ML18039A272

Provides Status of Util Schedule for Completing Actions to Address NRC Identified Issues Re GL 89-10 Program Closure for Units 2 & 3

ML18039A272
Person / Time
Site:	Browns Ferry
Issue date:	03/16/1998
From:	Abney T TENNESSEE VALLEY AUTHORITY
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
GL-89-10, TAC-M75636, TAC-M75637, NUDOCS 9803250206
Download: ML18039A272 (10)

Text

CATEGORY REGUL RY INFORMATION DXSTRXBUTI H SYSTEM (RXDS)

ACCESSION NBR:9803250206 DOC.DATE: 98/03/16 .NOTARIZED: NO DOCKET FACIL:50-260 Browns Ferry Nuclear Power Station, Unit 2, Tennessee 05000260 50-296 Browns Ferry Nuclear Power Station, Unit 3, Tennessee 05000296 AUTH. NAME,. AUTHOR AFFILIATION ABNEY,T.E. Tennessee Valley Authority RECIP.NAME RECIPIENT AFFILIATION Document Control Branch (Document Control Desk)

SUBJECT:

Provides status of util schedule for completing actions to address NRC identified issues re GL 89-10 program closure for Units 2 S 3.

DISTRIBUTION CODE: A064D COPIES RECEIVED:LTR ENCL SIZE:

TITLE: Response to Generic Ltr 89-10, "Safety-Related MOV Testing &. Surveill T NOTES:

RECIPIENT COPXES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PD2-3-PD DEAGAZIO,A INTERNAL: QR AEOD/SPD/RAB FILE 'CE NRR/DE/EMEB RES/DST RES/DST/PRAB EXTERNAL: NOAC NRC PDR D

0 NOTE TO ALL "RIDS" RECIPIENTS:

PLEASE HELP US TO REDUCE WASTE. TO HAVE YOUR NAME OR ORGANIZATION REMOVED FROM DISTRIBUTION LISTS OR REDUCE THE NUMBER OF COPIES RECEIVED BY YOU OR YOUR ORGANIZATION, CONTACT.THE DOCUMENT CONTROL DESK (DCD) ON EXTENSION 415-2083 TOTAL NUMBER OF COPIES REQUIRED: LTTR 11 ENCL

0' Tennessee Va! ley Authority, Post Office Box 2000, Decatur, Atabama 35609-2000 March 16, 1998 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C. 20555 Gentlemen:

In the Matter of Docket No. 50-260 Tennessee Valley Authority 50-296 BROWNS FERRY NUCLEAR PLANT'BFN) UNITS 2 AND 3 GENERIC LETTER (GL) 8 9 1 0 I SAFETY RELATED MOTOR OPERATED VALVE TEST ING I

AND SURVE LLANCE I STATUS OF ACTIONS FOR PROGRAM CLOSURE ( TAC NOS. M75636 AND M75637)

This letter provides a status of TVA's schedule for completing actions to address NRC identified issues regarding the GL 89-10 program closure for,BFN Units 2 and 3.

On November 17 through November 21, 1997, NRC conducted an inspection (Inspection Report 97-11) of BFN's Unit 3 GL 89-10 program. Several issues were identified and characterized by the inspectors as requiring resolution prior to program closure by NRC. The primary issue identified involves design assumptions for valve factors made when the BFN GL 89-10 program was established. These assumptions relate to the effective friction factor under loaded conditions, i.e., when the MOV operates with a differential pressure (DP).

By letter dated December 15, 1997, TVA committed to take actions to resolve the issues identified by NRC. TVA also committed to provide a status of its progress in completing the actions described in the letter. Listed below are the commitments made by TVA and their status.

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U.S. Nuclear Regulatory Commission Page 2 March 16, 1998 TVA COMMITMENT TVA will revise the BFN GL'89-10 program to address the design input issues identified by NRC during IR 97-11 by January 31, 1998.

STATUS TVA has reviewed the valve types for BFN and made a determination of the appropriate valve factors associated with each valve type. The basis for the valve factors includes the consideration of DP test data from BFN, Sequoyah Nuclear Plant, NRC/Idaho National Engineering Laboratory (INEL) valve testing, Electric Power Research Institute (EPRI) Performance Prediction Program testing, and other utilities as applicable to the BFN valves.

Parameters for valve factor, stem factor coefficient of friction, and Load Sensitive Behavior (Rate of Loading) and the technical basis for the values used for each of these parameters has been documented in TVA calculation MD-Q0999-980001. Where applicable, statistical analysis has been used to determine appropriate values for stem factor coefficient of friction, and Load Sensitive Behavior. TVA considers that the actions regarding this commitment are complete.

TVA COMMITMENT TVA will revise the BFN Unit 3 Motor-Operated valve design calculations to reflect the GL 89-10 program design input revisions by March 31, 1998.

STATUS'VA is in the process of incorporating the design parameters described above into the BFN Unit 3 MOV calculations. TVA is on track to complete the Unit 3 MOV design calculations by March 31, 1998. MOV modifications required as a result of the parameter changes are planned, subject to material availability, to be implemented during the next Unit 3 refueling outage (Fall 1998).

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U.S. Nuclear Regulatory Commission Page 3 March. 16, 1898 TVA COMMITMENT TVA will revise the BFN Unit 2 Motor-Operated valve design calculations to reflect the GL 89-10 program design input revisions by August 31, 1998.

STATUS Based on the time required to complete the BFN Unit 3 MOV design calculations, and lessons learned during the process, TVA does not anticipate any problem in meeting its August 31, 1998, commitment for revising the BFN Unit 2 MOV design calculations. MOV modifications required as a result of the parameter changes are planned, subject to material availability, to be implemented during the next Unit 2 refueling outage (Spring 1999).

In summary, TVA is on schedule to meet the commitments in its December 15, 1997 letter regarding the issues identified by NRC during the BFN Unit 3 GL 89-10 closure inspection (IR 97-11) .

The due date for this letter was revised from March 2, 1998, to March 16, 1998, in accordance with TVA's commitment evaluation process. The revised date was discussed with E. H. Girard, NRC, Region II.

If you have any questions, please contact me at (205) 729-2636.

Si cerely, ne Manager of Li sing and Indus ry Affair cc: See Page

lt U.S. Nuclear Regulatory Commission Page 4 March 16, 1998'c:

Mr. Albert W. De Agazio, Project Manager U.S. Nuclear Regulatory Commission One White Flint, North 11555 Rockville Pike Rockville, Maryland 20852 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

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