ML19343A320
| ML19343A320 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 09/09/1980 |
| From: | Mills L TENNESSEE VALLEY AUTHORITY |
| To: | Harold Denton Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8009170206 | |
| Download: ML19343A320 (3) | |
Text
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! TENNESSEE VALLEY AUTHORITY
' CH ATTANOOGA. TENN ESSEE 37401 400 Chestnut Street Tower II September 9, 1980 Mr. Harold R. Denton, Director Office of. Nuclear Reactor Regulation U.S. Nuclear Regulatory. Commission Washington, DC 20555 1
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Dear Mr. Denton:
In the Matter of the
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Docket No. 50-259 Tennesse Valley Authority
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~1n response to C, G. Eisenhut's July 25, 1980, letter to H. G.
Parris, and as a result of the August 4,1980, meeting in Bethesda, with R. Bernero of the Division of Systaas and Reliability Research, enclosed are our comments regarding our understanding of the extent of TVA participation in the Interim Reliability Evaluation Program (IREP) Phase II study. The enclosed comments are' based on the assumption that TVA will. perform an independant reliability
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evaluation of unit 1 of the Drowns Ferry Nuclear Plant. However, if TVA decides not to. perform this risk assessment of Browns Ferry unit 1, TVA will notify you and reevaluate our present plans for participation in Phase II of IREP. TVA anticipates that a decision to perform this risk assessment will be made by mid-October 1980.
To ensure proper coordination of the IREP effort within TVA, we would greatly appreciate your continuing to forward all requests i
for information and all transmittals of information to this office.
l Very truly yours, TENNESSEE VALLEY AUTHORITY
. M. Mill's, M< nager Nuclear Regulation and Safety i-Subscribe a d sworn to efor.
1 1980.
me this day of
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. Enclosures 4
80091Jo 2 O4 An Equal Opportunity Employer i.
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p ENCLOSURE RESPONSE TO D. G. EISENHUT'S JULY 25, 1980, LETTER TO H. G. PARRIS INTERIM RELIABILITY EVALUATION PROGRAM (PFASE II)
FOR BROWNS FERRY NUCLEAR PLANT UNIT 1 1
'IRC will retain Brouns Ferry 1 in the IREP program uith the study to be perforned 5y INEL in Idaho Falls. TVA has orovided to INEL an information package (listed in Attaenment 1) consisting of systen descriptions, applicable drawings, plant emergency and operating procedures. TVA will provide, in a future submittal, a copy of the Operations Training Program to comply with the request for information.
TVA will not provide personnel to work in Idaho Falls with INEL.
2.
TVA has initiated preliminary steps to perform an independent risk assessment on Browns Ferry 1.
TVA believes that this approach would be beneficial for the following reasons:
(a) TVA can provide a much greater participation by its design and operating perscnnel if the risk asssessnent is headquartered in Knoxville. This should orovide a more accurate mathematical model of the plant.
(b' Since the TVA personnel will be deeply involved in the construction of the plant mathematical model, they should be able to use the model for evaluating hardware mealfications and changes in plant maintenance procedures as these arise in the future.
(c) The heavy involvement of TVA pe-annel in this independent study will enable TVA to gain experiec in performing risk assessment studies.
This experience will et-le TVA to more efficiently handle the subsequent risk assessnent stu s which will t necessary for other TVA plants besides Browns Ferry.
(d) TVA will provide the results of its independent sttdy to the NRC in order to provide a comparison between the TVA s udy and the INEL study. This would enable NRC to evaluate both stu les and the overall approach used before finalizing the proced res to be used in Phase III of IREP.
3 It will be very difficult for TVA to perforn or fund any special analyses arising from the INEL study cencerning plant responses wh'ch may not be available from existing plant documentation. We undert tand that the NRC will nininize such requests and consult with TVA before initiating any such requests.
4 TVA believes that the NRC should set up a formal procedure to factor in the ecmments of the four utilities involved in Phase II of IREP concerning the procedural guide for further reliability evaluation studies..We understand that the NRC will receive comments through the Atomic Industrial Forum and the IEEE but believe-the comments from the four utilities involved in Phase II of IREP will be significant enough to merit a separate channel of communication. We request,that the NRC initiate a procedure for such communication.
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O ATTACHMENT 1 LIST OF INFORMATION SUBMITTED TO If!FL FOR IREP STUDY 1.
Conrol diagrams - 47W610 series 2.
Logic diagrams - 47W611 series 3
Flow diagrams -
(a) General plant - 47W800-1 series (b) Systems L7W500 series 4.
AC auxiliary pouer system -
(a) Key diagram - 15N500 series (b) Single line diagrams and schematics - 45N700 series 5.
250V de system -
(a) Key diagram, single line diagrams, and schematics - 45N700 series 6.
Equipment plans 47W200 series 7.
System descriptions - Text material from applicable FSAR sections 9.
Plant System Operating Instructions (301's), SOI 1 through 00 9
Emergency Operating Instructions (E0I's), E0I 1 through 49 NOTE: The only remaining item of information to be provided to INEL is a copy of the Operations Training Program.
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