ML18026B076
| ML18026B076 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 07/02/1984 |
| From: | Kammer D TENNESSEE VALLEY AUTHORITY |
| To: | Harold Denton Office of Nuclear Reactor Regulation |
| References | |
| GL-84-09, GL-84-9, TAC-55953, TAC-55954, TAC-55955, NUDOCS 8407090116 | |
| Download: ML18026B076 (8) | |
Text
DOCKET 0 05000259 05000?60 05000296
, ri.-~,
REGULATORYQIFORMATION DISTRIBUTION S'EM (RIBS)
ACCESSION NBR:8407090116 DOC,DATE: 84/07/02 NOTARIZED:
VES FACIL:50-259 Browns Ferry Nuclear Power Stations Unit 1< Tennessee 50 260 Browns Ferry Nuclear Power Stations Unit 2i Tennessee 50-296 Browns Ferry Nuclear Power Stations
-Unit 3E Tennessee AUTH BYNAME AUTHOR AFFILIATION KAMMERED AS>>
Tennessee Valley Authority RECIP ~ NAME RECIPIENT AFFILIATION
~DENTONiH.R>>
O,ffice of Nuclear Reactor Regulationi Director
,i
SUBJECT:
Forwards response to Generic Ltr 84-09.re recombiner capability requirements of'0CFR50.44(c)(3)(ii)Eper, 840508 request, Facilities do not rely on purge/repressurization;sys as primary means for hydrogen control.
DISTRIBUTION CODE:
A001S COPIES RECEIVED:LTR ENCL SIZE; TITLE; OR Submittal:
General Distribution NOTES!NMSS/FCAF 1cy.
1cy NMSS/FCAF/PM, OL;06/26/73 NMSS/FCAF 1cy ~
1cy NMSS/FCAF/PM, OL:06/28/74 NMSS/FCAF. 1cy ~
1cy NMSS/FCAF/PM>>
OL:07/02/76 05000259 05000260 05000296 RECIPIENT ID CODE/NAME NRR ORB2 BC 01 INTERNAL; ELD/HDS4 NRR/DL DIR METB REG 04 COPIES LTTR ENCL 7
7 1
0
,1 1
1 1
1 1
RECIPIENT ID CODE/NAME NRR/DE/MTEB NRR/DL/DRAB NRR/DS I/RAB RGN2 COPIES LTTR ENCL 1
0 1
1 EXTERNAL: ACRS NRC PDR NTIS NOTES:
09 02 6"
6 1
1 1
LPDR NSIC 03 05
-TOTAL NUMBER OF COPIES REQUIRED>>
LTTR 27 ENCL 25
)
Cl e
'i
TENNESSEE VALLEYAUTHORITY CHATTANOOGA. TENNESSEE 3740t 400 Chestnut Street Tower II July 2, 1984 Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, D.C. 20555
Dear Mr. Denton:
In the Matter of the Tennessee Valley Authority Docket Nos. 50-259 50<<260 50-296 Enclosed is our response to D. G. Eisenhut's letter to All Licensees of Operating Reactors dated May 8, 1984, subject, Recombiner Capability Requirements of 10 CFR 50.44(c)(3)(ii) (Generic Letter No. 84-09), for the Browns Ferry Nuclear Plant.
As requested, our response addresses the applicability of the generic studies submitted by the Mark I Owners'roup to Browns Ferry and additional information relative to the three criteria given in the letter.
As explained more fully in the enclosure, it has been determined that Br owns Ferry does not rely upon the purge/repressurization system as the primary means for hydrogen control.
If you have any questions, please get in touch with us through the Browns Ferry Project Manager.
Subscribe+
an sworn be re me this ~
day o E
Very truly yours, TENNESSEE VALLEY AUTHORITY p5~~+
D. S.
Kammer Nuclear Engineer 1984.
Not y Public My ommission Expires Enclosure cc (Enclosure):
U.S. Nuclear Regulatory Commission Region II ATTN:
James P. O'Reilly, Regional Administrator 101 Marietta Street, NW, Suite 2900 Atlanta, Georgia 30323 An Equal Opportunity Employer Mr. R. J. Clark Browns Ferry Project Manager U.S. Nuclear Regulatory Commission 7920 Norfolk Avenue
PDR pcs 1l
F 7
4 0
k
~
4
r gr ENCLOSURE
RESPONSE
TO GENERIC LETTER 84-09 DATED MAY 8, 1984 RECOMBINER CAPABILITY REQUIREMENTS OF 10-CFR 50.44(c)(3)(ii)
BROWNS FERRY NUCLEAR PLANT In response to the recombiner capability requirements of 10 CFR 50.44(c)(3),
the BWR Mark I Owners'roup prepared NED0-22155, "Generation and Mitigation of Combustible Mixtures in Inerted BWR Mark I Containments."
This report is applicable to Browns Ferry units 1, 2, and 3 ~
The technical criteria outlined in the generic letter and the position of Browns Ferry for each are as follows.
1.
NRC CRITERION The plant has technical specifications (limiting conditions for operation) requiring that, when the containment is required to be
- inerted, the containment atmosphere be less than four percent oxygen.
BROWNS FERRY POSITION Browns Ferry technical specification 3.7.A.5 requires the containment atmosphere to be less than four percent oxygen by volume when the containment is required to be inerted.
2.
NRC CRITERION The plant has only nitrogen or recycled containment atmosphere for use in all pneumatic control systems within containment.
BROWNS FERRY POSITION The control air system, which provides pneumatic control to systems inside containment, provides only recycled containment atmosphere to those systems.
It is possible to supply air to this system, but this is only used as a contingency action when nitrogen is not available.
A modification is planned to provide an alternate source of nitrogen.
I ll I"
t ll e
r h
3.
NRC CRITERION There are no potential sources of oxygen in containment other than-that resulting from radiolysis of the reactor coolant.
Consideration of potential sources of inleakage of air and oxygen into containment should include consideration of not only normal plant operating conditions but also postulated loss-of-coolant accident conditions.
These potential sources of inleakage should include instrument air systems, service air systems, MSIV leakage control systems, purge lines, penetrations pressurized with air and inflatable door seals.
BROWNS FERRY POSITION There are no potential sources of oxygen in the containment during normal plant conditions or any postulated loss-of-coolant accident conditions other than that resulting from radiolysis of the reactor coolant.
The plant ventilation lines are isolated during normal plant operation and would remain isolated following an accident signal.
The instrument air system provides only nitrogen to'he containment.
The service air systems and purge inlet lines remain isolated following an accident.
Browns Ferry does not have any inflatable door seals or a main steam isolation valve leakage contr ol system.
The containment penetrations with bellows are filled with air at atmospheric pressure.
The penetrations are rated to withstand the design and accident pressure of the containment; therefore, there is no potential for the air in the penetration bellows to leak into the containment atmosphere.
Based on the above information, it is determined that, with respect to 10 CFR 50.44(c)(3),
Browns Ferry does not rely upon the purge/repressurization system as the primary means for hydrogen control.
~W I
4