ML15112A588
| ML15112A588 | |
| Person / Time | |
|---|---|
| Site: | Oconee  |
| Issue date: | 03/23/1998 |
| From: | Labarge D NRC (Affiliation Not Assigned) |
| To: | Mccollum W DUKE POWER CO. |
| References | |
| NUDOCS 9803250090 | |
| Download: ML15112A588 (5) | |
Text
March, 23, 1998 Mr. W. R. McCollum Distribution:
HBerkow LPlisco, RIl Vice President, Oconee Site Docket File LBerry COgle, Rll Duke Energy Corporation PUBLIC DLaBarge P. 0. Box 1439 PD 11-2 Rdg.
OGC Seneca, SC 29679 JZwolinski ACRS
SUBJECT:
INFORMATION REQUEST - REACTOR PRESSURE VESSEL BELTLINE REGION CROSS-SECTIONAL DEVELOPED INNER-SURFACE AREAS OF PLATE AND WELDS - OCONEE NUCLEAR STATION, UNIT 1
Dear Mr. McCollum:
In order to perform an overall pressurized thermal shock (PTS) analysis and revise Regulatory Guide 1.154 for reactor pressure vessels (RPVs), the NRC Office of Nuclear Regulatory Research has requested that you supply the "Developed Inner-Surface Area Dimensions" of the Beltline Region for the Oconee Unit 1 RPV. Enclosure 1 is an example of the Developed Area that has been supplied for Calvert Cliffs Unit 1. Please note that the Oconee Unit 1 RPV PTS study was performed (NUREG/CR-3770, May 1986) to support Regulatory Guide 1.154 technical bases development.
Based on the information in the NRC Office of Nuclear Reactor Regulation's Reactor Vessel Integrity Data Base, Version 2, there are 14 different plate and weld regions in the beltline region of the Oconee Unit 1 RPV. This information is shown in Enclosure 2. For each region, we request that you supply the length of the weld or area of the plate, as appropriate. This information was inadvertently omitted from the NUREG/CR-3770 PTS analysis.
Sincerely, ORIGINAL SIGNED BY:
David E. LaBarge, Senior Project Manager Project Directorate 11-2 Division of Reactor Projects - 1/11 Office of Nuclear Reactor Regulation Docket No. 50-269
Enclosures:
As stated (2) cc w/encls: See next page DOCUMENT NAME: G:\\OCONEE\\RPVRES.INF To receive a copy of this document, indicate in the box:
"C" = Copy without attachmentlenclosure "E" = Copy with attachment/enclosure "N" = No copy 6
OFFICE PDII- /P PDII-21 DII NAME DLaB
- cn LBerry (Be DATE 3' A/ 98 47/1((/98 3/19 98
/ :198
- See previous concurrence OFFICIAL RECORD COPY 9803250090 980323 PDR ADOCK 05000269 p
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-4001 March 23, 1998 Mr. W. R. McCollum Vice President, Oconee Site Duke Energy Corporation P. 0. Box 1439 Seneca, SC 29679
SUBJECT:
INFORMATION REQUEST - REACTOR PRESSURE VESSEL BELTLINE REGION CROSS-SECTIONAL DEVELOPED INNER-SURFACE AREAS OF PLATE AND WELDS - OCONEE NUCLEAR STATION, UNIT 1
Dear Mr. McCollum:
In order to perform an overall pressurized thermal shock (PTS) analysis and revise Regulatory Guide 1.154 for reactor pressure vessels (RPVs), the NRC Office of Nuclear Regulatory Research has requested that you supply the "Developed Inner-Surface Area Dimensions" of the Beltline Region for the Oconee Unit 1 RPV. Enclosure 1 is an example of the Developed Area that has been supplied for Calvert Cliffs Unit 1. Please note that the Oconee Unit 1 RPV PTS study was performed (NUREG/CR-3770, May 1986) to support Regulatory Guide 1.154 technical bases development.
Based on the information in the NRC Office of Nuclear Reactor Regulation's Reactor Vessel Integrity Data Base, Version 2, there are 14 different plate and weld regions in the beltline region of the Oconee Unit I RPV. This information is shown in Enclosure 2. For each region, we request that you supply the length of the weld or area of the plate, as appropriate. This information was inadvertently omitted from the NUREG/CR-3770 PTS analysis.
Sincerely, David E. LaBarge, Senior Project Manager Project Directorate 11-2 Division of Reactor Projects - III Office of Nuclear Reactor Regulation Docket No. 50-269
Enclosures:
As stated (2) cc w/encls: See next page
Oconee Nuclear Station cc:
Mr. Paul R. Newton Mr. J. E. Burchfield Legal Department (PBO5E)
Compliance Manager Duke Energy Corporation Duke Energy Corporation 422 South Church Street Oconee Nuclear Site Charlotte, North Carolina 28242 P. 0. Box 1439 Seneca, South Carolina 29679 J. Michael McGarry, Ill, Esquire Winston and Strawn Ms. Karen E. Long 1400 L Street, NW.
Assistant Attorney General Washington, DC 20005 North Carolina Department of Justice Mr. Robert B. Borsum P. 0. Box 629 Framatome Technologies Raleigh, North Carolina 27602 Suite 525 1700 Rockville Pike L. A. Keller Rockville, Maryland 20852-1631 Manager - Nuclear Regulatory Licensing Manager, LIS Duke Energy Corporation NUS Corporation 526 South Church Street 2650 McCormick Drive, 3rd Floor Charlotte, North Carolina 28242-0001 Clearwater, Florida 34619-1035 Mr. Richard M. Fry, Director Senior Resident Inspector Division of Radiation Protection U. S. Nuclear Regulatory North Carolina Department of Commission Environment, Health, and 7812B Rochester Highway Natural Resources Seneca, South Carolina 29672 3825 Barrett Drive Raleigh, North Carolina 27609-7721 Regional Administrator, Region II U. S. Nuclear Regulatory Commission Atlanta Federal Center 61 Forsyth Street, S.W., Suite 23T85 Atlanta, Georgia 30303 Max Batavia, Chief Bureau of Radiological Health South Carolina Department of Health and Environmental Control 2600 Bull Street Columbia, South Carolina 29201 County Supervisor of Oconee County Walhalla, South Carclina 29621
o 00 0
90 180 270 360 Outlet Inlet Inlet Outlet Inlet Inlet Outlet 1-0 1-203 1-203 8-203 (D
Weight 2-203B Cu Ni P
2-203C 2-203A W
0.21 0.87 0.015 Nj K,,_9-203 0
Weight %
Cu Ni P
0 ft a a a a a at se m a ft ft ft-a aaa-aa-
-aa
-a--a.
/
aiL W4 aaaas a
3-203 Weight -Z320 3-203 a
leCu Ni P
4 U
0 O.21 0.71 0.016 4j 10-203 M JP i t 2pg 3S9 Azimuthal Location (degrees)
Figure 5.3. Developed view of Inner surface of beltline region of Calvert Cliffs Unit I
- 0. 1pressure vessel, showing locations of welds. (Weld 2-203A was determined to be the most important weld).
CD
NRC - Reactor Vessel Integrity Database Printed 3/13/98 8:48:44 APTS Summary Report Docket No: 50-269 Page I OCONEE 1 EOL Date:
02/06/2013 Neutron Fluence Beline dt i
RTpts Fluence ARTndt(u)
Factor Chem Chemistry Factor Type Heat ID
@EOL
@ EOL RTndt(u) RTndt(u) METHOD
@ EOL
@ EOL Factor Method Margin Margin Method Cu%
NI%
P%
S%
LOWER NOZZLE BELT 127.5 0.118 3.0 B&W GENERIC 53.8 0.451 119.25 TABLE 70.7 POSITION 1.1 0.160 0.650 0.006 0.010 FORGING AHR54 (ZV2861)
(NO S DATA)
INTERMEDIATE SHELL 162.4 0.796 1.0 B&W GENERIC 97.8 0.936 104.50 TABLE 63.6 POSITION 1.1 0.150 0.500 0.008 0.010 2
PLATE C2197-2 (NO S DATA)
LOWER SHELL 136.1 0.868 1.0 B&W GENERIC 71.5 0.960 74.45 TABLE 63.6 POSITION 1.1 0.110 0.630 0.012 0.017 3
PLATE C2800-1 (NO S DATA)
LOWER SHELL 136.1 0.868 1.0 B&W GENERIC 71.5 0.960 74.45 TABLE 63.6 POSITION 1.1 0.110 0.630 0.012 0.017 PLATE C2800-2 (NO S DATA)
UPPER SHELL 113.8 0.904 1.0 B&W GENERIC 56.4 0.972 58.01 OVERRIDE 56.4 POSmON 2.1 0.100 0.500 0.015 0.015 PLATE I
C3265-1 (S DATA)
UPPER SHELL 145.3 0.904 1.0 B&W GENERIC 80.7 0.972 83.00 TABLE 63.6 POSITION 1.1 0.120 0.600 0.010 0.016 PLATE
.C3278-1 (NO S DATA)
INTERMEDIATE SHELL AXIAL WELDS SA-211.9 0.628
-5.0 B&W GENERIC 148.4 0.870 170.60 TABLE 68.5 POSITION 1.1 0.210 0.640 0.025 0.017 WELD 1P0962 (NO S DATA)
NOZZLE BELTANT. SHELL CIRC WELD SA 113.2 0.118
-5.0 B&W GENERIC 69.8 0.451 154.87 OVERRIDE 48.3 POSITION 2.1 0.250 0.540 0.011 0.013 WELD 61782 (S DATA)
INT.ILOWER S?::LL CIRC WELD SA-1229 233.4 0.796
-5.0 B&W GENERIC 170.0 0.936 181.60 OVERRIDE 68.5 POSmON 1.1 0.260 0.610 0.021 0.012 WELD 71249 (NO S DATA)
LS/DUTCHMAN CIRC. WELD WF-9 59.4 0.010
-5.0 B&W GENERIC 16.1 0.110 146.09 OVERRIDE 48.3 POSITION 2.1 0.210 0.590 0.000 0.000 0
WELD 72445 (S DATA)
UPPERILOWER SHELL CIRC WELD SA-158 183.5 0.868
-5.0 B&W GENERIC 140.2 0.960 148.00 OVERRIDE 48.3 POSITION 2.1 0.210 0.590 0.016 0.016 WELD 72445 (S DATA)
LOWER SHELL AXIAL WELDS SA-1426 202.2 0.729
-5.0 B&W GENERIC 138.7 0.911 152.25 TABLE 68.5 POSITION 1.1 0.200. 0.550 0.017 0.013 WELD 8T1762 (NO S DATA)
LOWER SHELL AXIAL WELDS SA-1430 202.2 0.729
-5.0 B&W GENERIC 138.7 0.911 152.25 TABLE 68.5 POSITION 1.1 0.200 0.550 0.017 0.015 WELD 8Ti762 (NO S DATA)
UPPER SHELL AXIAL WELDS SA-1493 201.9 0.723
-5.0 B&W GENERIC 138.4 0.909 152.25 TABLE 68.5 POSITION 1.1 0.200 0.550 0.017 0.010 14 WELD 8T1762 (NO S DATA)
Plant References and Beltline Material Notes Fluence, chemical composition, and IRTndts are from BAW-2166.
Chemistry Factor for SA-1 585 was calculated from Point Beach and Crystal River surveillance data that was reported in BAW 1803, Rev. i. The surveillance welds were fabricated using the same weld wire heat number as SA-1585.
2 Chemistry Factor for SA-1 135 was calculated from Ginna and Davis-Besse surveillance data that was reported In BAW-1803, Rev. 1. The surveillance welds were fabricated with the same weld wire o
heat number as SA-1 135.
e
-s The UUSE data are from BAW-2222 (June 1994).
io Surveillance data for heat 71249 was determined not credible, Table was used to calculate chemistry factor.