ML020840509
| ML020840509 | |
| Person / Time | |
|---|---|
| Site: | Oconee  |
| Issue date: | 03/11/2002 |
| From: | Mccollum W Duke Energy Corp |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| Download: ML020840509 (16) | |
Text
Duke Duke Energy Energy Oconee Nuclear Station 7800 Rochester Highway Seneca, SC 29672 W R. McCollum, Jr.
(864) 885-3107 OFFICE Vice President (864) 885-3564 FAx March 11, 2002 U.S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555
Subject:
Duke Energy Oconee Nuclear Station, Unit 3 Docket Nos. 50-270 Third Ten Year Inservice Inspection Interval Request for Relief No.02-001 Pursuant to 10 CFR 50.55a(g) (5) (iii),
attached is a Request for Relief from the requirement to examine 100% of the volume specified by the ASME Boiler and Pressure Vessel Code,Section XI, 1989 Edition with no Addenda (as modified by Code Case N-460).
This request is to allow Duke Energy to take credit for limited ultrasonic examinations on a specific Reactor Building penetration pipe to valve weld described in the attached request.
During examination of the subject Unit 2 weld, the ultrasonic examination coverage did not meet the 90% examination requirements of Code Case N-460.
Achievement of greater than 66.67%
examination coverage for this weld is impractical due to piping/valve geometry, interferences, and existing examination technology.
Therefore, Duke Energy requests that the NRC grant relief as authorized under 10 CFR 50.55a(g) (6) (i).
If there are any questions or further information is needed you may contact R.
P.
Todd at (864) 885-3418.
Very truly yours, Attacmll
- r.
Site Vice P sident Attachment
U.
S. Nuclear Regulatory Commission March 11, 2002 Page 2 xc w/att: L.
A.
Reyes, Regional Administrator U.S. Nuclear Regulatory Commission, Region II Atlanta Federal Center 61 Forsyth St.,
- SWW, Suite 23T85 Atlanta, GA 30303 L.
N. Olshan, Project Manager, Section 1 Project Directorate II Division of Licensing Project Management Office of Nuclear Reactor Regulation U.
S. Nuclear Regulatory Commission Washington, DC 20555-0001 xc(w/o attch):
Scott Freeman Acting NRC Senior Resident Inspector Oconee Nuclear Station Mr. Virgil Autrey Division of Radioactive Waste Management Bureau of Land and Waste Management SC Dept. of Health & Environmental Control 2600 Bull St.
- Columbia, SC 29201
Duke Energy Corporation Oconee Nuclear Station Unit 3 THIRD 10-YEAR INTERVAL REQUEST FOR RELIEF NO.02-001 Duke Energy Corporation has determined that conformance with certain ASME Section XI Code requirements is impractical. Therefore, pursuant to 10CFR50.55a(g)(5)(iii), Duke Energy Corporation requests relief from applicable portions of the code.
Included in this request is a single Examination Category C-F-2 weld.
The Oconee Unit-3 Inservice Inspection Plan was written to the requirements of the 1989 Edition of ASME Section XI, no addenda.
The exam in this Request for Relief was performed during EOC-1 9, the last outage in the second period of the third ten-year interval.
Code Case N-460 applies to the examination performed during this outage.
System/Component(s) for Which Relief is Requested:
A.
Pipe to Valve 3PR-2:
ID Number Item Number 3-20B-21-18-18 C05.051.046 This weld is part of the Reactor Building Purge System Penetration Piping and is located in the exterior penetration room.
Code Requirement:
Examination Category C-F-2: ASME Section XI, Figure IWC-2500-7 (a),
Examination Volume C-D-E-F.
Illh Code Requirement from which Relief is Requested:
Relief is requested from the requirement to examine 100% of Volume C-D-E-F.
Page 1 of 3
IV.
Basis for Relief:
Pipe to Valve 3PR-2 weld 3-20B-21-18-18 (Item C05.051.046) is limited to 66.67% coverage of the required volume due to the proximity of a penetration. In order to achieve more coverage, the penetration would have to be removed or re-designed to allow scanning from both sides of the weld. That would be impractical. Reference Attachment A for a drawing of the pipe to valve 3PR-2 weld.
Reference Attachment B for a copy of the examination records for the weld addressed in this request.
V.
Alternate Examinations or Testing:
The use of radiography as an alternate volumetric examination of the weld/component referenced in this request is not a viable option.
Restrictions to performing radiography are primarily due to limited access for placement of film due to the proximity of the penetration. No additional examinations are planned during the current interval for weld 3-20B-21 18-18. Duke Energy Corporation will continue to use the most current ultrasonic techniques available to obtain maximum coverage for future examinations of this weld.
VI.
Justification for the Granting of Relief:
The Code requires 100% volumetric examination of the subject weld.
However, as discussed in Section IV above, the 100% volumetric examination is impractical. To meet Code examination requirements, modification would be necessary to allow scanning from both sides of the weld. A modification of this nature would not be practical for Duke Energy.
The subject weld was examined to the maximum extent practical using ultrasonic techniques qualified in accordance with the requirements of ASME Section Xl, Appendix VIII, Supplements 2 and 3 of the 1995 Edition with the 1996 Addenda as administered by the PDI. This weld was inspected by visual examination during construction and verified to be free from unacceptable surface fabrication defects.
Duke Energy Corporation will use the existing pressure test program established for this piping segment to compliment the limited examination coverage.
VII.
Implementation Schedule:
Duke Energy Corporation will continue to use ultrasonic examination procedures to obtain maximum coverage to the extent practical for inspections in future intervals of the item number referenced in Section I of this Request for Relief.
Page 2 of 3
The following individuals were involved in the development of this request for relief:
B. W. Carney Jr., Oconee Engineering provided input to Sections V and VI of this request.
J. J. McArdle Ill, NDE Level III provided input for Sections II, Ill, IV, and V of this request.
L. C. Keith, Oconee ISI Plan Manager compiled and completed this request.
Sponsored By:
Approved By:
0.a C8 v
c Date:
Date:
Page 3 of 3 AI
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Attachment B Request for Relief 02-001 Page /
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DUKE POWER COMPANY NDE-UT-5 UT PROFILE/PLOT SHEET Revision 1 EXAMINATION SURFACE 1 4
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A Level: T Date: vo z,_oi
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DUKE POWER COMPANY FORM NDE-UT-10 ULTRASONIC INDICATION RECORD FOR PIPING Revision 0 Station:
Oconee Unit:
3 Component/Weld ID: 3-20B-21-18-18 Date:
10/25/2001 Surface Condition:
A ROUND Item No: C05.051.046 Examiner: Jay A. Eaton Level:
III Procedure:
NDE-600 Rev:
14 FC:
N/A Examiner: James L. Panel
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Calibration Sheet No:
1 II 0103012 Lo:
9.1.1.1 Configuration:
32 to S1 Pipe to Valve (Valve 3PR-2)
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DUKE POWER COMPANY FORM NDE-UT-4 ISI LIMITATION REPORT Revision 1 Component/Weld ID: 3-20B-21-18-18 Item No: C05.051.046 Remarks:
SURFACE BEAM DIRECTION DUE TO VALVE CONFIGURATION 0] NO SCAN OLIMITED SCAN Ei 02
[1 1 2 K cw 0 ccw FROM L N/A to L __-N/A INCHES FROM WO
.2" to BEYOND ANGLE:
0 0 F] 45 Z 60 E3 Other FROM 0
DEG to 360 DEG SURFACE BEAM DIRECTION 0] NO SCAN 03 LIMITED SCAN
[3 1 0l 2 E0 1 E0 2 El cw El ccw FROM L to L INCHES FROM WO to ANGLE:
E0 0 E0 45 [0 60 0l Other FROM DEG to DEG SURFACE BEAM DIRECTION El NO SCAN El LIMITED SCAN E]
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[1 2 El 1 El 2 El cw El ccw FROM L to L INCHES FROM WO to ANGLE:
E0 0 03 45 E0 60 0l Other FROM DEG to DEG SURFACE BEAM DIRECTION El NO SCAN E3 LIMITED SCAN E]
02 0l 1 0l 2 El cw El ccw FROM L to L INCHES FROM WO to ANGLE: 0 0 0- 45 0l 61 0l Other FROM DEGto Prepared By:
Level:
Date:
Sketch(s)atached Pyes El Sheet 5 of Reviewed By:
Date:
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DUKE POWER COMPANY Form NDE-UT-8 ULTRASONIC INDICATION RESOLUTION SHEET Revision 1 Acceptance Standard:
INDICATION #1 WAS DETERMINED TO BE A GEOMETRIC REFLECTOR DUE TO I.D. WELD ROOT GEOMETRY. THIS WAS CONFIRMED BY 1. THE SIGNAL WOULD NOT HOLD UP TO SKEWING 2. THE 700 SHEAR WAVE RESPONSE WAS 10% FSH VERSES 60% FSH WITH THE 600 SHEAR WAVE 3. PLOTTING OF THE INDICATION.
Item No: C05.051.046 Acceptable Indications: #1 Rejectable Indications:
NONE These indications have been co pared with previous ultrasonic data El Yes 2 No previous dataavailable Examiner:
Level:
Date:
/0 Jay A. Eaton
"*V III 10/25J20 Reviewer:
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2*Date:
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NA DUKE POWER COMPANY NDE-91-1 Limited Examination Coverage Worksheet Rvso Examination Volume/Area Defined 0 Base Metal 0
Weld El Near Surface EU Boltinq El Inner Radius Area Calculation Volume Calculation SEE DRAWINGS 0.16SQ.IN.
0.16 SQ.IN. X 151 IN. = 24.16 CU.IN.
Coverage Calculations Area Length Volume Volume Beam Examined Examined Examined Required Scan # Angle Direction (sq.in.)
(in.)
(cu.in.)
(cu.in.)
Percent Coverage 1
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