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Category:Memoranda
MONTHYEARML23325A2022024-01-16016 January 2024
CFR Part 52 Construction Lessons-Learned Report
ML23331A7912023-12-0606 December 2023
Nov. 2023 Enviro Scoping Meetings Related to the V.C. Summer Subsequent License Renewal Application Meeting Summary Memo
ML23171A9172023-06-20020 June 2023
Summary of Meeting Concerning the V.C. Summer Nuclear Station, to Discuss Annual Assessment for Period Jan 1, 2022 Through December 31, 2022
ML22270A2042022-09-30030 September 2022
Summary of Meeting Regarding a Potential Request to Modify the Reactor Vessel Surveillance Capsule Withdrawal Schedule for VC Summer
ML21160A0312021-07-12012 July 2021
10 CFR Part 52 Lessons-Learned with Construction at Vogtle 3 & 4 and V.C. Summer 2 & 3
ML21131A1612021-05-11011 May 2021
Public Meeting Summary - 2020 Annual Assessment Meeting Regarding Virgil C. Summer Nuclear Station, Docket No. 50-395; North Anna Power Station, Docket Nos. 50-338 and 50-339; and Surry Power Station, Docket Nos. 50-280 and 50-281, Meeting
ML20105A1482020-04-10010 April 2020
Public Meeting Summary Virgil C. Summer Nuclear Station
ML19123A1332019-05-0101 May 2019
Public Meeting Summary - V.C. Summer Nuclear Station, Docket No. 50-395 to Provide Opportunities to Discuss Annual Assessment of V.C Summer Nuclear Station with the Public for Period of January 01, 20018 - December 31-2018
ML18144A1482018-05-24024 May 2018
Public Meeting Summary - Virgil C. Summer Nuclear Station Docket No. 50-395
ML17103A5222017-04-12012 April 2017
Annual Assessment Meeting Summary 2017
ML16218A4722016-08-0505 August 2016
Wectec, LLC, Commitment for Ongoing Compliance to Confirmatory Order EA-12-189 and EA-13-196
ML16068A3882016-03-0909 March 2016
Memo Ico Staff Review of V.C. Summer Nuclear Station Physical Security Plan Rev. 15 (NS113625) for Verification of ASM Order (EA-13-228) Implementation (CAC L25088)
ML16061A5252016-02-26026 February 2016
Memo T Mossman, NSIR, Technical Assistance Request - Review of Physical Security Plan for the Virgil C. Summer Nuclear Station ISFSI (72-1038, 50-395) (L25088)
ML15119A5102015-04-29029 April 2015
Meeting Summary with Members of the Public Concerning the Annual Assessment of of Virgil C. Summer Nuclear Station, Unit 1, in Blair, S.C
ML14106A4762014-04-16016 April 2014
End of Cycle 2013 Public Meeting Memo
ML13275A3102013-11-25025 November 2013
Cover Memo from Robert Caldwell to Robert Pascarelli, RAI for V C Summer Revision 10 Security Plan Review
ML13142A1572013-05-29029 May 2013
Update for 06/20/13 Meeting Notice with South Carolina Electric & Gas Company Regarding Voluntary Fire Protection Risk Initiative Self Assessment
ML13122A1782013-05-13013 May 2013
Notice of Forthcoming Meeting with South Carolina Electric & Gas Company Regarding Voluntary Fire Protection Risk Initiative Self Assessment
ML13067A2592013-03-11011 March 2013
Forthcoming Meeting with South Carolina Electric & Gas Company Regarding Proposed Emergency Plan Change for Virgil C. Summer Nuclear Station, Unit No. 1
ML12325A4322012-11-26026 November 2012
Verbal Approval of Alternative for Overlay Repair of Reactor Vessel Head Penetrations
ML12333A1252012-11-0808 November 2012
FEMA Memo from C. Burnside to Regional Assistance Committee Discussing the VC Summer Nuclear Station 10-Mile EPZ Boundary Change Request
ML1120707482011-07-26026 July 2011
July 20, 2011, Meeting Summary Pre-Application Meeting with South Carolina Electric and Gas Regarding General License Independent Spent Fuel Storage Installation Plans (TAC No. L24544)
ML1106800552011-03-0909 March 2011
Notice of Forthcoming Meeting with South Carolina Electric & Gas Company, (Sce&G), to Discuss NFPA 805 License Amendment for Virgil C. Summer Nuclear Station, Unit 1
ML1016704282010-06-17017 June 2010
Meeting Summary Notice
ML1009200352010-05-17017 May 2010
Staff Review of WCAP-16571-P Referenced in Virgil C. Summer'S GL 2004-02 Supplemental Response for Downstream Effects Evaluations of Components
ML1009105332010-04-0505 April 2010
U.S. Nuclear Regulatory Commission Staff Review of the Department of Homeland Security Consultation Reports
ML0924606222009-09-0303 September 2009
Forthcoming Conference Call with South Carolina Electric & Gas, to Discuss the Licensee'S Planned Response to the Nrc'S Request for Additional Information Pertaining to Generic Letter 2004-02, Potential Impact of Debris
ML0807400842008-03-14014 March 2008
Draft Regulatory Guide for Comment
ML0617805592006-07-10010 July 2006
Revised Closeout Letter for Bulletin 2003-01, Potential Impact of Debris Blockage on Emergency Sump Recirculation at Pressurized-Water Reactors.
ML0618101822006-07-0707 July 2006
Presentation Materials: Crack Growth Rates in a PWR Environment of Nickel-Base Alloy Welds from the Davis-Besse and V.C. Summer Plants, by Bogdan Alexandreanu, Omesh Chopra, and Bill Shack
ML0615302842006-06-0505 June 2006
Notice of Meeting with South Carolina Electric & Gas Company Online Monitoring of Instrument Channel Performance at V. C. Summer
ML0608000022006-03-22022 March 2006
Memo, Response to TIA 2005-04 Tornado Missile Vulnerability
ML0516505112005-08-16016 August 2005
Closeout Letter for Bulletin 2003-01, Potential Impact of Debris Blockage on Emergency Sump Recirculation at Pressurized-water Reactors.
ML0514604012005-05-25025 May 2005
Ltr., Correction of License Authority
ML0504901422005-02-17017 February 2005
Summary of January 13, 2005, Meeting Between the U.S. Nuclear Regulatory Commission (NRC) and Nuclear Energy Institute (NEI) on Updating the License Renewal Guidance Documents
ML0421003322004-06-30030 June 2004
Close-out of Tacs Relating to the Review of 35-day Letters Submitted in Response to the April 29, 2003, Orders Revising the Design Basis and Security Guard Force Training Enhancements and Physical Fitness Requirements
ML0408600142004-04-28028 April 2004
Renewal of Full-Power Operating License for Virgil C. Summer Nuclear Station, Unit 1 - Memo to Comm. from W. Travers
ML0404104222004-02-0404 February 2004
Request Approval of Excused Absence for Employees Affected by Inclement Weather Conditions
ML0327900132003-10-0303 October 2003
Summary of Telecommunication (Telecon) with South Carolina Electric and Gas (Sce&G) Company Representatives to Discuss Staff Questions on 10 CFR 54.4(a)(2) Criteria, and Responses to Requests for Additional Information Pertaining to the Lic
ML0326810252003-09-24024 September 2003
Results of the Virgil C. Summer SDP Phase 2 Notebook Benchmarking Visit
ML0307805472003-03-19019 March 2003
Revisions to ESFAS Technical Specifications Request for Additional Information
ML0229703632002-10-23023 October 2002
Meeting with NEI, Surry & North Anna Units 1 & 2, McGuire & Catawba Units 1 & 2, Peach Bottom Units 2 & 3, St. Lucie Units 1 & 2, Fort Calhoun, H. B. Robinson Unit 2, R.E. Ginna, and Virgil C. Summer. the Proposed Agenda Is Attached
ML0227704612002-09-27027 September 2002
Evaluation of Reactor Pressure Vessel Nozzle to Hot-leg Piping Bimetallic Weld Joint Integrity for the V.C. Summer Nuclear Power Plant, Figures 21 - 70
ML0227602642002-09-27027 September 2002
Evaluation of Reactor Pressure Vessel Nozzle to Hot-leg Piping Bimetallic Weld Joint Integrity for the V.C. Summer Nuclear Power Plant, Memorandum Dated 09/27/02 - Figure 20
ML0215706002002-06-0606 June 2002
V. C. Summer - Telephone Conference Reactor Vessel Head Inspection Results
NRC Generic Letter 1989-111989-06-30030 June 1989
NRC Generic Letter 1989-011: Resolution of Generic Issue 101 Boiling Water Reactor Water Level Redundancy
2024-01-16
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May 17, 2010 MEMORANDUM TO: Michael L. Scott, Chief Safety Issues Resolution Branch Division of Safety Systems FROM: Ervin L. Geiger /RA/
Safety Issues Resolution Branch Division of Safety Systems Office of Nuclear Reactor Regulation
SUBJECT:
STAFF REVIEW OF WCAP-16571-P REFERENCED IN VIRGIL C. SUMMERS GL 2004-02 SUPPLEMENTAL RESPONSE FOR DOWNSTREAM EFFECTS EVALUATIONS OF COMPONENTS.
The South Carolina Electric & Gas (SCE&G) Generic Letter 2004-02 supplemental response for Virgil C. Summer Nuclear Station, dated February 29, 2008 (ML080640545), stated that the downstream effects evaluations for components and systems were performed in accordance with the Nuclear Regulatory Commission staff-approved Topical Report (TR) WCAP-16406-P, Revision 1, except that the erosive wear analysis for the emergency core cooling system safety-injection-line throttle valves used coating erosion data extracted from WCAP-16571-P, Test of Pump and Valve Surfaces to Assess the Wear from Paint Chip Debris Laden Water. To facilitate the staffs review of SCE&Gs supplemental response, the staff requested that WCAP-16571-P be made available for staff review.
The wear-rate data in WCAP-16406-P used to evaluate erosion of wetted emergency core cooling system component surfaces are based on wear testing using a specific mixture of sand, concrete, glass fiber and protective coatings debris. Since the V. C. Summer debris mix is comprised mainly of coatings debris and contains only small quantities of the more erosive debris used in the WCAP-16406-P debris mix, it was advantageous for SCE&G to adjust the WCAP-16406-P erosive wear rate model using WCAP-16571-P erosive wear rates developed for coating debris.
WCAP-16571-P developed wear rates for aluminum and 300-series stainless steel using water slurries containing a mixture of inorganic zinc, epoxy and alkyd chips and particulate circulated in a loop for 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. The aluminum was used to provide a reference point for observed erosion. Using a comparison from the test data to that presented in WCAP-16406-P, a wear model was developed for the erosive effects of paint coatings (minus glass, concrete, etc.). The resultant paint coatings wear model was then used in the V. C. Summer downstream effects evaluation for the emergency core cooling system (ECCS) valves.
CONTACT: Ervin L. Geiger, NRR/DSS/SSIB 301-415-5680
M. Scott The NRC staff reviewed the method used in WCAP-16571-P to develop the erosive wear rate of metal parts due, exclusively, to coatings debris and found the method to be acceptable because it followed the same method that was used in the staff-approved TR WCAP-16406-P, revision 1, to develop the wear rate model for the more erosive debris mix. The one exception is that the WCAP-16571-P test duration was 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, versus the WCAP-16406-P test duration of 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
The longer test period is acceptable because it results in more measurable wear and a more accurate wear rate measurement.
The method in which the WCAP-16751-P and WCAP-16406-P erosion rates were applied to calculate the total valve wear is described in SCE&Gs RAI response number 22, in SCE&Gs letter to the NRC dated February 28, 2008 and, therefore, is reviewed as part of SCE&Gs GL-2004-02 response.
M. Scott The NRC staff reviewed the method used in WCAP-16571-P to develop the erosive wear rate of metal parts due, exclusively, to coatings debris and found the method to be acceptable because it followed the same method that was used in the staff-approved TR WCAP-16406-P, revision 1, to develop the wear rate model for the more erosive debris mix. The one exception is that the WCAP-16571-P test duration was 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, versus the WCAP-16406-P test duration of 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
The longer test period is acceptable because it results in more measurable wear and a more accurate wear rate measurement.
The method in which the WCAP-16751-P and WCAP-16406-P erosion rates were applied to calculate the total valve wear is described in SCE&Gs RAI response number 22, in SCE&Gs letter to the NRC dated February 28, 2008 and, therefore, is reviewed as part of SCE&Gs GL-2004-02 response.
DISTRIBUTION: RMartin ADAMS ACCESSION NO.: ML100920035 NRR-106 Office NRR/DSS/SSIB NRR/DSS/SSIB Name EGeiger: MScott:
Date 05/02/10 05/17/10 OFFICIAL RECORD COPY
