ML18039A211

From kanterella
Jump to navigation Jump to search

Provides Schedule for Completing Actions Which Address NRC Identified Issues Re GL 89-10 Program Closure for Bfn,Units 1 & 2.Commitments Made by Util,Encl
ML18039A211
Person / Time
Site: Browns Ferry  
Issue date: 12/15/1997
From: Abney T
TENNESSEE VALLEY AUTHORITY
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
GL-89-10, TAC-M75636, TAC-M75637, NUDOCS 9712230018
Download: ML18039A211 (10)


Text

CATEGORY 1 REGULATO INFORMATION DISTRIBUTIO YSTEM (RIDS)

ACCESSION NBR:9712230018 DOC DATE: 97/12/15 NOTARIZED: NO FACIAL:50-260 Browns Ferry Nuclear Power Station, Unit 2, Tennessee 50-296 Browns Ferry Nuclear Power Station, Unit 3, Tennessee AUTH.NAME' AUTHOR AFFILIATION ABNEY,T.E.

Tennessee Valley Authority RECIP.NAME RECIPIENT AFFILIATION Document Control Branch (Document Control Desk)

SUBJECT:

Provides schedule for completing actions which address NRC identified issues re GL 89-10 program closure for BFN,Units 1

5 2.Commitments made by util,encl.

DISTRIBUTION CODE:

A064D COPIES RECEIVED:LTRj ENCL i

SIZE:

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

DOCKET 05000260 05000296 A

Surveill T RECIPIENT ID CODE/NAME PD2-3-PD INTERNAL: ACRS EN~T~ 1 R

D T/EIB/B RES/DST/PRAB EXTERNAL: NOAC COPIES LTTR ENCL 1

1 1

1 1

1 1

1 1

1 1

1 RECIPIENT ID CODE/NAME DEAGAZIO,A AEOD/SPD/RAB NRR/DE/EMEB RES/DST NRC PDR COPIES LTTR ENCL 1

1 1

1 1

1 1

1 1

1 0

D NOTE TO ALL "RZDSE 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 11

, ~

Tennessee Valley Authority, Post Office sox 2000Gecatur. Alabama 35609-2000 December 15, 1997 U.S. Nuclear Regulatory Commission ATTN:

Document Control Desk Washington, D.C.

20555 Gentlemen:

In the Matter of Tennessee Valley Authority Docket No. 50-260 50-296 BROWNS FERRY NUCLEAR PLANT (BFN)

- UNITS 2 AND 3 -

GENERIC LETTER (GL) 89-10, SAFETY-RELATED MOTOR-OPERATED VALVE TESTING AND SURVEILLANCE, PROGRAM CLOSURE (TAC NOS.

M75636 AND M75637)

This letter provides 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.

There were no operability concerns identified as a

result of the inspection.

However, several issues were identified and characterized by the inspectors as requiring resolution prior to program closure by NRC.

or IIIIIIIIIIIIIIIIIIlIIIIIIlII IIIIII The primary issue identified involves design assumptions f valve factors made when the BFN GL 89-10 program was 9'7122300i8 9'7i215

( t POR aaaCX OSOOaaeO P

pnR J

~ >

II~

I I

I ll I

I

U.S. Nuclear Regulatory Commission

>age 2

December 15, 1997 established.

These assumptions relate to the effective friction factor under loaded conditions, i.e.,

when the MOV operates with a differential pressure (DP).

At the time -.the BFN GL 89-10 program was established, and as recent as July 1995 (IR 50-259/260/296/95-19),

the assumptions used by TVA were considered valid based on the best available industry information.

Additionally, TVA used a safety factor of 1.2 to account for any uncertainties in the available information.

Since that time, additional test data has been obtained from TVA and other utilities.

At BFN, 17 additional DP tests have been performed.

At the time of the November,

1997, GL 89-10 inspection, TVA was in the process of evaluating the design assumptions based on available test data from BFN, other TVA nuclear sites, and the industry.

These assumptions relate primarily to factors under loaded conditions and -include the commonly used calculation terms, "valve factor" and stem factor coefficient of friction, and "rate of loading."

As part of the BFN Power Uprate Program, TVA submitted a

license amendment request on October 1,

1997, to uprate BFN's licensed reactor power by five percent.

TVA will be revising the design calculations for the GL 89-10 MOVs as part of the BFN Power Uprate Program to account for the higher system pressures.

The calculation revisions will reflect any revised design assumptions described above.

The schedule for Power Uprate implementation requires that the Unit 3

MOV design calculations be revised to support the Fall (October 1998) refueling outage.

Accordingly, TVA will revise the Unit 3 GL 89-10 design calculations by March 31, 1998.

For Unit 2, TVA will revise the GL 89-10 design calculations by August 31, 1998.

In summary, TVA is making the necessary technical assessment and program revisions to address the MOV=calculation issues identified by NRC during its GL 89-10 inspection of

i'

U.S. Nuclear Regulatory Commission Page 3

December 15, 1997 November 17 through 21, 1997.

The assessment and any needed program revisions will be completed by January 30, 1998.

Design calculations for the GL 89-10 MOVs will be revised for Unit 3 by March 31,

1998, and Unit 2 by August 31, 1998, in conjunction with the BFN Power Uprate Program.

TVA plans to provide a status letter by March 2,

1998, to inform NRC of the progress in completing the above actions.

The enclosure to this letter contains a summary of commitments made in this letter.

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

cerely,

~

n Ma@age of License.ng L, and Industry Affairs Enclose 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. Albert W.

De Agazio, Project Manager U.S. Nuclear Regulatory Commission One White Flint, North

'1555 Rockville Pike Rockville, Maryland 20852

~i 0

ENCLOSURE TENNESSEE VALLEY AUTHORITY BROWNS FERRY NUCLEAR PLANT (BFN)

UNITS 2 AND 3 GENERIC LETTER 89-10, SAFETY-RELATED MOTOR-OPERATED VALVE (MOV) TESTING AND SURVEILLANCE ACTIONS REQUIRED FOR PROGRAM CLOSURE COMMITMENT

SUMMARY

TVA will revise the BFN GL 89-10 program to address the design input issues identified by NRC during Inspection IR 97-11 by January 30, 1998.

2.

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.

3

~

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.

4.

TVA will provide a status letter by March 2, 1998, to inform NRC of progress in completing the actions described in this letter.

i

>r