ML18039A609
| 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: |
| 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 DOCKET I 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 AFFILXATION Records Management Branch (Document Control Desk)
SUBJECT:
Provides supplemental info recpxested by ltr drd 981019 to support NRC staff review of proposed Tech Specs Change TS-393.No commitments contained in ltr.With one oversize drawing DISTRIBUTION CODE:
D030D COPIES RECEIVED:LTR ENCL SIZE:
TITLE: TVA Facilities
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N NOTE TO ALL "RIDS" RECIPIENTS:
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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 Tennessee Valley Authority Docket Nos.
50-260 50-296 BROWNS FERRY NUCLEAR PLANT (BFN) - UNITS 2 AND 3 - RESPONSE TO REQUEST FOR ADDITIONALINFORMATIONREGARDING PRESSURE-TEMPERATURE CURVE UPDATE, TS-393 (TAC NOS. MA1304 AND MA1305)
Reference:
NRC to TVAletter 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. TVAsubmitted 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.
Ifyou have any questions regarding this information, please telephone me at (256) 729-2636.
S'erely wb wO COLO 0'0 O'C CLIO So CIA WC N
IXI'"It.I y
Mana g icensing an dustry Affairs Enc ures cc: See
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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
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ENCLOSURE 1 TENNESSEE VALLEYAUTHORITY BROWNS FERRY NUCLEAR PLANT (BFN)
UNITS 2 AND 3 RESPONSE TO REQUEST FOR ADDITIONALINFORMATIONREGARDING PRESSURE-TEMPERATURE CURVE UPDATE, TS-393 RAI uestion 1 - ART Values Provide the adjusted reference temperature (AR77 calculations forall beltline, flange, and bottom head materials that were notincludedin your submittal.
~Res ense
References:
1.
TVAto 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.
TVAto 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-BELTLINERTNoT'S - UNIT2 NON-BELTLINERTNoT'S - UNIT3 COMPONENT / REGION Closure Region Bottom Head Region Jet Pump Nozzle AllOther Non-Beltline RTNoT 22'F 42'F 54'F
<40'F COMPONENT / REGION Closure Region Bottom Head Region Recirc. Inlet Nozzle Recirc. Outlet Nozzle Steam Outlet Nozzle Feedwater Nozzle Jet Pump Instr. Nozzle AllOther Non.Beltiine RTNoT 10'F 58'F 46'F 50'F 42'F 42'F 58'F
<40'F
ENCLOSURE 1 TENNESSEE VALLEYAUTHORITY BROWNS FERRY NUCLEAR PLANT (BFN)
UNITS 2 AND 3 RESPONSE TO REQUEST FOR ADDITIONALINFORMATIONREGARDING PRESSURE-TEMPERATURE CURVE UPDATE, TS-393 RAI uestion 2-ART Values for the N16 Instrumentation Nozzle Ifthe N16instrumentation nozzles arein the beltline regions ofthe Browns Feny reactor pressura vessels, then include the ARTcalculations forthe instrumentation nozzles among the ARTcalculations forthe materials 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 Alloy600 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 ADDITIONALINFORMATIONREGARDING PRESSURE-TEMPERATURE CURVE UPDATE, TS-393 Reference Drawings 1.
Unit 3-Shell segment Assembly Course ¹2, B&WDwg. No. 142116E, Sht.
1 2.
Units 1 and 2 - 12" Feedwater Nozzle, B&WDwg. No. 122866E, Sht. 2