ML20198P466
| ML20198P466 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 10/31/1997 |
| From: | Abney T TENNESSEE VALLEY AUTHORITY |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| GL-97-04, GL-97-4, NUDOCS 9711070176 | |
| Download: ML20198P466 (4) | |
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Tennmec Va y Amy W.M Ohe Da OixM Deuy Anea MN October 31, 1997 U.S. Nuclear Regulatory Commission 10 CFR 50.54 (f)
ATTN:
Document Control Desk Washington, D.C. 20555 Gentlemen:
In the Matter of
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Docket Nos. 50-259 Tennessee Valley Authority
)
50-260 50-296 BROWNS FEPRY NUCLEAR PLANT (BFN) - RESPONSE TO NRC GENERIC LETTER (GL) 97-04, ASSURANCE OF SUFFICIENT NET POSITIVE SUCTION HEAD (NPSH) FOR EMERGENCY CORE COOLING AND CONTAINEMNT HEAT REMOVAL PUMPS On October 7, 1997, the Nuclear Regulatory Commission issued the referenced generic letter regarding degraded performance of Emergency Core Coo).ing System pumps.
The GL required, within 30 days, a written response indicating ;a) whether or not the requested information will be submitted, and (b) whether or not the requested information will be submitted within the requested time periot'.
By this letter, TVA is providing the required BFN 30-day response, TVA is participating in a Boiling Water Reactor (BWR) Owner's Group effort which has the objectives of reviewing current BWR industry NPSH calculation methodology and recommending a consistent approach for utility 90-day response to this GL.
The information to be contained in the 90-day response will provide assurance to the Staff that NPSH issues are being d
adequately addressed.- -The BWROG established dialog with the stcff prior to the issuance of this GL and plans to continue
~ chat interaction so that NPSH issues are properly addressed.
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r U.S. Nuclear Regulatory Commission Page 2 October 31, 1997 TVA intends to provide a 90-day response to the GL for Units 2 and-3, incorporating the recommendations resulting from the BWR Owners Group NPSH Committee and address the requested information.
TVA expects to submit this information by January 5, 1998.
Unit 1 is shutdown and in an extended outage.
Therefore, TVA will evaluate the impact of NPSH for emergency core cooling.
containment heat removal pumps on Unit 1 prior to its restart.
The commitments made in this response are provided in the enc],osure.
If you have any questions regarding this please contact me at (205) 729-2636.
Si cerely,
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ney l
Manager of Lice 1 g and Industry ffairs V
Subscribed and sworn to before me on this 3\\wT day of October 1997.
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hdw CL h cJ Notary Public My Commission Expires Enclosure cd::
See page 3
U.S. Nuclear Regulatory Commission Page 3 October 31, 1997 Enclosure cc (Enclosure):
Mr. Mark S.
Lesser, Branch Chief U.S. Nuclear Regulatory Commission Region II 61 Forsyth Street, S. W.
Suite 23T85 Atlanta,-Georgia 30303 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
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,e ENCLOSURE TENNESSEE VALLEY AUTHORITY BROWNS FERRY NUCLEAR PLANT (BFN)
UNITS-1,~2, AND 3
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RESPONSE TO NRC GENERIC LETTER 97-04, ASSURANCE OF SUFFICIENT NET POSITIVE SUCTION HEAD FOR EMERGENCY CORE COOLING AND CONTAINMENT HEAT REMOVAL PUMPS LIST OF COM4ITHENTS 1.
TVA intends to provide a 90-day response to the Generic Letter for-Units 2 and 3.
TVA expects to-submit this response-by January 5, 1998.
2.-
TVA will evaluate the Ampact of net positive suction head for emergency core cooling and containment heat removal pumps on Unit 1 prior to its restart.
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