ML20197J346
| ML20197J346 | |
| Person / Time | |
|---|---|
| Site: | North Anna  |
| Issue date: | 12/18/1997 |
| From: | Saunders R VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.) |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| 97-713, NUDOCS 9801020151 | |
| Download: ML20197J346 (22) | |
Text
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VIHUINI A Et,ECTRIC ANI) POWER COMi%NY Riemimi, %>unNI A 2326:
i December 18, 1997 United States Nuclear Regulatory Commission Serial No.97-713 Attention: Document Control Desk NL&OS/ETS R0 Washington,- D.C. 20555 Docket No. 50-338 License No. NPF-4 Gentlemen:
VIRGINIA ELECTRIC AND POWER COMPANY fiORTH ANNA POWER STATION UNIT 1 ASME SEQIlON XI RE.Ll.EF REQUESTS NDE-37 THRQJLGH NDE-41 ASME_SECTIONXIJNSERVICE INSPECTION PROGBAM_flELIEEREQUEST During the Spring 1997 refueling outage, North Anna Power Station Unit 1 completed examinations in the third period of the second ten year interval.
Examinations were conducted to the requirements of the 1983 Edition with Summer 1983 Addenda of ASME Section XI. However, there were instances where the examination coverage required by the Code was not possible due to weld geometry or obstructions. Therefore, pursuant to 10 CFR 50.55a (g) 5, relief is requested from certain requirements of ASME Section XI Code associated with partial examinations conducted during the 1997 North Anna Unit 1 refueling outage. Relief requests NDE-37 through NDE-41 are attached and provide the basis of this request.
These relief requests have been reviewed and approved by the Station Nuclear Safety and Operating Committee, if you have any additional questions conceming this request, please contact us.
Very truly yours, R. F. Saunders Vice President - Nuclear Engineering and Services
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am:1 Commitments made in this letter:
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U. S. Nuclear Regulatory Commission Region ll Atlanta Federal Center 61 Forsyth St., SW, Suite 23T85 Atlanta, Georgia 30303 Mr. M. J. Morgan NRC Senior Resident inspector North Anna Power Station I
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ASME Section XI Relief Requests NDE-37 through NDE-41 North Anna Power Station Unit 1 Virginia Electric and Power Company i
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Virginia Electric & Power Company North Anna Power Station Unit 1 Second 10 Year Interval Request for Relief Number NDE-37 1.
IDENTIFICATION OF COMPONENTS Mark / Weld No.
Line No.
Drawing No.
Class 1
1 RC R-1 11715-WMKS-RC-R-1.2 1
11.
CODE REQUIREMENTS The 1983 Edition with Summer 1983 Addenda of ASME Section XI Table IWB-2500-1, examination category B A, item number B1.40 does not allow any limitations to the required volumetric or surface examinations. Code Case N-460, "Altemative Examination Coverage for Class 1 and Class 2 Welds", allows a reduction in coverage, if it is less than 10%
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CODE REQUIREMENT FROM WHICH RELIEF IS REQUESTED Relief is requested from oxaminino the Code required volumetric examination for the identified head-to flange weld.
IV.
BASIS FOR RELIEF The weld listed above has been examined to the extent practical as required by the Code. The Code required volumetric examination coverage was reduced due to weld joint geometry and a lifting lug. The scope of volumetric examination coverage completed for the above listed weld is listed in Table NDE-37-1 below.
Figures NDE-37-1 and NDE-37-2 are provided detailing graphically the limitations experienced. The surface examination covered 96% of the required area.
V.
ALTERNATE PROVISIONS It is proposed that the examination already completed at the reduced coverage be counted as meeting the Code requirementc. In addition:
1.
A visual (VT-2) examination will be performed during the normally scheduled system leakage test each refueling outage;
,2.
Technical Specifications requires that the reactor coolant system leak rate be limited to one gallon per minute unidentified leakage. This value is calculated at least once per 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />; and 3.
The containment atmosphere particulate radioactivity is monitored every 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
The proposed alternative examinations stated above will ensure that the overall level of plant quality and safety will not be compromised.
Table NDE-37-1 Examination Coverage Estimates (Vessel)
Category B-A, Item B1.40 Mark /
Beam Exam Scan Percent Reason For Weld.No.
Angle
&ea Direction Exam Partial 96 Proximity To Flange 1
_0 Weld & Base (240 to 0 45 Weld 2
48 and Lifting Lug degrees) 45 Weld 5
96 Interference 45 Weld 7
95 45 Weld 8
95 60 Weld 2
15 60 Weld 5
96 60 Weld 7
95 60 Weld 8
95 45 & 60 Base 2
56 45 & 60 Base 5
96 45 & 60 Base 7
95 45 & 60 Base 8
95 UT Scan Direction Definitions 2 - Axial scan flange side of weld 5 - Axial scan head side of weld 7 - Circumferential scan, clockwise (looking down on head) 8 - Circumferential scan, counterclockwise (looking down on ' ad)
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h Virginia Electric & Power Company North Anna Power Station Unit 1 Second 10 Year Interval-Request for Fielief Number NDE-38
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IDENTIFICATION OF COMPONENTS MarWWeld No.
Line No.
Drawina No Class 13 1 RC-E-2 11715-WMKS RC-E 2 1
II.
CODE REQUIREMENTS The 19C3 Edition with Summer 1983 Addenda of ASME Section XI Table IWB-2500-1, examination category B D, item number B3.110 does not allow any limitations to the required volumetric examination. Code Case N-460, "Altemative Examination Coverage for Class 1 and Class 2 Welds", allows a reduction in coverage,if it is less than 10%
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CODE REQUIREMENT FROM WHICH RELIEF IS REQUESTED Relief is requested from examining the Code required volumetric examination for the identified nozzle-to-head wald.
IV.
BASIS FOR RELIEF The weld listed above has been examined to the extent practical as required by the Code. The Code required volumetric examination coverage was reduced due to weld joint geometry for two-thirds of the circumference of the weld, The weld geometry is due to the weld configuration and the transition from the nozzlo to the pressurizer. The nozzle is situated on the pressurizer in such a manner that the angle between the nozzle and the pressurizer is not perpendicular. The intrados of this angle is the major contributor to the reduced coverage experienced because it limits search unit manipulation.
Ninety-eight (98.3).
percent coverage was obtained over one-third of the circumference _ of the weld and seventy eight (78.5) percent coverage was obtained over two-thirds of the circumference of the weld. The total percent coverage obtained for the entire weld for all scans is eighty-eight (88.4) percent. The weld was examined to the maximum extent possible by using a 0.25" 60a search unit to achieve additional l
coverage. The extent of volumetric examination coverage completed is listed in Table NDE-38-1.
Figure NDE-38-1 is provided detailing graphically the limitations experienced on two-thirds of the circumference of the weld.
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i V.4-J ALTERNATE PROVISIONS
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it is proposed that the examination already completed at the reduced coverage -
be counted as meeting the Code requirements, in addition:
1.
A visual (VT 2) examination will be performed during the normally scheduled-l system leakage test each refueling outage; 2.
Technical Specifications requires that the reactor coolant system leak rate -
be limited to one gallon per minute unidentified leakage. This valus 3s calculated at least once per 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />; and 3.
The containment atmosphere particulate radioactivity is monitored every 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
The proposed attemative examinations stated above will ensure that the overall level of plant quality and safety will not be compromised.
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Table NDE-38-1 North Anna Unit 1 Examination Coverage Estimates (Vessel)
Category B-D, item B3.110 Mark /
Beam Exam Scan Percent Reason Wald Angle.
&Ea Direction Exam For Partial 79 Weld 13 0
Weld & Base (1/3 Cir.)
45 Weld 2
100 configuration 45 Weld 5
100 45 Weld 7
100 45 Weld 8
100 60 Weld 2
100 60 Weld 5
100 60 Weld 7
100 60 Weld 8
100 45 & 60 Base 2
100 45 & 60 Base 5
100 45 & 60 Base 7
100 45 & 60 Base 8
100 79 Weld 13 0
Weld & Base (2/3 Cir.)
45 Weld 2
46 configuration 45 Weld 5
99 45 Weld 7
100 45 Weld 8
97 60 Weld 7
100 60 Weld 8
100 45 & 60 Base 2
46 45 & 60 Base 5
34 45 & 60 Base 7
100 45 & 60 Base 8
100 UT Scan Direction Definitions 2 - Axial scan pipe side of weld 5 - Axial scan head side of weld 7 - Circumferential scan, clockwise (looking down on head) 8 - Circumferential scan, counterclockwise (looking down on head)
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Virginia Electric & Power Company North Anna Power Station Unit 1 Second 10 Year Interval Request for Relief Number NDE 39 1.
IDENTIFICATION OF COMPONENTS Mark / Weld No.
Line No.
Drawina No.
Class SW-8 29"-RC-1-2501 R-Q1 11715-WMKS-109E-2 1
SW-9 29"-RC-1 2501 R-Q1 11715 WMKS-109E-2 1
SW 41 27%"-RC-3-2501 R-Q1 11715 WMKS-109E-2 1
II.
CODE REQUIREMENTS The 1983 Edition with Summer 1983 Addenda of ASME Section XI Table IWB-2500-1, examination category B-J, item number B9.11 does not allow any limitations to the required volumetric or surface examinations. Code Case N-460, "Altemative Examination Coverage for Class i and Class 2 Welds", allows a reduction in coverage, if it is less than 10%.
Ill.
CODE REQUIREMENT FROM WHICH RELIEF IS REQUESTED Relief is requested from examining the Code required volumetric examination for the identified plpe-to-pipe welds.
IV.
BASIS FOR RELIEF The welds listed above have been examined to the extent practical as required by the Code. The Code required volumetric examination coverage was reduced due l
to weld joint geometry, and the material type from which the components are constructed. The scope of volumetric examination coverage completed for the abova listed welds are listed in Table NDE-39-1. Figures NDE-39-1 and 2 are provided detalling graphically the limitations experienced.
These welds are i
classified as terminal ends and are required to be examined by the ISI Program.
V.
ALTERNATE PROVISIONS l
It is proposed that the examinations already completed at the reduced coverage be counted as meeting the Code requirements. In addition:
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1.
A visual (VT-2) examination will be performed during the normally i
screduled system leakage test each refueling outage; I
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~ 2.
Technical Specifications requires that the reactor coolant system leak rate be limited to one. gallon per minute unidentified leakage. This value is
. calculated at least once per 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />; and 3.
The containment atmosphere particulate radioactivity is monitored every 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
The proposed altemative examinations stated above will ensure that the overall level of plant quality and safety will not be compromised.
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Table NDE-39-1 North Anna Unit 1 Examinatio Coverage Estimates Category B-J, item B9.11 UT Coverage %
Surface Examination MarkJWek' 'JA _2
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_B Coverace Percentace Reason for Partial Examination SW-8 0
77 30 30 100 Nozzle and weld joint configuration and material type (ASTM A-351 austenitic steel casting) limit the use of an extended V-path examinatiort Due to ciange in configuration around the nozzle the percent of volume varied around the circumference. The minimurr.
coverage for the 5 scan,30%, occurred between 330 degrees to 30 degrees and 150 degrees to 210 degrees. The coverage for the remaining circumference of the 5 scan was 100% Approximately 77% of the lower 1/3 of the weld was covered in the 5 direction.
SW-9 87 0
30 30 100 Nozzle and weld joint configuration and material type (ASTM A-351 austenitic steel casting) limit the use of an extended V-path examination Due to change in confguration around the nozzle the percent of volume varied around the c.rcumference. The minimum coverage for the 2 scan,59%, occurred between 330 degrees to 30 degrees and 150 degrees to 210 degrees. The coverage for the remaining circumference of the 2 scan was 100% Approximately 87% of the lower 1/3 of the weld was covered in the 2 direction.
SW-41 74 0
28 28 100 Nozzle and weld joint configuration and material type (ASTM A-351 austerutic steel casting) limit the use of an extended V-path examination. Due to change in configuration around the nozzle the percent of volume varied around the circumference. The minimum coverage for the 2 scan,54.75%, occurred between 330 degrees to 30 degrees and 150 degrees to 210 degrees. The coverage for the remaining circumference of the 2 scan was 100% Approximately 74% of the lower 1/3 of the weld was covered in the 2 direction.
UT Scan Direction Definitions 2 - Axial scan,180 degrees from isometric flow direction (weld count).
5 - Axial scan, the same direction as the isometric flow (weld count).
7 - Circumferential scan, clockwise rotation when viewing in the direction of isometric flow.
8 - Circumferential scan, counterclockwise rotation when viewing in the direction of isometric flow.
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e Virginia Electric & Power Company-North Anna Power Station Unit 1 Second 10 Year Interval Request for Relief Nutnber NDE-40 1.
IDENTIFICATION OF COMPONENTS Mark / Weld No.
Line No.
Drawina No.
GASS SW-8 6'-RC 37-1502 01 11715-WMKS-110A 1
SW 31 6"-RC 38-1502-01 11715 WMKS-110A 1-SW-38 6" RC-391502 01 11715 WMKS-110A 1
II.
CODE REQUIREMENTS The 1983 Editlen with Summer 1903 Addenda of ASME Section XI Table IWB-250041, examination category B-J, item number B9.11 does not allow any limitations to the required volumetric or surface examinations. Code Case N-460, "Altemative Examination Coverage for Class 1 and Class 2 Welds", allows a reduction in coverage, if it is less than 10%.
Ill.
CODE REQUIREMENT FROM WHlCH RELIEF IS REQUESTED Relief is requested from examining the Code required surface and volumetric examination for the identified pipe-to-flange welds.
IV.
BASIS FOR RELIEF
-The welds listed above have been examined to the extent practical as required by the Code. Due to interference by an existing pipe support, only 6 inches out of 21 inches were examined. The scope of volumetric examination and surface examination coverage completed for the above listed welds is listed in Table NDE-40-1.
Figure NDE-40-1 is provided detailing graph!cally the limitations experienced. These welds are classified as terminal ends and are required to be examined by the ISI Program.
V.
ALTERNATE PROVISIONS lt is proposed that the examinations already completed at the reduced coverage be counted as meeting the Code requirements. In addition:
1.
A visual (VT-2) examination will be performed during the normally scheduled system leakage test each refueling outage;
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, - 2.
Technical Specifications requires that the reactor coolant system leak rate be limited to one gallon per minute unidentified leakage. This value is calculated at least once per 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />; and 3.
The containment atmosphere particulate radioactivity is monitored every 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
The proposed alternative examinations stated above will ensure that the overall level of plant quality and safety will not be compromised.
Tab!e NDE-40 North Anna Unit 1 Examination Coverage Estimates Category B-J, item B9.11 Percentage UT-MaM Coverage at Locations Percentage Surface Weld No.
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Examination CovelaQQ Reason for Partial Exam SW-8 29 29 29 29 29 Pipe support limits examination to 6 inches of 20.8 inches, i
SW-31 29 29 29 29 29 Pipe support limits examination to 6 inches of 20.8 inches.
SW-38 29 29 29 29 29 Pipe support limits examination to 6 inches of 20.8 inches.
UT Scan Dircetion Definitions 2 - Axial scan,180 degrees from isometric flow direction (weld count).
5 - Axial scan, the same direction as the isometric flow (weld count).
7 - Circumferential scan, clockwise rotation when viewing - the direction of isometric flow.
8 - Circumferential scan, counterclockwise rotation when viewing in the direction of isometric
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SUPPORT ENCIRCLES 270 CEGREES 6 -RC-37-1502-01 ISV-81 l
6 -RC-38-1502-01 ISV-311 6 -RC-39-1502-01 iSV-38)
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E SUPPORT 11715-WMKS-l l OA SW-8, SW-31, AND SW-38 ricure N lE z0
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i Vinjinia Electric & Power Company North Anna Power Station Unit 1 Second 10 Year interval i
Request for Relief Number NDE-41 i
1.
IDENTIFICATION OF COMPONENTS MarWWeld.No.
Line No.
Drawina No.
l GlAAA 31 2" RC 1981502-01 11715 WMKS 103BC 1
j li.
CODE REQUIREMENTS The 1983 Edition with Summer 1983 Addenda of ASME Section XI Table IWB-
'25001, examination category B J, item number B9.40 does not allow any i
limitations to the required surface examinations. Code Case N 460, "Altemative Examination Coverage for Class 1 and Class 2 Welds", allows a reduction in-coverage, if it is less than 10%
Ill.
CODE REQUIREMENT FROM WHICH RELIEF IS REQUESTED Relief is requested from examining the Code required surface examination for the identified pipe to valve wcD.
IV.
BASIS FOR RELIEF The weld listed above has been examined to the extent practical as required by i
the Code. The Code required surface examination t "arage was reduced due to a l
Code name plate band restricting access to the base metal of the pipe. The entire weld surface was examined. The surface examination coverage completed for the above listed weld was 76% of the Code required surface. Figure NDE-411 is provided detalling graphically the limit;;tions experienced. This weld is classified as a terminal end and is required to be examined by the !SI Program.
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ALTERNATE PROVISIONS it is proposed that the examination already completed at the reduced coverage be counted as meeting the Code requirements, in addition:
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1; A visual -(VT 2) examination.will be performed during the normally L
scheduled system leakage test each refueling outage; l
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I 2.
Technical Specifications requires that the reactor coolant system leak rate be limited to one gallon per minuto unidentified leakage. This value is
- calculated at least once per 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />; and
- 3.
The containment atmosphere particulate radioactivity is monitored every 12 i
hours.
I The proposed altomative examinations stated above will ensure that the overall level of plant quality and safety will not be compromised.
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