ML17255A661

Updates Actions Taken to Satisfy Requirements of NUREG-0737, Item II.B.2, Plant Shielding. Consequences of Accidents Can Be Controlled W/O Access to Radwaste Control Panel Through Recently Installed Remote Monitor

ML17255A661
Person / Time
Site:	Ginna
Issue date:	02/01/1984
From:	Kober R ROCHESTER GAS & ELECTRIC CORP.
To:	Crutchfield D Office of Nuclear Reactor Regulation
References
RTR-NUREG-0737, RTR-NUREG-737, TASK-2.B.2, TASK-TM NUDOCS 8402070138
Download: ML17255A661 (6)

Text

R EGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)

ACCESSION NBRe8402070138 DOC ~ DATE! 84/02/01 NOTAR D:.NO DOCKET FACILg50<244 Robert Emmet, Ginna Nuclear Plantg Unit lg Rochester G

05000244 AUYH.NAME AUTHOR AFFILIATION KOBERI 8 ~ G ~

Rochester Gas 8, Electric Corp.

RECIP ~ NAME REC IP IENT AF F IL'IAT I ON CRUTCHFIELDtD~

Operating Reactors Branch 5

SUBJECT:

Updates actions, taken to satisfy requirements of NUREG 0737i Item II,B~'2i."Plant Shielding," Consequences of accidents can be." controlled w/o access.to'adwaste control panel through recently insta'lied remote monitor

~

DISTRIBUTION CODE:

A046S COPIES RECEIVED:LTR g ENCL SIZE:

TITLE:'OR Submittal'.

TMI Action Plan Rgmt NUREG 0737 8

NUREG"0660 NOTES:NRR/DL/SEP icy, 05000244 RECIPIENT ID CODE/NAMEi NRA ORB5 BC 01 INTERNAL) ELD/HDS4

=IE/DEPER/EPB NRR ERICKSONi P NRR/DHFS DEPY29 NRR/DL/ORAB 18 NRR/DSI/AEB NRR/DSI/RAB 04 COPIES LTTR ENCL "7

1 1

1 3

1 1

RECIPIENT ID CODE/NAME IE/DEPER DIR 33 IE/DEPER/IRB NRR,'PAULSONiN ~

NRR/DI D IR 14 NRR/DSI/ADRS 27 NRR/DS I/ASB NRR/DST DIR 30 RGN1

, COPIES LTTR ENCL 1

1 1

1 1

1 1

1 EXTERNAL; ACRS NRC PDR NTIS NOTFS:

3402'01 1

LPDR NSIC 03 05 TOTAL NUMBER OF COPIES REQUIRED:

LTTR 42 ENCL

ji

~ j jj>>,ll,,

II i( 4 if s D, D l.0

~

ill('

3 (f i,, ij > j ij

~ l,.

!,Dis, f Jgi I <<'

lx

< a" j

f~f, g

i "D,D'1',(i

('ll

i '$sysggaj Df" D Dgg(,~i( ~

)1j

~, ~ a'l hl jj!. ', f( f, Qgf

((> iaa(

l 1 'i,,

qD gf, a

I aaa i a aas aaa sk,

"(j(j>>X, >, r ~i

(:,j T

f(

( j, (f,, (j; g W

(ar>> f Df(D( 'ir

'lL 1 "sI l )1! i!gi i

'pf 1j'(I sii s) lfFD

(',1

'(

i. A f f ji$ a i(g(

~ f f fg i(a i '>>'f 1ij 9

(

'((iiy f ij DDt'( f 0 $

r i fi D

~

a f,)

11<5,$

', D '

f>'

'1 (f ll i '( l i"P 5 11 D 0 ii I f j(il

$ Da "'f f 'fi

• ij'k((

a i "'if f i(tj f il 1 f'j f (j

jj E j s)

XJ

~

j lg 1

i jj 7 i

. Qr~WST 8'EIE Ii l/llilSS ROCHESTER GAS AND ELECTRIC CORPORATION o 89 EAST AVENUE, ROCHESTER, N.Y. 1464S 0001 TELEPHONE AREA CODE 7IS 546-2700 February 1,

1984 Director of Nuclear Reactor Regulation Attention:

Mr. Dennis M. Crutchfield, Chief Operating Reactors Branch No.

5 U.S. Nuclear Regulatory Commission Washington, D.C.

20555

Subject:

NUREG 0737, Item II.B.2, Plant Shielding R. E. Ginna Nuclear Power Plant Docket No.

50-244

Dear Mr. Crutchfield:

Previous RG&E letters dated December 15,

1980, September 4,

1981, November 25,

1981, December 2,

1982 and November 21, 1983 have described RG&E's planned and completed activities to meet post-TMI requirements for plant shielding.

The plant shielding topic reviews and necessary corrective actions were to increase the capability of operators to control and mitigate the con-sequences of an accident.

Shielding evaluations were to be performed for several specified areas within the plant and were to be considered in several other suggested areas including near the radwaste control panel.

RG&E performed many shielding evaluations and concluded that, using the required source

term, occupancy in the area of the existing radwaste panel would be severely restricted.

RG&E committed to relocate (and later to duplicate) the radwaste panel as a prudent course of action even though it is difficult to define when the radwaste equipment may be used.

Experience at TMI showed that existing radwaste equipment will not be used for long-term recovery and cleanup following accidents with similar fuel damage.

Only for significantly less severe conditions will the existing radwaste system be used for post-accident recovery.

The existing equipment is designed to meet GDC 60 so as to control suitably the release and to provide retention of gaseous and liquid effluents containing radioactive materials.

It was not RG&E's intention, in making the commitment to relocate some controls, that an inference be made that the radwaste processing equipment is required to mitigate the consequences of an accident except as necessary to retain effluents and control releases.

8402070 0~000P44 84020i pgp

@DOCK 0>

pop p

ea ll N

%1

~'l ")" ~

V C

I

ROCHESTER GAS AND ELECTRI ORP.

February 1,

1984 Mr. Dennis M. Crutchfield SHEET NO.

Following TMI, many new regulatory requirements were issued with short time constraints imposed for response.

As a result, responses were often submitted based upon scoping studies and preliminary analyses.

RGGE committed to relocate some controls as a prudent course of action to be responsive to TMI requirements and because the relocation would aid the company in meeting its established policy of keeping personnel radiation exposures as low as reasonably achievable.

Subsequent to performing the shielding analyses which defined the dose rates at the radwaste

panel, and following our commitment to relocate some controls as a prudent course of action because of the high dose rates, objectives were identified for the radwaste systems to meet TMI requirements.

Those objectives were to retain the access necessary to terminate

releases, to limit the radioactivity that might be transferred to the auxiliary building and to monitor important system parameters.

A review of existing plant controls showed that no additional plant features were necessary to meet the first two objectives.

The capability already existed within the control room to terminate releases and limit the transfer of radioactive material to the auxiliary building.

Certain parameters were identified to be provided at a remote location to meet the third objective.

Those parameters are listed in an RG&E letter dated November 21, 1983 and have been made available at two remote operating terminals.

The Ginna operators have the capability to terminate releases and retain effluents through the use of existing plant hardware in the control room.

In addition, remote indication to monitor important radwaste system parameters has been installed.

There-fore, access to the existing radwaste control panel is not required to control and mitigate the consequences of accidents and the TMI requirements are met with no increased permanent or temporary shielding at the radwaste panel.

V r truly yours, R

er W. Kober Vice President Electric and Steam Production

0 J

I, t

I