ML20210B511

Discusses Review of Util Reactor Bldg Sump Criticality Safety Evaluation.Proposed Use of Nonborated Water for Decontamination Purposes Contingent Upon Submittal of Related Procedures

ML20210B511
Person / Time
Site:	Crane
Issue date:	09/11/1986
From:	Travers W Office of Nuclear Reactor Regulation
To:	Standerfer F GENERAL PUBLIC UTILITIES CORP.
References
CON-NRC-TMI-86-088, CON-NRC-TMI-86-88 NUDOCS 8609180103
Download: ML20210B511 (2)

Text

g s

g DISTRIBUTI0t; Y,)E gy e:

DN50-320 Local PDR p,

NRC PDR

.$k DCS hk September 11, 1986 f4 t

/f

}#gp FJMiraglia HRC/THI 86-088 WDTravers MTMasnik M-CCowgill fh fC

-Docket No. 50-320 er g

ACRS

~M' Mr. F. R. Standerfer ME M-T wn OfH ce W[>

Vice President / Director, THI-2 Service List GPU huclear Corporation y,,

P. O. Box 480 Hiddietown, PA 17057 o

k,

Dear Mr. Standerfer:

%w

Subject:

Reactor Building Sunp Criticality Safety Evaluation Report M~

References:

(a) GPUN letter. F. R. Standerfer to W. D. Travers M

Reactor Building Sump Criticality Safety Evaluation J;

Report, dated Janut.ry 23, 1986-f, (b) URC letter, W. D. Travers to F. E. Standerfer, dated March 5,1986 (c) GPUN letter. F. R. Standerfor to W. D. Travers, Reactor Building Swp Criticality Safety Evaluation Report, dated May 26, 1986 O

(d) CPUN letter F. R. Standerfer to W. D. Travers,

~

Reactor Bu11 ding Sump Criticality Safety Evaluation Report, dated Septer/ocr 5,1986

,e Reference (a) forwarded for NRC staff review and approval, a safety evaluation -

which demonstrated that it is sufficiently unlikely that there could be an occurrence of critice.11ty in the reactor building sump frem the use of-non-borated water in carrying out decontacination activities. During our review, we requested additional information in reference (b) and you responded in reference (c). You have since supplied us additional infomation in reference (d) to assist in our review,

p..

,4 The staff's review has detemired that the amount of fuel in the reactor

.? '

. building basement is less than the conservative mass of 70 kg required to

!1 achkye criticality. We have found that your analysis bounds the amount of fuel at 2 kg to 18 kg with an average value of 15 kg (reference d) of uraniua fuel in the basement of the reactor building. Our conclusion on this is based prinarily on the direct results of resctor building samples which have been obtained and analyzed for their fuel and fission product content. We agree

'i that this estfrete (15 kg) and the bounding analyses of 2 kg to 13 kg arc based on the best available information. We have further detemined that N

there is enough conservatism in your analytical approach to demonstrate that 7

the arEunt of fuel in the reactor building basement is sufficiently sraller

.mc >

0609100103 060911 PDR ADOCK 05000320 h.

P PDR Nf c.,

.h

..f cc rostu sie (so soi nucu ca4o OFFICIAL RECORD COPY

]

w-O Mr. F. R. Standerfer Septer6er 11,1986 then the 70 kg critical rats and that criticclity cannot occur in the reoctor raufiding sung frca the use of non-borated water in decontamination activities.

In addition, cur evaluacions have concluded that it is highly unlikely that the fuel prcsently distributcd throughout the reuctor buildin basamnt could s

be in;dvertently accuhulsted in a gccnetric configuration which would support criticelity.

We have cur;pleted our review of reference (o) cod supporting documents and have ?

.uded that your proposed operation of using non-borated water for dcccatwanatian purposes presents no adverse inpact on public health and safety and dues not involve en unreviewed safety question.

We, thsefore, approve the proposed use of non-borated uccer for

[

decontenination purposes as described in reference (a) contiagent upon the submittal of relatid procedures subject to Technical Specification 6.8.2.

These prxedures shall address the cmtrolled use of non-borated water for decontenination purposes and liuit the accuc.ulation of w6ter to 70,000 gallons in the reactor buildino casenunt. This limit till assure adequate boration in the case that basexnt wtor is required for recirculation into the reactor coolant systen.

Sincerely, ORIGirlAL SIGNED in.

Wil;iam D. Travers Williaa D. Travtre Ofrector Tiil-2 Clecnup Project Directuretc cc:

T. F. D n itt L. C. Itogan

5. Levin

c. P. Frew J. J. Byrne A. W. Hiller Service Listribution List (st.e e ttuchu!)

1 l

i

" ' " > Iti

.... TtilCPD...

.. 7ti,!CR aa=>N

n....wTJpp....

. pthr...

o^" > 9(//(99.... 9(d89.....

9(.f]/89,,,,,

,,,,,,,,,3 a

._ a (J4c ronv ais oa soi sacu o2*

OFFICI AL__RE.COR D COPY

_______________________________;