ML20129A014
| ML20129A014 | |
| Person / Time | |
|---|---|
| Site: | Quad Cities  |
| Issue date: | 10/10/1996 |
| From: | Pearce L COMMONWEALTH EDISON CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| LWP-96-075, LWP-96-75, NUDOCS 9610210339 | |
| Download: ML20129A014 (3) | |
Text
Comiminwealth 1.dman Onnpan)'
I Quad Citics Generating Mation 22710 206th Asenar Nonh e*
Gardos J,11. 612 il 9" 40 Tri w9 <,s i 22 n LWP-96-075 October 10, 1996 U.S. Nuclear Regulatory Commission Washington, D.C. 20555 Attn:
Document Control Desk
Subject:
Quad Cities Station Unit 2 Augmented Examination of the RPV Shell Welds Pursuant To 10CFR50.55a(G)(6)
NRC Docket Nos. 50-265 In accordance with the rules of 10CFR50.55a(g)(6)(ii)(A), Quad Cities Station plans to conduct an augmented examination of the Unit 2 reactor pressure vessel (RPV) shell welds during the upcoming refuel outage Q2R14.
Quad Cities Station expects that less than 90% of the examination volume of RPV shell welds (ASME Section XI, Category B-A, Item Bl.10 shell welds) will be achieved using currently available remote examination technology.
Less than 90% examination volume does not satisfy the augmented examination requirements for the RPV shell welds.
However, subsection 6(ii)(A)(5) allows licensees unable to satisfy this augmented examination requirement to propose an alternative that provides an acceptable level of quality and safety.
Pursuant to the rules of subsection 6(ii)(A)(5), Quad Cities Station proposes the following examination plan for RPV shell welds (item Bl.10 RPV shell welds).
PROPOSED EXAMINATION PLAN The RPV shell welds (ASME Section XI, Category B-A, Item Bl.10 shell welds) will be ultrasonically examined (a) remotely from the inside of the reactor vessel to the extent possible and (b) manually from the outside of the vessel to the extent practical where remote inside examination is not achieved and where scheduled bioshield wall blocks and insulation materials disassembly allows access.
The remote internal examination will be performed in accordance with the remote ultrasonic examination procedure by General Electric, which was demonstrated at the Performance Demonstration Initiative (PDI)
Qualification in a manner conducive with the requirements of Appendix VIII of ASME Section XI, 1992 Edition through 1993 Addenda. As such, Regulatory Guide 1.150 is not applicable for the remote internal l
examination.
The aforementioned remote internal examinations will be supplemented by manual ultrasonic examinations that will be performed from the outside surface to the extent practical.
The manual ultrasonic examinations will be performed in accordance with the rules of IWA-2230 of ASME Section XI,1989 Edition, as modified by Regulatory 9jp079 Guide 1.150.
9610210339 961010 PDR ADOCK 05000265 STMGR\\07$96 L P
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LWP-96-075 October 10, 1996 Page 2 Augmented Examination Coverage:
An accessibility study of the RPV shell welds was performed in preparation of this augmented examination. This study was completed before the installation of shroud repair hardware during Q2R13. Quad Cities Station does not intend to remove any shroud repair hardware to perform the remote internal examination. The shroud repair hardware location is such that examination of weld VSC2-22 will not be possible and coverage on CW-C2C3 will be reduced. All remaining weld coverages will be unaffected by the shroud repair hardware and the estimated coverage is 65.1%.(see attached table for projected weld coverages)
Although the greater than 90% coverage required under 10CFR50.55a l
(g)(6)(ii)(A) will not be achievable for all welds, an acceptable level of quality and safety will be achieved based on the ara ments documented in a report, BWRVIP-05, "BWR Reactor Pressure Vest.el Shell Weld Inspection Recommendations," issued by the Boiling Water Reactor Ownars Group Vessel and Internals Project (BWRVIP).
This document provides the technical and economic basis for a reduction in examination scope for the BWR RPV shell weld examination.
This report I
has been submitted for NRC review by the BWR Owners Group.
1 A final report will be submitted to the Commission for information within 90 days after the completion of the refuel outage, which will provide details on examination coverage and results.
Respectfully, i
COMMONWEALTH EDIS0N COMPANY i
~
Q ITIE UCLEAR POWER STATION
~. hi{ {L L. W. Pearce Station Manager LWP/CP/plm Enclosure cc:
A. B. Beach, Regional Administrator, Region III R. M. Pulsifer, Project Manager, NRR C. Miller, Senior Resident Inspector, Quad Cities R. J. Singer, MidAmerican Energy Company D. C..Tubbs, MidAmerican Energy Company P. Piet, Licensing, Comed F. Spangenberg, Regulatory Affairs Manager, Dresden INPO Records Center j
' STMORW7596.LWP
~
i QUAD CITIES UNIT 2
/
PROJECTED COVERAGES
% COVERAGE
% COVERAGE PROJECTED
% x LENGTH
% x LENGTH PROJECTED (WITHOUT WELD (WITH (WITHOUT WELD ID (WITH REPAIR)
REPAIR)
LENGTH REPAIR)
REPAIR)
VSC177 0.0%
0.0%
133 0.0 0.0 VSC1-197 0.0%
0.0%
133 0.0 0.0 VSC1-317 85.7 %
85.7 %
133 114.0 114.0 -
CW-C1C2 53.3 %
53.3 %
790.1 421.1 421.1 VSC2-22
- 0.0%
51.8 %
133 0.0 68.9 VSC2-141 100.0 %
100.0%
133 133.0 133.0 VSC2-261 55.6 %
55.6 %
133 73.9 73.9 CW C2C3
- 53.4%
67.0 %
790.1 421.9 529.4 VSC3-77 22.2 %
22.2 %
133 29.5 29.5 VSC3-197 23.2 %
23.2 %
133 30.9 30.9 VSC3-317 72.0 %
72.0 %
i33 95.8 95.8 CW-C3C4 95.4 %
95.4 %
790.1 753.8 753.8 VSC4-60 100.0 %
100.0%
129.9 129.9 129.9 VSC4-99 100.0 %
100.0 %
129.9 129.9 129.9 VSC4-219 79.0 %
79.0 %
129.9 102.6 102.6 VSC4-339 100.0 %
100.0 %
129.9 129.9 129.9 CW-C4FLG 76.8 %
76.8 %
790.1 606.8 606.8 TOTALS 4877.0 3173.0 3349.3
% COVERAGE WITH REPAIR =
65.1 %
% COVERAGE WITHOUT REPAIR =
68.7 %
- welds affected by shroud repair hardware h:\\exceli7596LWP.xis
.