ML18038B632
| ML18038B632 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry |
| Issue date: | 02/23/1996 |
| From: | Salas P TENNESSEE VALLEY AUTHORITY |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| Shared Package | |
| ML18038B633 | List: |
| References | |
| NUDOCS 9603040248 | |
| Download: ML18038B632 (9) | |
Text
/
CATEGORY X
REGULA
.'NFORMATION DISTRIBUTIO SYSTEM (RIDS)
ACCLSSION NBR:9603040248 DOC.DATE: 96/0$ /23 NOTARIZED: NO FACIL:50-259 Browns Ferry Nuclear Power Station, Unit 1, Tennessee 50-260 BrOwns Ferry NuClear Power Station, Unit 2, Tennessee 50-296 Browns Ferry Nuclear Power Station, Unit 3, Tennessee AUTH.NAME AUTHOR AFFILIATION SALAS,P.
Tennessee Valley Authority RECIP.NAME REC P$ ENT AFFILIATION Document Control Branch (Document Control Desk)
DOCKET ¹ 05000259 05000260 05000296
SUBJECT:
For'wards proprietary adoption of GE SAFER/GESTR loss of cc)olant accident methodology. Encl withheld (r'ef 10CFR2.790(a)(4)).
DISTRIBOTSON CODE:
APOID COPIES RECEIVED:LTR I
ENCL l
SIZE:
TITLE: Pr6prietary Review Distribution Pre Operating License NOTES:
Operating R
E RECIPIENT ID CODE/NAME PD2-3 WILLIAMS,J~
INTERNAL: ACRS OGC/HDS3 EXTERNAL: NRC PDR COPIES RECIPIENT LTTR ENCL ID CODE/NAME 1
1 PD2-3-PD 1
1 6
6 FILE CEN'PER 01 1
0 1
0 COPIES LTTR ENCL 1
1 1
1 D
NOTE TO ALL "RIDS" RECIPIENTS:
PLEASE HELP US TO REDUCE WASTE'ONTACT THE DOCUMENT CONTROL DESKS ROOM OWFN 5D-S(EXT. 415-2083)
TO ELIMINATE YOUR NAME FROM DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEED!
TOTAL NUMBER OF COPIES REQUIRED:
LTTR 12 ENCL 10
\\
I,
Tennessee Vatley Authority. Post Office Box 2000, Decatur, Afabama 36609 February 23, 1996 U.S. Nuclear Regulatory Commission ATTN:
Document Control Desk Washington, D.C.
20555 Gentlemen:
In the Matter of
)
Tennessee Valley Authority
)
10 CFR 50. 46 (a) (3) (ii)
Docket Nos.
50-259 50-260 50-296 BROWNS FERRY NUCLEAR PLANT (BFN) - UNITS 1~
2~
AND 3 ADOPTION OF THE GENERAL ELECTRIC (GE)
SAFER/GESTR LOSS OF COOLANT ACCIDENT METHODOLOGY In accordance with the requirements of 10 CFR 50.46(a)(3)(ii),
TVA is reporting a change in the evaluation model utilized to analyze the Loss-of-Coolant Accident (LOCA) for BFN.
TVA is adopting the General Electric (GE)
SAFER/GESTR model for evaluation of the LOCA analysis for BFN.
The NRC accepted this model of LOCA analysis evaluation for use by the owners of Boiling Water Reactors (BWR)(BWR/3, BWR/4, BWR/5, and BWR/6) designed by GE.
This is discussed in the letter from C.
O. Thomas, NRC to J.
F. Quirk, GE (see Reference).
TVA will utilize the SAFER/GESTR model evaluation for LOCA analysis for Unit 2 cycle 9 operation and Unit 3 Cycle 8
operation'.
Unit 1 is in an extended outage; nevertheless, TVA anticipates utilizing the SAFER/GESTR model for Unit 1 when restarted.
As a result of using the SAFER/GESTR model for evaluating a
LOCA, the limiting License Basis fuel rod peak cladding temperature (PCT) for a postulated event is reduced by more than 50 degrees fahrenheit (F) and remains below 2200 degrees F.
Additionally, the application of this methodology results in an upper bound PCT of less than the Licensing Basis PCT and is less than 1600 degrees F.
Changing to the 0400(5 9603040248
'tf6022317 PDR ADQCK 05000259 p
C l,>>
J
U.S. Nuclear Regulatory Commission Page 2
February 23, 1996 SAFER/GESTR evaluation model does not require any changes in the parameters that initiate Engineered Core Cooling System logic.
Therefore, no Technical Specification change will be required to implement this change.
A plant specific analysis in support of the change to SAFER/GESTR model is provided in Enclosure 1.
This enclosed information is proprietary to GE and GE request that this document be withheld from public disclosure in accordance with 10 CFR 2.790(a)(4).
An affidavit supporting the request in accordance with 10 CFR 2.790(b)(1) is provided in with the analysis.
The commitments made in this letter are provided in Enclosure
- 2. If you have any questions please contact me at (205) 729-2636.
Si l
e alas a ager of Site Licensing Enclosure cc:
See page 4
-e Il
U. S. Nuclear Regulatory Commission Page 3
February 23, 1996
Reference:
NRC letter dated June 1,
- 1984, "Acceptance for Referencing of Licensing Topical Report NEDE-23785 Revision 1, Volume III(P),
The GESTR-LOCA and SAFER Models for the Evaluation of the Loss-of-Coolant Accident."
~
~
~
~
U.S. Nuclear Regulatory Commission Page 4
February 23, 1996 Enclosure cc (Enclosure):
Mr. Mark S. Lesser, Branch Chief U.S. Nuclear Regulatory Commission Region II 101 Marietta Street, NW, Suite 2900 Atlanta, Georgia 30323 NRC Resident Inspector Browns Ferry Nuclear Plant 10833 Shaw Road
- Athens, Alabama 35611 Mr. J.
F. Williams, Project Manager U.S. Nuclear Regulatory Commission One White Flint, North 11555 Rockville Pike Rockville, Maryland 20852