ML17256A399

From kanterella
Jump to navigation Jump to search
Forwards Response to NUREG-0916 Re Restart After 820125 Tube Rupture Incident.Based on Response to Item 2C(2),revised Tech Specs Re Primary Coolant Activity Will Be Requested
ML17256A399
Person / Time
Site: Ginna Constellation icon.png
Issue date: 11/22/1982
From: Maier J
ROCHESTER GAS & ELECTRIC CORP.
To: Crutchfield D
Office of Nuclear Reactor Regulation
Shared Package
ML17256A400 List:
References
RTR-NUREG-0916, RTR-NUREG-916 NUDOCS 8211290410
Download: ML17256A399 (4)


Text

REGULATORY Il'RMATION DISTRIBUTION SYST t (RIDS)

ACCESSION NBR ~ 821 1?90410 DUC ~ DATE ~ 82/1 1/22 NOTARIZE NO DOCKET FACIL:50 244 Robert Emmet Ginna Nuclear Plant~ Unit li Rochester G 05000244 AUTH, NAME AUTHOR AFFILIATION MAIERpJ,ED Rochester Gas 8 Electric Corp+

REC IP, NAME RECIPIENT AFFILIATION CRUTCHFIELDg D, Operating Reactors Branch 5

SUBJECT:

Forwards response to NUREG"0916 re restart after 820125 tube rupture incidentiUased on response to Item 2C(2)~revised Tech Specs re primary coolant activity will be requested' DISTRIBUTION CODE cga';v.

D007S COf IES RECEIVED LTR g ENCL ~ ,1 SIZE ~ +f TITLE: Ginna (50-244) Steam Generator Tube Failure NOTES: NRR/DL/SEP 1 cy ~ 05000244 w'~.4,g Q;M RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTlR ENCL ID CODE/NAME LTTR ENCL NRR ORU5 BC INTERKAL: IE/DEP IE/DRP DIR NRR/DE DIR NRR/DL DIR 01 13 08 07 7 el NRR DIR '2 IE/DEQA DIR NHR/DHFS DIR 09 FILE ADSA 11 NRH/DST D IR 10 REG 04 RGN1 06 EXTERNAL: ACHS 14 10 LPDR 03 NRC PDR 02 1 1 NSIC NTIS 1 1 NOTES: 1 C TOTAL NUMBER OF COPIES REQUIRED: LTTR 33 ENCL 33 I

) RR Rim g I 'JR' 'f ) s> l

'Irl Il 1'N.)

ll')')1

>rR ~ N f Rfm tm R lip

'IR mmm" m l(

r) t i( i I mp I.;w) n)R Ii

~ Ii I

'1 II Rr'i 1

) I' '1 i) ll c ') R,N I w

~

wllw) NR i R I>> il'",f jr,t),,t i NR1 l7) 'Rri II g I "l.g ll II

>>1 1 'r) 1:1'1 lt '\ q ) aJ RR). >>>>cr

)>> f 77 i mp rmr 7'Ri( I'i iip

'i g'l, mr>>.y w).-l N 1 I 'wr ll Iw 1' )lp 1 N)ll Rfi ig '1 'ir1 1 l r) r) 1 1 j 'll Il ',ms 71" RP rw iI

'w III 1

'I'"

1RR j tf ll NRN t 'Rf) 1 i '1rm(Rrm 'I I RW'~) lf II w z w ll ll l'

)my RN mp N f l 'j Rl lj "w N I "li>>

'gT l)1 t %l ~M) I ~l >>Ilf S 4 ~

,I1 N ll m R

km, <

n l m Rli,"1 II "m

~ 5>> lk l(g I.N

,l, Npl , N R

'I gwK R ll I i't 71tX1

-,r lf p' tI ll w

f 1

'p < l>, r $ R 'IIhl 7 " w ' '

7>>m 7>>

I L LIr 0%r ~

SIIEPiE /////////////

//// /////////////

ZK roar ROCHESTER GAS AND ELECTRIC CORPORATION ~ 89 EAST AVENUE, ROCHESTER, N.Y. 14649 TELEPHONE AREA CODE TI6 546-2700 November 22, 1982 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.: Response" to Safety Evaluation Report NUREG 0916 Steam Generator Tube Rupture Incident R. E. Ginna Nuclear Power Plant Docket No. 50-244

Dear Mr. Crutchfield:

The Safety Evaluation Report (NUREG-0916) related to the restart of Ginna after the tube rupture incident on January 25, 1982 and license conditions 2C(1) to 2C(20) require Rochester Gas and Electric Corporation to address several long term items. The enclosed report contains our response to those long term items.

Based on our response to item 2C(2), we will be requesting a revision in the Technical Specifications for primary coolant activity in the near future.

Very truly yours, Jo E. Maier Enclosure ~oo 7

'/~

821122.

t" 82112eo<110 0S0OO2a<

pga ggOGl pg l P

t t

F l g i I I'

C C,~

0 I I ~ ~

yl l >

jl,

) 'I