ML102950430
| ML102950430 | |
| Person / Time | |
|---|---|
| Site: | Vogtle  |
| Issue date: | 01/14/2011 |
| From: | Patrick Boyle Plant Licensing Branch II |
| To: | Southern Nuclear Operating Co |
| Boyle, Patrick, NRR/DORL/LPL2-1/415-3936 | |
| References | |
| TAC ME3003, TAC ME3004 | |
| Download: ML102950430 (15) | |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 January 14, 2011 LICENSEE:
Southern Nuclear Operating Company, Inc.
FACILITY:
Vogtle Electric Generating Plant, Units 1 and 2 SUB..IECT:
SUMMARY
OF OCTOBER 21,2010, MEETING WITH SOUTHERN NUCLEAR OPERATING COMPANY, INC. AND WESTINGHOUSE ON SUBMITIAL SCHEDULE FOR STEAM GENERATOR INTERIM REPAIR CRITERIA (TAC NOS. ME3003 AND ME3004)
On October 21,2010, a Category 1 public meeting was held between the U.S. Nuclear Regulatory Commission (NRC) and representatives of Southern Nuclear Operating Company, Inc. (SNCllicensee), Westinghouse, and other utilities at NRC Headquarters, Executive Boulevard Building, Room 3 B 18, 6003 Executive Boulevard, Rockville, Maryland.
The purpose of the meeting was to discuss the analysis, results, and submittal plan for the anticipated license amendment requests for steam generator (SG) tube Interim Alternative Repair Criteria (IARC) to support the spring 2011 outages. A list of attendees is provided as.
The licensee presented (as a spokesman for multiple utilities) information (see Enclosure 2) describing the schedule development and analytical results associated with the H* analysis in support of the planned IARC. The licensee presented details of the H* lengths that would be included in the license amendment requests and indicated what analysis has been completed.
The results were compared and contrasted to the eXisting H* values for the affected plants.
The NRC staff engaged in a dialog discussing the details of the inspection scope and completed computational analysis. The NRC staff also discussed status of the forthcoming technical report with Westinghouse and the planned submittal dates as they apply to the IARC schedule.
The submittal plan presented at the meeting is consistent with the NRC staff expectations on the current approach to resolution of the remaining issues associated with development of the permanent SG tube alternative repair criteria and an acceptable timeline for the IARC submittals to allow the staff to complete its review within the requested time frame. No outstanding issues were identified at the meeting.
Members of the public were not in attendance. Public Meeting Feedback forms were available at the meeting but no comments were received.
- 2 Please direct any inquiries to me at 301-415-3936.
- vO
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P-
- ck G. Boyle, Project Ma~
Plant Licensing Branch 11-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-424 and 50-425
Enclosures:
- 1. List of Attendees
- 2. Licensee Presentation "Industry/NRC Meeting on Interim SG Tube Repair Criteria," power point dated October 21, 2010.
cc w/encls: Distribution via Listserv
LIST OF ATrENDEES NRC MEETING WITH SOUTHERN NUCLEAR OPERATING CO. (SNC)
REGARDING SG TUBE H* CRITERION IARC SCHEDULE OCTOBER 21,2010 NAME Robert Martin Patrick Boyle Emmett Murphy Andrew Johnson John Lubinski Robert Taylor Ken Karwoski Thomas Hess Hermann Lagaliy Gary Whitman Damian Testa Ben Mays Dan Mayes Jay Smith Steve Wideman Jim Riley AFFILIATION NRC/NRRlDORL NRC/NRRIDORL NRC/NRRlDCI NRC/NRRlDCI NRC/NRRlDCI NRC/NRRlDCI NRC/NRRIDCI SNC Westinghouse Westinghouse Westinghouse LuminentiComanche Peak Duke Exelon Wolf Creek Nuclear Operating Corporation NEI
INDUSTRY/NRC MEETING ON INTERIM SG TUBE REPAIR CRITERIA OCTOBER 21,2010 1
Ipurpose
~ Establish criteria for an Interim SG Tube Alternate Repair Criteria (IARC) license amendment request to support Spring 2011 outages.
.. Discuss criteria for IARC amendment requests for Fall 2011 outages Discuss submittal dates for spring and fall 2011 outages.
111 Establish meeting date to discuss success path for Permanent ARC.
2
=
Background===
~ Previous Amendments have:
o Excluded degradation found in the portion of the tubes below 17 inches (B*)from the top of the hot leg tubesheet from the requirement to plug o Required full-length inspection of the tubes within the tubesheet but does not require plugging tubes if any circumferential cracking observed in the region greater than 17 inches from the top of the tubesheet is less than a value sufficient to permit the remaining circumferential ligament to transmit the limiting axial loads.
o Excluded degradation found in the portion of the tubes below 13.1 inches (H*) from the top of the tubesheet for Model F (HL and CL) from the requirement to plug (Current TS Requirements) 3
H-STAR Depth (in)
Square Cell Calculations Implemented H*
Whole Bundle Whole Plant Limiting Plant Limiting Condition Plant Tech Spec 95/50 95/95 95/50 95/95 Byron & Braidwood 2 (05)
SLB 16.95 13.35 13.36 N/A N/A Millstone 3 (F)
NOP 13.10 14.57 14.60 15.15 15.20 Turkey Point 3 &4 (44F 3-Loop)
NOP 17.28 17.58 17.62 17.79 17.80 Surry 1 & 2 (51 F)
NOP 16.7 17.41 17.43 17.72 17.74 Point Beach 1 (44F 2-Loop)
SLB 17 (IARC)
TBO TBO N/A N/A Results include Poisson Contraction and Probabilistic Analysis 4
Ilnt~-~im Insp~~ti-~n Scope II SG Tube Inspection Scope o TTS+3" to Interim H* Depth with Qualified Technique o Flaws identified within the Interim H* Depth will be repaired upon detection o Scope Expansion lAW Current Industry Guidance Plants will monitor for slippage 5
Interim ARC Proposal for F/51 F/44F II Model Specific H* Depths are based on:
o Square Cell Analysis which includes:
II Poisson Contraction Probabilistic Analysis o Bottom of the Expansion Transition (BET) o Eccentricity Effects SG Leakage Factor will remain the same as current one-time ARC 6
Interim ARC Proposal for D5 H* depth based on previous One Cycle Value:
o Square Cell Analysis used to conservatively support previous one cycle H* value includes:
II Poisson Contraction II Probabilistic Analysis o Bottom of the Expansion Transition (BET) o Eccentricity Effects SG Leakage Factor will remain the same as current one-time ARC o Leakage Evaluation 7
Interim ARC LAR Documentation Response to NRC Unresolved Issues Letter, 11/23/2009 Final Westinghouse Technical Report White paper on leakage Importance of BET
~ Effects of Tubesheet Bore Eccentricity 8
I Schedule Spring 2011 IARC's will be submitted by Dec 15, 2010 Plant SG Model LAR Requested Approval Date Vogtle 1 F
3/12/11 Comanche Peak 2 D5 4/4/11 Wolf Creek F
4/8/11 Seabrook 1 F
4/10/11 Braidwood 2 05 4/18/11 Surry 2 51F 5/3/11 9
Plants with Fall 2011 Outages Submittal Date o Point Beach 1 (Currently under previous IARC) o Millstone 3 o Vogtle 2 (LAR will be submitted with Vogtle 1) o Byron 2 (LAR will be submitted with Braidwood 2) 10
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ML102950430 OFFICE DORULPL2-1/PM DORULPL2-1/PM DORULPL2-1/LA NRRlCSGB/BC DORULPL2-1/BC DORULPL2-1/PM NAME PBoyle RMartin SRohrer (THarris for)
RTaylor GKulesa PBoyle (VSreeinvas for)
DATE 1/13 /11 1/13//11 1/14/11 1/13/11 1/14/11 1/14/11