ML18038B229
| ML18038B229 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 03/27/1995 |
| From: | Salas P TENNESSEE VALLEY AUTHORITY |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| GL-92-01, GL-92-1, NUDOCS 9504050013 | |
| Download: ML18038B229 (21) | |
Text
REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)
ACCESSION NBR:9504050013 DOC.DATE: 95/03/27 NOTARIZED: YES FACIL:50-259 Browns Ferry Nuclear Power Station, Unit 1, Tennessee 50-260 Browns Ferry Nuclear Power Station, Unit 2, Tennessee 50-296 Browns Ferry Nuclear Power Station, Unit 3, Tennessee AUTH.NAME AUTHOR AFFILIATION SALAS,P.
Tennessee Valley.Authority RECIP.NAME RECIPIENT AFFILIATION.
Document Control Branch (Document Control Desk)
DOCKET 05000259 05000260 05000296 P
I
SUBJECT:
Provides update to RPV matl
& fluence data provided in util response to NRC GL 92-0l,dtd 920707.
DISTRIBUTION CODE: A028D COPIES RECEIVED:LTR ENCL SIZE:
TITLE: Generic Letter 92-01 Responses (Reactor Vessel Structural Integrity 1 NOTES:
RECIPIENT ID CODE/NAME PD2-4-PD INTERNAL: ACRS NRR/DE/EMCB NUDOCS-ABSTRACT RES/DE/MEB EXTERNAL: NOAC COPIES LTTR ENCL 1
1 6
6 2
2 1
1 1
1 1
1 RECIPIENT ID CODE/NAME WILLIAMS,J.
FILE CENTER 01 NRR/DRPE/PDI-1 OGC/HDS3 NRC PDR COPIES LTTR ENCL 1
1 1
1 1
1 1
0 1
1 D
C U
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PLEASE HELP US TO REDUCE WASTE! CONTACTTHE DOCUMENTCONTROL DESK, ROOM Pl-37 (EXT. 504-2083 ) TO ELIMINATEYOUR NAMEFROM DISTRIBUTIONLISTS FOR DOCUMENTS YOU DON'T NEED!
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LTTR 17 ENCL 16
4
Tennessee Valley Authority. Post Office Box 2000, Oecatur, Alabama 35609 March 27, 1995 10 CFR 50.4 U.S. Nuclear Regulatory Commission ATTN:
Document Control Desk Washington, D.C.
20555 Gentlemen:
In the Matter of Tennessee Valley Authority Docket Nos.
50-259 50-260 50-296 BROWNS FERRY NUCLEAR PLANT (BFN) - UNITS 1~
2~
AND 3 GENERIC LETTER (GL) 92 Oiq REACTOR VESSEL STRUCTURAL 1NTEGRZTY UPDATE TO THE INITIALREFERENCE NIL-DUCTILITYTEMPERATURE (RTNDT)i CHEMICAL COMPOSITION AND FLUENCE VALUES This letter provides an update to the reactor pressure vessel (RPV) material and fluence data provided in TVA's response to GL 92-01, dated July 7, 1992.
Specifically, this update revises some of the initial RTNDT, chemical composition, and fluence values for BFN's Unit 1, 2, and 3 RPVs.
In addition, TVA requests NRC to revise the NRC computerized reactor vessel integrity database (RVID) to reflect BFN's updated RPV values.
TVA provided BFN Units 1, 2, and 3
RPV beltline material properties and beltline upper shelf energy (USE) predictions in response to GL 92-01.
These material properties and USE predictions were based on analysis performed by Babcock and Wilcox (B&W) in report BAW-1845.
General Electric (GE) has subsequently reanalyzed the material properties and USE predictions.
GE's analysis uses the same data (i.e.,
TDT and Charpy values) as B&W.
This GE method for calculating RT>>T values (NEDC-32399) was approved by NRC on December 16, 1994.
Some differences in RTNDT values were noted between the GE values and those previously provided by TVA in response to GL 92-01.
Additionally, the chemical composition (i.e., copper and nickel content) of the RPV plates provided in response to GL 92-01 were taken from the reactor vessel surveillance program material reanalysis contained in B&W report BAW-1845, Appendix F.
The RPV plate values used in the GE analysis were determined from the certified material test reports.
This 9504050013 tf50327 PDR ADOCK 0500025tif P
U.S. Nuclear Regulatory Commission Page 2
March 27, 1995 produced minor differences in the chemical composition (percent nickel) for two plates in the Unit 1 RPV low-intermediate shell and one plate in the Unit 3 RPV low-intermediate shell.
A minor difference was also noted in the chemical composition (percent copper) for the Unit 1, 2,
and 3
electroslag welds.
Finally, differences in calculated fluence values were noted.
The differences in GE's values and those reported in TVA's response to GL 92-01 are due to differences in the source of input methodology.
However, both sets of values produce conservative results.
TVA requests that NRC update the RVID to reflect GE's values.
The enclosure contains the updated RPV data and a discussion of the differences in values.
There are no commitments contained in this letter. If you have any questions, please contact me at (205) 729-2636.
Sin P
Salas.
Manager of Site Licensing Subscribed and sworn o before me on this ~l W day of a.
1995.
P~c~o Notary Public My Commission Expires~g C0Nmlgsfog P~tr~ ~OIONSe
4 v
\\ r f ~
U..S. Nuclear Regulatory Commission
'age 3
March 27, 1995 Enclosure cc (Enclosure):
Regional Administrator U.S. Nuclear Regulatory Commission Region II 101 Marietta Street, NW, Suite 2900 Atlanta, Georgia 30323 Mr. Mark S. Lesser, Acting Branch Chief U.S. Nuclear Regulatory Commission Region II 101 Marietta Street, NW, Suite 2900 Atlanta, Georgia 30323 NRC Resident Inspector Browns Ferry Nuclear Plant Route 12, Box 637
- Athens, Alabama 35611 Mr. Z. F. Williams, Project Manager U.S. Nuclear Regulatory Commission One White Flint, North 11555 Rockville Pike Rockville, Maryland 20852
ENCLOSURE TENNESSEE VALLEY AUTHORZTY BROWNS FERRY NUCLEAR PLANT (BFN)
UNITS 1, 2, and 3
GENERIC LETTER (GL) 92 01'EACTOR VESSEL STRUCTURAL ZNTEGRITY UPDATE TO THE INITIALREFERENCE NZL-DUCTILITY TEMPERATURE (RT>>Y) g CHEMICAL COMPOSITION AND FLUENCE VALUES REPORTED IN TVAiS GL 92-01 RESPONSES I ~
PURPOSE The purpose of this enclosure is to inform NRC that TVA is revising some initial RT>>~, chemistry composition, and fluence values previously provided in TVA's July 7,
- 1992, response to GL 92-01 (Reference 1).
TVA requests that NRC update the computerized reactor vessel integrity database to reflect the General Electric (GE) values high-lighted in Tables 1 through 3.
II'ACKGROUND TVA provided BFN Units 1, 2, and 3 reactor pressure vessel (RPV) beltline material properties and beltline upper shelf energy (USE) predictions in Reference 1.
These material properties and USE predictions were based on analysis performed by Babcock and Wilcox (B&W) in report BAW-1845 (Reference 2).
Also, additional information regarding the GL was provided in References 3 through 6.
GE has subsequently reanalyzed the material properties and USE predictions.
GE's analysis uses the same data (i.e.,
T>>Y and Charpy values) as B&W.
- However, GE used a
different method for calculating the initial RT>>~ values.
This GE method for calculating RT>>~ values (NEDC-32399) was approved by NRC on December 16, 1994 (Reference 7).
Some differences in RT>>~ values were noted between the GE values and those previously provided by TVA in Reference 1.
Additionally, the chemical composition (i.e., copper and nickel content) of the RPV plates provided in Reference 1
were taken from the reactor vessel surveillance program (RVSP) material reanalysis contained in Reference 2.
The RPV plate values used in the GE analysis were determined from the certified material test reports (CMTRs).
This produced minor differences in the chemical composition (percent nickel) for two plates in the Unit 1 RPV low-intermediate shell and one plate in the Unit 3 RPV low-intermediate shell.
.A minor difference was also noted in the chemical composition (percent copper) for the Unit 1, 2, and 3
electroslag welds.
Finally, differences in calculated fluence values were noted.
The following paragraphs describe the reasons for the differences in the initial RT>>Y, chemical composition, and fluence values.
III'IFFERENCES IN INITIALRT>>Y VALUES Table 1 shows a comparison of the results for both GE and B&W for BFN Units 1, 2, and 3, respectively.
The shaded areas identify the differences.
As can be seen, the initial RT>>~ for B&W is the T>>~; while the initial RT>>~ for GE is the greater of the T>>~ or transverse Charpy V-notch (CVN) 50 ft-lb transition temperature minus 60 degrees F.
Because GE has a special method for converting transition temperatures for CVN values lower than 50 ft-1b up to a transition temperature that corresponds to 50 ft-lb, and a
method for converting temperatures of longitudinal data to transverse, it is reasonable that B&W and GE would have different initial RT>>~ values.
The GE method has recently been approved by NRC for generic use (Reference 7).
Zt should be noted that in each case the GE initial RT>>Y values are greater than or equal to the B&W values (i.e.,
more conservative).
ZV.
DIFFERENCES ZN CHEMISTRY COMPOSITION The differences in the chemical composition calculated by GE and reported by TVA in Reference 1 are due to the different values used for the copper (Cu) and nickel (Ni) concentrations used in the calculation.
A comparison of these differences is provided in Table 2.
The plate values used by GE were determined from the CMTRs for each material, while the plate values reported in Reference 1 were taken from the RVSP material reanalysis contained in Reference 2.
This produced minor differences in the nickel concentration for two plates in the Unit 1 RPV low-intermediate (low-int) shell and one plate in the Unit 3 RPV low-int shell.
The generic chemistry for the Unit 1, 2,
and 3 electroslag welds was calculated by both GE and B&W using the same data contained in Reference 2.
- However, GE's methodology utilized the conservative approach specified in Regulatory Guide 1.99, Revision 2, to obtain a copper content that was different from that developed in Reference 2.
E-2
.In most cases the GE chemical composition values are greater than those reported in the GL 92-01 response, which results in greater (i.e.,
more conservative) chemistry factors.
V.
DIFFERENCES IN FLUENCE The fluence values calculated by GE are as follows:
Unit 1 = 7.62 x 10'~
Unit 2 = 1.07 x 10" Unit 3 = 1.07 x 10" These values were calculated using an initial fluence of 2 38 x 10 for Unit 1 and 3
34 x 10io for Units 2 and 3
The initial fluence values came from TVA calculation NDQ0999-900054 RO.
This calculation is available on site for review.
The fluence values calculated by NRC in Reference 7 are as follows:
Unit 1 = 1.24 x 10is Unit, 2 = 1.06 x 10 Unit 3 = 1.04 x 10'hese values appear to have been calculated using initial fluence values of 3.91 x 10'or Unit 1g 3'4 x 10 for Unit 2, and 3.28 x 10'or Unit 3.
These initial fluence values were provided by TVA in Reference 1.
VI~
CONCLUSION The GE initial RT~Y, chemical composition, and fluence values are contained in this enclosure.
In each case, except the fluence value for Unit 1, the GE values are greater than or equal to the B&W values (i.e.,
more cnoservative).
E-3
VX'EFERENCES 2
~
3 ~
4 ~
5.
6.
7.
8.
TVA letter to NRC, dated July 7,
and Watts Bar Nuclear Plant (WBN)
Response to Generic Letter 92-01 (Reactor Vessel Structural Integrity)
BAW Report 1845, dated August 1984, Browns Ferry Core Region Materials Information (Unit 1, 2, and 3)
TVA letter to NRC, dated December 1,
- 1992, Completion of Commitment Made in Response to Generic Letter 92-01, "Reactor Vessel Structural Integrity" TVA letter to NRC, dated August 2,
- 1993,
Response
to Request for Additional Information, Generic Letter 92-01, Revision 1
TVA letter to NRC, dated May 23,
- 1994, TVA's Response to NRC's letter dated April 19, 1994, Generic Letter 92-01, Revision 1, "Reactor Vessel Structural Integrity" TVA letter to NRC, dated July 28,
- 1994, Supplemental Response to TVA letter dated May 23,
- 1994, Generic Letter 92-01, Revision 1, Reactor Vessel Structural Integrity Letter from Brian Sheron to Mr. R. A. Pinelli, dated December 16,
- 1994, "Safety Assessment of Report NEDC-32399-P, "Basis for GE Ropy Estimation Method",
September
- 1994, US NRC, Washington D.C.
NRC letter to TVA, dated April 19,
- 1994, Generic Letter (GL) 92-01, Revision 1, "Reactor Vessel Structural Integrity" Tennessee Valley Authority Browns Ferry Units 1, 2, and 3
(TAC Nos.
- M83438, M83439, and M83440)
TABLE 1 (SHEET 1 OF 3)
COMPARISON OF GENERAL ELECTRIC AND BABCOCK AND WILCOX RT~~ VALUES UNIT 1 Lower Shell Low-Int Shell WELD ID 6-127-1 6-127-2 6-127-4 I
6-139-19 6-139-20 6-139-21 HEAT A0999-1 B5864-1 A1009-1 C2884-2 C2868-2 C2753-1 GE RT~g (4F)
-20
-20
-10 B&W RTgpg (oF)
-20
-20
-10 E-5
t
TABLE 1 (SHEET 2
OF 3)
COMPARISON OF GENERAL ELECTRIC AND BABCOCK AND WILCOX RT~g VALUES UNIT 2 REGION Lower Shell Low-Int Shell WELD ID 6-127-14 6-127-15 6-127-17 6-127-6 6-127-16 6-127-20 HEAT C2467-2 C2463-1 C2460-2 A0981-1 C2467-1 C2489-1 GE RTgpY (~F)
-20
-20
-10
-10
-10 B&W RT~Y (~F)
-20
-20
-10
-10
-10 E-6
I'
TABLE 1 (SHEET 3
OF 3)
COMPARISON OF GENERAL ELECTRIC AND BABCOCK AND WILCOX RT~~VALUES UNIT 3 REGION Lower Shell Low-Int Shell WELD ID 6-145-4 6-145-7 6-145-12 6-145-1 6-145-2 6-145-6 HEAT C3222-2 C3213-1 C3217-2 C3201-2 C3 188-2 B7267-1
-20
-20 E-7
TABLE 2 COMPARISON OF CHEMICAL COMPOSITION UNIT MATERIAL Low-Int Shell COMPONENT ID 6-139-19 6-139-20 HEAT NUMBER C2884-2 C2868-2 CCu 0.12 0.09 GE CNi
- CF 58 4Cu 0.09 B&W 4Ni
- CF 58 Long Weld Long. Weld Low-Int Shell Long. Weld ESW ESW 6-145-2 ESW C3188-2 0.10 0.35 0.35 0.35 1~5'O'Q!
0.::.'Q~S
- 0. 35 65 0.35 X42;,.;5 3~42::%:8 65
- CF = Chemistry Factor E-8
V
TABLE 3 DIFFERENCES IN CALCULATED FLUENCE VALUES UNIT GE FLUENCE FOR 32 EFPY (n/cm~)
GENERIC LETTER 92-01 FLUENCE FOR 32 EFPY (n/cm~)
Effective Full Power Years (EFPY)
E-9
1 11 I