ML18029A708
| ML18029A708 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry |
| Issue date: | 07/15/1985 |
| From: | Domer J TENNESSEE VALLEY AUTHORITY |
| To: | Vassallo D Office of Nuclear Reactor Regulation |
| References | |
| RTR-NUREG-0737, RTR-NUREG-737, TASK-2.F.2, TASK-TM GL-84-23, TAC-45116, TAC-45117, TAC-45118, NUDOCS 8507220141 | |
| Download: ML18029A708 (6) | |
Text
REGULATORY I RMATION DISTRIBUTION SYS (RIDS)
MJ
~
+
e
'ACCESSION NBR ~ 8507220 1 4 1 DOC ~ DATE 85/07/1 5 NOTARIZED YES,,
DOCKEiT FACIL'150 259 Browns Fer ry Nuclear Power Stations Unit 1< Tennessee 05000259 50 260 Browns Ferry Nuclear Power Stationi Unit 2< Tennessee 05000260 50 296'r owns Ferry Nuclear Power Stations Unit 3~ Tennessee 050Q0296
'AUTH'AME AUTHOR AFFILIATION DOMERgJ ~ AD Tennessee Valley Authority RECIP, NAt4E RECIPIENT AFF ILIATION VASSALLOiDiB~
Operating Reactors Branch 2
SUBJECT:
Responds to request for addi info re high drywell -temp per response to Generic Ltr 84-23 "Reactor Vessel l'later-Level Instrumentation in BNRs." Evaluation of cost 5 feasibility of mod to ref legs inside drywell underway'ISTRIBUTION CODE':
A002D
'COPIES RECEIVED:LTR ENCL SIZE ~
TITLEt OR Submittal:Inadequate Core Cooling (Item II~ F ~ 2)
GL 8?
28 NQTESg NMSS/FCAF icy, 1cy NMSS/FCAF/Pth, OL',06/26/73 NMSS/FCAF 1cy, icy NMSS/FCAF/PM'L':06/28/74 NESS/FCAF 1cy, icy NMSS/FCAF/PM.
OL':07/02/76 05000259 05000260 05000296 EXTERNAL; 20X NRC PDR NOTES!
Q 2,i RECIPIENT ID CODE/NAME'-
INTERNAL:'CRS 17 ttRR SHEAg J 01 NRR/DL/ORAB 08 NRR/DSI DIR 09-NRR SB 14 OQ COPIES LTTR ENCL 1
1 1
1 10 10 1
1 1
1 1
1 1
1 1
1 1
1 1
1 2'
RECIPIENT ID CODE/NAtlE NRR-ORB2 LA LPDR NSIC 03 06 ADM/LFMB NRR/DHFS/HFEB15 NRR/DL/ORB5 NRR/DSI/CPB 10 NRR/DSI/RSB 13 RGN2 07 COPIES LTTR -ENCt-1 1
0, 1
1 1
1 3
3 1'
1 1
1 1
1
.TOTAL NUMBER OF COPIES REQUIRED'TTR 32 ENCL 31
<<r
>>W>>v Wr
>>>> C1 fvvi
>>w e v <<o>> 'llfI fg
~
oo 1
rvi<<
<<f vl 4
~ I
~ W-<>W 1 "w X
>>4 W
ill+f
' >>V>>
Cg(IW I
fv 1 1,
Il I~I WI '1
' +
<<<<41>>I I
<<I Il
'v M
I v<<
'I '4O fI
>>IV I>> il 14 1, 'I
~
~
C>> I'4 IW
~ g<<o
>>wwr" f 1f'I' "I I!1 1 t f i>>)
~ 41 v<<f
'<<CI" f 1(
fv rwf
'll I,
>> 'll
~Wr p
ll V ~ Vvfyk>>sv 1
4!1 I,>>
rx
'I >>o <<
~
~ 'I <<
v '1 go 1<<f1 f f vl C1,<<
>>fan 1>>C 1;Io q <<>>,.
l' fxr
'I [
'l>>,
qfp
~
I gf
~
I 1 )w>>r r'
""WW<<f 1 <<>>>>>>:,>>,4<<'1 g
vs 14 14 vw Ifi I fl Cs v
~
I V<<
I 1
v 4llv CY>>
x>>
I, ll
<> '<<v II
) )i
~
1
<<1 1<<'1 fi'ir f'Xv Ii 3
)
11
] t WW
- ).
41 1
'4I' I
I,t>>
J I
1 C'
)4 ~
y'll,.v
- r<< kglff C
44
N TENNESSEE VALLEYAUTHORITY CHATTANOOGA. TENNESSEE 37401 400 Chestnut Street Tower II July 15, 1985 Director of Nuclear Reactor Regulation Attention:
Mr. Domenic B. Vassallo, Chief Operating Reactor Branch No.
2 Division of Licensing U.S. Nuclear Regulatory Commission Washington, D.C.
20555
Dear Mr. Vassallo:
In the Matter of the Tennessee Valley Authority Docket Nos.
50-259 50-260 50-296 By letter from J.
W.
Hufham to you dated April 8,
- 1985, we submitted a partial response to Generic Letter 84-23, Reactor Vessel Water Level Instrumentation in BWRs, for the Browns Ferry Nuclear Plant.
In our response, we committed to provide additional information regarding the high drywell temperature concern by July 15, 1985.
That information is enclosed.
If you have any questions, please get in touch with us through the Browns Ferry Project Manager.
Very truly yours, TENNESSEE VALLEY AUTHORITY
.Sworn to and subscribe be ore me
,.this
~ day of 1985 e
J.
A. Domer, Chief Nuclear Licensing Branch Notary Public My Commission Expires Enclosure cc:
See page 2
8507220i4i 8507i5 PDR ADOCK 05000259 P
PDRp An Equal Opportunity Empioyer
l
Director of Nuclear Reactor Regulation July 15, 1985 cc (Enclosure):
U.S.
Nuclear Regulatory Commission Region II Attn:
Dr. J.
Nelson Grace, Regional Administrator 101 Marietta Street, NH, Suite 2900 Atlanta, Georgia 30323 Mr. R. J. Clark Project Manager Browns Ferry Nuclear Plant U.S. Nuclear Regulatory Commission 7920 Norfolk Avenue
- Bethesda, Maryland'0814
ENCLOSURE ADDITIONAL INFORMATION.REGARDING *HIGH -DRYWELL TEMPERATURE BROWNS FERRY NUCLEAR PLANT
(
REFERENCE:
GENERIC LETTER 84-23)
High Drywell Temperature TVA is evaluating the cost and feasibility of minimizing the vertical drops of the reference legs inside the drywell to one to two feet by bringing the reference legs outside the 'drywell at a higher elevation using existing penetrations.
This modification is described in Section 6.1.2 of the S.
Levy, Inc., report 8211, Review of BWR Reactor Vessel Water Level Measurement Systems.
NRC review of this report was acknowledged in Generic, Letter 84-23.
This solution to the high drywell temperature issue appears to be the best and most cost effective provided the existing drywell penetrations can be used.
We are still in the process of ensuring that this modification is feasible, and that implementation will not involve an unreviewed safety question.
Since the evaluation of this design change is not yet complete, we cannot firmly commit to a particular modification or a completion date.
We will submit an updated response by October 15, 1985.