ML18039A609

Provides Supplemental Info Requested by Ltr Dtd 981019 to Support NRC Staff Review of Proposed Tech Specs Change TS-393.No Commitments Contained in Ltr.With Two Oversize Drawings

ML18039A609
Person / Time
Site:	Browns Ferry
Issue date:	11/13/1998
From:	Abney T TENNESSEE VALLEY AUTHORITY
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML18039A610	List: ML18039A609 ML18039A616 ML18039A618
References
CON-TVA-BFN-TS-393 TAC-MA1304, TAC-MA1305, TVA-BFN-TS-393, NUDOCS 9811240029
Download: ML18039A609 (10)

Text

CATEGORY 1

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REGULA mY XNFORMATION DISTRIBUTIO YSTEM (RIDS)

ACCESSION NBR:9811240029 DOC.DATE: 98/11/13 NOTARIZED: NO FACIL:50-260 Browns Ferry Nuclear Power Station, Unit 2, Tennessee DOCKET 05000260 I

50-296 Browns Ferry Nuclear Power Station, Unit 3, Tennessee 05000296 AUTH.NAME AUTHOR AFFILIATION ABNEY,T.E. Tennessee Valley Authority RECIP.NAME -RECIPIENT AFFILXATION Records Management Branch (Document Control Desk)

SUBJECT:

Provides supplemental info recpxested by ltr support NRC staff review of proposed Tech Specs Change drd 981019 to TS-393.No commitments contained in ltr.With one oversize A drawin g T DISTRIBUTION CODE: D030D COPIES RECEIVED:LTR ENCL SIZE:

TITLE: TVA Facilities - Routine Correspondence E NOTES:

RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL XD CODE/NAME LTTR ENCL PD2-3 1 1 PD2-3-PD 1 1 DEAGAZIO,A 1 1 INTERNAL: ACRS '1 1 FILE CENTER 1 1 OGC/HDS3 1 0 R E SSEB SES 1 1 EXTERNAL: NOAC 1 1 NRC PDR 1 1 D

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N NOTE TO ALL "RIDS" RECIPIENTS:

PLEASE HELP US TO REDUCE WASTE. TO HAVE YOUR NAME OR ORGANIZATION REMOVED FROM DISTRZBUTION 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 9 ENCL 8

4 Tennessee Valley Authority, Post Office Box 2000, Decatur, Alabanta 35609-2000 November 13, 1998 TVA-BFN-TS-393 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C. 20555 Gentlemen:

In the Matter of Docket Nos. 50-260 Tennessee Valley Authority 50-296 BROWNS FERRY NUCLEAR PLANT (BFN) - UNITS 2 AND 3 - RESPONSE TO REQUEST FOR ADDITIONALINFORMATION REGARDING PRESSURE-TEMPERATURE CURVE UPDATE, TS-393 (TAC NOS. MA1304 AND MA1305)

Reference:

NRC to TVA letter dated October 19, 1998, Browns Ferry Nuclear Plant, Units 2 and 3 - Request for Additional Information Regarding Pressure - Temperature Update The enclosures provide supplemental information requested by the reference letter to support the NRC staff's review of proposed technical specification change TS-393. TVA submitted TS-393 on March 3, 1998 to revise the BFN Units 2 and 3 pressure-temperature curves to extend the validity of the curves to 32 effective full power years. The information contained in the enclosures reflects ciarifications to the questions as discussed with the NRC staff during a November 4, 1998 telephone call. lt l There are no commitments contained in this letter. If you have any questions regarding this information, please telephone me at (256) 729-2636.

S'erely wb wO COLO 0'0 y

O'C Mana g icensing CLIO So an dustry Affairs CIA WC N Enc ures ~ lb cc: See IXI'"

It. I ocel~d ~'A Be 4~/Fi(~~

U.S. Nuclear Regulatory Commission Page 2 November 13, 1998 Enclosures cc (Enclosures):

Mr. Harold O. Christensen, 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 11555 Rockville Pike Rockville, Maryland 20852 Mr. L. Raghavan, Project Manager U.S. Nuclear Regulatory Commission One White Flint, North 11555 Rockville Pike Rockville, Maryland 20852

C ENCLOSURE 1 TENNESSEE VALLEYAUTHORITY BROWNS FERRY NUCLEAR PLANT (BFN)

UNITS 2 AND 3 RESPONSE TO REQUEST FOR ADDITIONALINFORMATION REGARDING PRESSURE-TEMPERATURE CURVE UPDATE, TS-393 RAI uestion 1 - ART Values Provide the adjusted reference temperature (AR77 calculations for all beltline, flange, and bottom head materials that were notincludedin your submittal.

~Res ense

References:

1. TVA to NRC letter dated July 14, 1995, Browns Ferry Nuclear Plant (BFN) - Units 1, 2, and 3

- Supplemental Information For Proposed Technical Specification (TS) No. 349- Reactor Vessel Pressure-Temperature (P-T) Curves And Boltup Temperatures

2. TVA to NRC letter dated March 3, 1998, Browns Ferry Nuclear Plant (BFN) - Units 2 and 3-Technical Specification (TS) Change No. 393- Pressure-Temperature Curve Update The tables provided below list the initial RTNpT values for the Unit 2 and Unit 3 non-beltline components. The limiting initial RTNpT values were utilized to develop the non-beltline curves 1, 2, and 3 shown on Tables 3 and 4 of Reference 2. These data were previously provided to NRC by Reference 1.

NON-BELTLINE RTNoT'S - UNIT 2 NON-BELTLINE RTNoT'S - UNIT 3 COMPONENT / REGION RTNoT COMPONENT / REGION RTNoT Closure Region 22'F Closure Region 10'F Bottom Head Region 42'F Bottom Head Region 58'F Jet Pump Nozzle 54'F Recirc. Inlet Nozzle 46'F All Other Non-Beltline <40'F Recirc. Outlet Nozzle 50'F Steam Outlet Nozzle 42'F Feedwater Nozzle 42'F Jet Pump Instr. Nozzle 58'F All Other Non.Beltiine <40'F

ENCLOSURE 1 TENNESSEE VALLEYAUTHORITY BROWNS FERRY NUCLEAR PLANT (BFN)

UNITS 2 AND 3 RESPONSE TO REQUEST FOR ADDITIONALINFORMATION REGARDING PRESSURE-TEMPERATURE CURVE UPDATE, TS-393 RAI uestion 2- ART Values for the N16 Instrumentation Nozzle Ifthe N16instrumentation materials nozzles arein the beltline regions of the Browns Feny reactor pressura vessels, then include the ART calculations for the instrumentation nozzles among the ART calculations for the i Questr'on 1.

~Res ense The N16 instrumentation nozzles are two 2-inch diameter penetrations that are located in Shell Segment Assembly Course ¹2 whose centerline is located at 366 inches above reactor zero, which is the top of the active fuel region (216" - 366"). The "nozzle", which is used for instrumentation, consists of a tapered 2-inch Alloy 600 pipe that is welded to the inside of the reactor pressure vessel (RPV) using a partial penetration weld. A detail of the Unit 3 N16 instrumentation nozzle is shown on Reference Drawing 1, contained in Enclosure 2. The reactor feedwater nozzles are six 12-inch diameter nozzles that are located in Shell Segment Assembly Course ¹3. (See Enclosure 2, Reference Drawing No. 2). The nozzle is attached to the inside and outside of the RPV via a full penetration weld.

Since the stresses in the feedwater nozzles bound those of the instrumentation nozzles, the analysis for the 12-inch feedwater nozzles is considered to be bounding for the N16 instrumentation nozzles.

ENCLOSURE 2 TENNESSEE VALLEYAUTHORITY BROWNS FERRY NUCLEAR PLANT (BFN)

UNITS 2 AND 3 RESPONSE TO REQUEST FOR ADDITIONALINFORMATION REGARDING PRESSURE-TEMPERATURE CURVE UPDATE, TS-393 Reference Drawings

1. Unit 3- Shell segment Assembly Course ¹2, B&W Dwg. No. 142116E, Sht. 1

2. Units 1 and 2 - 12" Feedwater Nozzle, B&W Dwg. No. 122866E, Sht. 2