ML18031B026
"Draft Meeting" is not in the list (Request, Draft Request, Supplement, Acceptance Review, Meeting, Withholding Request, Withholding Request Acceptance, RAI, Draft RAI, Draft Response to RAI, ...) of allowed values for the "Project stage" property.
| ML18031B026 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 11/17/1986 |
| From: | Mason C TENNESSEE VALLEY AUTHORITY |
| To: | Bernero R Office of Nuclear Reactor Regulation |
| References | |
| TAC-63178, NUDOCS 8611250382 | |
| Download: ML18031B026 (6) | |
Text
REGULATOR INFQRNATION DISTRIBUTION TEf'f (R IDS>
ACCESSION NBR: 8611250382 DOC. DATE: 86/11/17 NOTARIZED:
NO DOCKET 5 FAC 1L: 50-259 Brogans Fev rg Nuc leav Power Stations Unit ii Tennessee 05000259 50-260 Brains Fev v g Nuc leav Pouer Station.
Unit 2.
Tennessee 05000260 50-296 Brogans Fevrg Nucleav Pouer Stations Unit Si Tennessee 05000296 AUTH. NANE AUTHOR AFFILIATION MASON> C. C.
Tennessee Valley Authov itg REClr. NAi'fE RECIPIENT AFFILIATION BERNEROi R. N.
Division of Boiling Mater Reactov (BLJR) Licensing
SUBJECT:
Responds to SA Mhite 860815 ltr summav izing v esults of 860731 meeting v e PRA 5 request fov documentation concerning v'isk assessment of facility.Util agv ees elrisk assessment activities v cached in meeting 5 commits to listed actions.
DISTRIBUTION CODE: *00ID COPIES RECEIVED: LTR
~
ENCL O SIZE:
TITLE:
QR Submittal:
Genev'al Distr i but ion NOTES: NNBS/FCAF 1 c g.
NNBS/FCAF/Pf'f 1 c g.
OIA 1 c g.
GROTENUI8, N 1 c g.
05000259 NNBB/FCAF 1 cg.
NNBB/FCAF/Pl'f 1 c g.
OIA 1 c g.
GROTENHUIS, 5 1 cg.
05000260 NNSS/FCAF ice.
NYiSS/FCAF/Pf'f ice.
OIA icy.
GROTENHUIS, 5 1 cg.
05000296 RECIPIENT ID CODE/MANE BWR EB BMR FQB BMR PD2 PD 01 BMR PBB COPIES LTTR ENCL RECIPIENT ID CODE/NAt'fE BMR EICBB BMR PD2 LA GEARS> G BMR RSB COPIES LTTR ENCL INTERNAL: ACRB ELD/HDBO NRR/GRAB RGN2 6
1 1
ADN/LFMB NRR/DHFT/TSCB E
04 EXTERNAL:
EGSG BRUBKE> S NRC PDR 02 NOTES:
LPDR NSIC 03 05 TOTAL NUf'fBER OF COPIES REQUIRED:
LTTR 33 ENCL
,.1
~
CJ FI 1
II Z;
I'
$ <<<<Z J
/
~
TENNESSEE VALLEYAUTHORITY CHATTANOOGA. TENNESSEE 3740t 6N 38A Lookout Place November 17, 1986 Mr. Robert M. Bernero Director of BWR Licensing Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, D.C.
20555
Dear Mr. Bernero:
BROWNS FERRY NUCLEAR PLANT (BFN) UNITS 1, 2, AND 3 UNIT 1
PROBABILISTIC RISK ASSESSMENT (PRA)
This letter is in response to your letter of August 15, 1986 to S.
A. White, summarizing the results of the July 31, 1986 meeting.
Your letter also requested submittal of documentation related to a risk assessment of BFN performed by the Tennessee Valley Authority (TVA).
This PRA document is only in preliminary draft status with numerous adjustments required to make it accurately reflective of plant conditions including:
the plant model used was based on design drawings reflecting the design circa 1980, rather than the current as-constructed configuration; does not incorporate modifications made to the plant in recent years; does not completely address operator recovery actions; does not have complete operator and plant review; does not have an independent technical review; does not fully credit the control rod drive hydraulic system; does not have an uncertainty analysis necessary to put the sequence probabilities in perspective; and all plant damage states were not reanalyzed crediting the reactor building model; therefore, the reported consequences and total risk curves are based upon conflicting assumptions.
TVA has reviewed the present status and future direction of the BFN risk assessment activities along with the agreements reached in the July 31 meeting and commit to the following actions:
0 (1) Three copies of the incomplete and unreviewed Browns Ferry PRA document will be provided to you under separate cover.
Due to the incomplete and unreviewed nature of this document, I do not consider it suitable for docketing as part of the BFN official record and request that it not be placed in the BFN docket files.
One of these copies is included for placement in the NRC Public Document Room.
(2)
As indicated in the previous correspondence, the PRA is incomplete and unreviewed.
Before TVA will consider classifying it as a working
- document, a thorough review, assessment, upgrade and uncertainty analysis must be accomplished'herefore, I
am planning a comprehensive PRA upgrade effort to begin shortly which will be completed sometime after the restart of unit 2.
During this peri'od of upgrade, I look forward to interaction with you and your staff.
Since we were not able to meet in September as previously proposed, my staff will contact you in November, to arrange a discussion of the upgrade plan.
Following completion of this'pgrade effort, I will provide you with the findings and schedule any additional meetings with you to discuss the results.
ADOCK 0500025~
8b11250382 8b1117 i
yer i
'b PDR ADO An Equal Opportunity Employer I
I
Mr. Robert M. Bernero November 17, 1986 (3)
In order to demonstrate the severe accident characterization of the Browns Ferry Plant, I have scheduled the application of the IDCOR Individual Plant Evaluation methodology to BFN.
Upon completion and review of this evaluation, my staff can meet with you and your staff to discuss the findings, if you so desire.
The approach outlined above will satisfy your near-term
- needs, provide assurance of the acceptable nature of severe accident characteristics of Browns Ferry, and allow TVA to complete its PRA activities in a manner consistent with other plant activities and efficient use of scarce resources.
If you have any questions concerning this approach, please inform my licensing staff at your earliest convenience.
Very truly yours, TENNESSEE VALLEY AUTHORITY C.
C.
Mason Acting Manager of Nuclear Power CQ:
Mr. R. J. Clark U.S.
Nuclear Regulatory Commission Browns Ferry Project Manager 7920 Norfolk Avenue
- Bethesda, Maryland 20814 U.S.
Nuclear Regulatory Commission Region II Attn:
Dr. J.
Nelson Grace, Regional Administrator 101 Marietta Street, NW, Suite 2900 Atlanta, Georgia 30323 Mr. James Taylor, Director Office of Inspection and Enforcement U.S.
Nuclear Regulatory Commission Washington, D.C.
20555
. ~
1 ol