposure to personnel as low as reasonably achievabic we hereby request that 4.1.C of the Technical Specifications be amended as follows:

4.1.C The Safety rods shall be visually inspected at intervals not to exceed twenty-four months or intervals of 150 Megawatt-days, whichever comes first.

If a safety rod is found to be deteriorated or have a crack of more than h inch in length, it shall be removed from service.

In our opinion this change does not involve an unreviewed safety question.

781220D N 1

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Division of Reactor Licensing Page 2

. July 13, 1978 I B.

An amendment is also requested for a change in the Technical Specification l 1.12 d of the UVAR Reactor, Facility License R-66 Docket No. 50-62 and Technical Specification 1.15 D of the CAVALIER reactor, Facility Lic;ense R-123, Docket No. 50-396, both of which a re the same and concern the definition of an abnormal occu rrenc e. The specification now reads as follows:

1.12 d (UVAR) ase of h. mon producu ham a fuel element.

1.15 D (C AVAL IER) -

l i

Many reactors release minute This specification as worded is unnecessary vague.

quantities of fission produce activity from irradiation of tramp uranium l which can b'c detected by up to date, analysis systems.. \

4 We request an amendment to change the specification as follows: 1 1

Fission product release from the geactor such that I-131 activit !

in the pool water exceeds 6 x 10' uci/ml.  :

I This value is a factor of ten below the maximum permissibic concentration for Iodine-131 for rest ricted areas. It is a factor We of ten above the minimum feel this is a reasonable number, detectable activity of our instrumentation.

easily detected by our instrumentation, and well below the MPC for restricted areas.

In our opinion this change does not involve an unreviewe i safety question.

These changes have been reviewed and approved by our Reactor Safety Commit te.

Very _t ruly yours,

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