Letter Sequence Other |
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MONTHYEARRC-12-0165, Relief Request RR-III-09 Alternative Weld Repair for Reactor Vessel Head Penetration2012-10-30030 October 2012
Relief Request RR-III-09 Alternative Weld Repair for Reactor Vessel Head Penetration
Project stage: Request
ML12319A2552012-11-0505 November 2012
Relief Request RR-III-09 Supplemental Information
Project stage: Supplement
RC-12-0170, LTR-PAFM-12-137-NP, Rev. 1, Technical Basis for Westinghouse Embedded Flaw Repair for V. C. Summer, Unit 1, Reactor Vessel Head Penetration Nozzles.2012-11-0505 November 2012
LTR-PAFM-12-137-NP, Rev. 1, Technical Basis for Westinghouse Embedded Flaw Repair for V. C. Summer, Unit 1, Reactor Vessel Head Penetration Nozzles.
Project stage: Request
RC-12-0173, Technical Basis for Westinghouse Embedded Flaw Repair for V. C. Summer Unit 1 Reactor Vessel Head Penetration Nozzles2012-11-14014 November 2012
Technical Basis for Westinghouse Embedded Flaw Repair for V. C. Summer Unit 1 Reactor Vessel Head Penetration Nozzles
Project stage: Request
RC-12-0179, Relief Request RR-III-09 Request for Information Fatigue Crack Growth and Transients2012-11-16016 November 2012
Relief Request RR-III-09 Request for Information Fatigue Crack Growth and Transients
Project stage: Request
ML12325A4322012-11-26026 November 2012
Verbal Approval of Alternative for Overlay Repair of Reactor Vessel Head Penetrations
Project stage: Other
ML13101A3332013-04-19019 April 2013
Alternative RR-III-09 Alternative Weld Repair for Reactor Vessel Head Penetration (TAC No. ME9851) (RC-12-0165)
Project stage: Other
2012-11-16
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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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Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 November 26, 2012 MEMORANDUM TO: Robert J. Pascarelli, Chief Plant Licensing Branch 11-1 Division of Operating Reactor Licensing FROM:
Office of Nuclear Reactor Regulation John P. Boska, Senior Project Manager Plant Licensing Branch 11-1 Division of Operating Reactor Licensing frO. ~
Office of Nuclear Reactor Regulation
SUBJECT:
VIRGIL C. SUMMER NUCLEAR STATION, UNIT NO.1, VERBAL APPROVAL OF ALTERNATIVE FOR OVERLAY REPAIR OF REACTOR VESSEL HEAD PENETRATIONS (TAC NO. ME9851)
On November 19,2012, the U.S. Nuclear Regulatory staff from the Office of Nuclear Reactor Regulation (NRR) granted verbal approval for an alternative to Title 10 of the Code of Federal Regulations, Part 50, Section 50.55a, to allow the licensee to perform overlay repairs to reactor vessel head penetrations. The details of the verbal approval are in the enclosure to this memo. This memo documents the verbal approval as required by the NRR Office Instruction LlC-102.
Docket No. 50-395
Enclosure:
Verbal Approval Statement cc wI encl: Distribution via Listserv
U.S. NUCLEAR REGULATORY COMMISSION VERBAL APPROVAL OF ALTERNATIVE FOR OVERLAY REPAIR OF REACTOR VESSEL HEAD PENETRATIONS VIRGIL C. SUMMER NUCLEAR STATION, UNIT NO.1 DOCKET NO. 50-395 Piping and NDE Branch Chief (Tim Lupoid)
By letter dated October 30, 2012, as revised and supplemented by letters dated November 5, 2012, November 14, 2012 and November 16,2012, South Carolina Electric & Gas Company (the licensee), submitted proposed alternative Relief Request (RR)-111-09, "Alternative Weld Repair for Reactor Vessel Head Penetration," for U.S. Nuclear Regulatory Commission (NRC) review and authorization. Specifically, the licensee requested relief from American Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASME Code),Section XI, paragraph IWA-4420, "Defect Removal Requirements," that requires that defects be removed or mitigated. The licensee is proposing to use the provisions of Westinghouse Topical Report WCAP-15987-P-A, Revision 2, for performing an embedded flaw repair of the indications found in control rod drive mechanism (CRDM) penetration nozzle tubes 19, 31,37, and 52 at Virgil C. Summer Nuclear Station, Unit 1 (Summer). The licensee has submitted the proposed alternative on the basis that the proposed alternative provides an acceptable level of quality and safety, in accordance with Title 10 of the Code of Federal Regulations (10 CFR), Part 50, Section 50.55, Paragraph
- 50. 55a(a)(3)(i).
The licensee states that their proposed alternative, as described by Section 5.1 of the submittal, will use the methodology of the NRC approved WCAP-15987 -P-A with modifications. The NRC staff reviewed Section 5.1 to ensure the licensee's proposed actions would meet the requirements of WCAP-15987 -P-A, and that any modifications would be acceptable. As part of this review the NRC staff identified the following technical changes:
- 1. Cracks in the Alloy 600 penetration nozzle tube material will be embedded with two weld layers of Alloy 52 rather than three layers specified in WCAP-15987-P-A.
- 2. A single layer consisting of at least 3 beads of stainless steel 309L will be installed on the reactor vessel head clad surface 360 degrees around at a distance of approximately 0.5 inches from the toe of the J-groove weld prior to deposition of the first Alloy 52 layer.
Enclosure
- 2
- 3. Nondestructive examination of the repair will be performed in accordance with ASME Code Case N-729-1, as conditioned by 10 CFR 50.55a(g)(6)(ii)(D). The staff has reviewed each of these technical changes and finds that the proposed alternative meets the methodology approved by the NRC for an effective embedded flaw repair.
The staff has reviewed the plant-specific Westinghouse Technical Basis document LTR-PAFM-12-137-NP, Revision 2, which calculates the fatigue lifetime of the repair. The staff compared the lifetime calculations to those for plants with similar construction and notes that the present evaluation predicts a fatigue life time in excess of 20 years, as compared to at least 10 years of service life for similar plants. By letter dated November 16, 2012, the licensee described the reasons for the differences. The staff accepts the licensee's explanation of the plant-specific differences and finds that the present 20-year life time prediction calculation is acceptable.
The Piping and Non-Destructive Examinations Branch staff concludes that the proposed alternative provides an acceptable level of quality and safety in accordance with 10 CFR 50.55a(a)(3)(i).
DORL Branch Chief (Robert Pascarelli)
On the basis of the above evaluation, the NRC finds that the proposed alternative for repair of indications found on control rod drive mechanism penetration tubes numbers 19, 31,37, and 52 will provide an acceptable level of quality and safety. The NRC therefore concludes that the regulatory requirements of 10 CFR 50.55a(a)(3)(i) have been fulfilled and authorizes use of the proposed alternative at Summer for the remainder of the third 1O-year inservice inspection interval which ends December 31,2013.
All other ASME Code,Section XI requirements for which relief was not specifically requested and approved in this proposed alternative remain applicable, including third party review by the Authorized Nuclear Inservice Inspector.
Dated: November 19, 2012
November 26, 2012 MEMORANDUM TO: Robert J. Pascarelli, Chief Plant Licensing Branch 11-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation FROM: John P. Boska, Senior Project Manager IRA!
Plant Licensing Branch 11-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
SUBJECT:
VIRGIL C. SUMMER NUCLEAR STATION, UNIT NO.1, VERBAL APPROVAL OF ALTERNATIVE FOR OVERLAY REPAI R OF REACTOR VESSEL HEAD PENETRATIONS (TAC NO. ME9851)
On November 19, 2012, the U.S. Nuclear Regulatory stafffrom the Office of Nuclear Reactor Regulation (NRR) granted verbal approval for an alternative to Title 10 of the Code of Federal Regulations, Part 50, Section 50.55a, to allow the licensee to perform overlay repairs to reactor vessel head penetrations. The details of the verbal approval are in the enclosure to this memo. This memo documents the verbal approval as required by the NRR Office Instruction LlC-102.
Docket No. 50-395
Enclosure:
Verbal Approval Statement cc wI encl: Distribution via Listserv DISTRIBUTION:
PUBLIC LPL2-1 RlF RidsNrrDorlLpl2-1 RidsNrrPMSummer RidsNrrLASFigueroa Resource RidsNrrDeEpnb JWaliace, NRR ADAMS Accession No.: ML12325A432 OFFICE NRRlLPL2-1/PM NRRlLPL2-1/LA NRR/LPL2-1-BC NRRlLPL2-1/PM JBoska SFigueroa RPascarelli JBoska 11/21/12 11/21/12 11/26/12 11/26/12 OFFICIAL RECORD COpy
