Similar Documents at Surry |
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Category:Legal-Affidavit
MONTHYEARML23096A2982023-04-0606 April 2023 Units 1 and 2 and Millstone Power Station, Units 2 and 3 - Request for Approval of Appendix F of Fleet Report DOM-NAF-2-P Qualification of the Framatome ORFEO-GAIA and ORFEO-NMGRID CHF Correlations in the Dominion ML22353A6202022-12-19019 December 2022 Request for Approval of Appendix F Fleet Report DOM-NAF-2-P, Qualification of the Framatome ORFEO-GAIA and ORFEO-NMGRID CHF Correlations in the Dominion Energy VIPRE-D Computer Code ML22322A1822022-11-18018 November 2022 Proposed Emergency Plan Revision - Relocation of the Technical Support Center ML21294A3382021-10-21021 October 2021 Proposed Amendment to Relocate Unit Staff Qualification Requirements from Technical Specifications to Nuclear Facility Quality . ML21259A0852021-09-15015 September 2021 North Ann, and Surry, Units 1 and 2, Millstone, Units 2 and 3, Request for Approval of Appendix E of Fleet Report DOM-NAF-2-A Qualification of the Framatome BWU-I CHF Correlation in the Vipre-D Computer Code Response to Request for Addition ML21133A2852021-05-13013 May 2021 Stations, Units 1 & 2 and Millstone Power Station, Units 2 and 3 - Request for Approval of Appendix E Fleet Report DOM-NAF-2-A Qualification of the Framatome Bwui CHF Correlation in the Dominion Energy VIPRE-D Computer Code ML21084A2732021-03-24024 March 2021 License Amendment Request - Application of Leak-Before-Break Methodology to Reactor Coolant System Branch Piping - Response to Request for Additional Information and Clarification ML21042B3212021-02-11011 February 2021 Stations, Units 1 & 2; Millstone Power Station, Units 2 & 3 - Request for Approval of Fleet Report DOM-NAF-2 Qualification of the Framatome BWU-I CHF Correlation in the Dominion Energy VIPRE-D Computer Code ML20296A6232020-10-22022 October 2020 Request for NRC Approval to Apply Leak-Before-Break Methodology to Reactor Coolant System Branch Piping ML20149K6942020-05-28028 May 2020 Response to Request for Additional Information, to Proposed License Amendment Requests Addition of Analytical Methodology to the Core Operating Limits Report for a Small Break Loss of Coolant Accident ML19343A0192019-12-0606 December 2019 Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors ML19267A0422019-09-16016 September 2019 Subsequent License Renewal Application Response to NRC Requests for Confirmation of Information Set 2 ML19253B3302019-09-0303 September 2019 Response to Requests for Additional Information - Sets 3 and 4 - Subsequent License Renewal Application ML19204A3572019-07-17017 July 2019 Subsequent License Renewal Application Response to Request for Additional Information - Set 2 ML19196A1092019-07-0909 July 2019 Stations, Units 1 and 2 - Proposed License Amendment Requests Re Addition of Analytical Methodology to the Core Operating Limits Report for a Small Break Loss of Coolant Accident (SBLOCA) Response to Request for Additional. ML19183A3862019-06-27027 June 2019 Subsequent License Renewal Application - Response to Requests for Additional Information - Set 1 ML19095A5972019-04-0202 April 2019 Submittal of Supplement to Subsequent License Renewal Application Change Notice 2 ML18291A8352018-10-15015 October 2018 Submittal of Application for Subsequent Renewed Operating Licenses ML18218A1702018-07-31031 July 2018 Proposed License Amendment Request Revision of Analytical Methodology Reference in Core Operating Limits Report for Small Break Loss of Coolant Accident ML17251A8972017-08-24024 August 2017 Enclosure 3 to 17-296, Affidavit from Structural Group ML17251A8982017-08-16016 August 2017 Affidavit from Simpson Gumpertz & Heger, Inc ML17055C3602017-02-23023 February 2017 Submittal of Supplement to Proposed Alternative to ASME Section XI, Requirements for Repair/Replacement of Buried Circulating and Service Water Class 3 Piping with Carbon Fiber Reinforced Polymer ML15324A0442015-11-12012 November 2015 Request for Withholding Proprietary Information from Public Disclosure ML0501903172004-12-17017 December 2004 Virginia Electric and Power Company Surry Power Station Units 1 and 2 - Proposed Technical Specifications Change Request for Reactor Coolant System Pressure/Temperature Limits. Ltops Setpoint, and Ltops Enable Temperature with Exemption. ML19093B5491980-09-18018 September 1980 Motion for a Stay Pending Appeal ML19093B3211979-04-0202 April 1979 Licensee'S Answer to Show Cause Orders ML19093B0171978-04-27027 April 1978 Attached Herewith Are 40 Copies of Additional Information Concerning the Steam Generator Replacement at the Surry Power Station ML19093B0321977-12-0202 December 1977 Provide Additional Information Concerning Steam Generator Replacement, Submitting as Revision 1 to Steam Generator Program, Surry Power Station, Unit Nos. 1 & 2. ML19093B0121977-08-17017 August 1977 Attached Herewith Certain Information Which Identified & Marked as Proprietary, Being Submitted in Conjunction with Document Entitled Steam Generator Program, Surry Power Station, Unit Nos. 1 & 2. ML19098B4491977-07-0505 July 1977 Response to Letter of 5/20/1977, Furnishing Information Re Postulated Fuel Handling Accident in Containment & Submitting Revised Analysis Including Proposed Tech Spec ML19094B4611975-07-23023 July 1975 Request for Amendment to Operating Licenses, Technical Specification Change No. 32. Changes Update Organizational Chart & Maximize Effectiveness of System Nuclear Safety & Operating Committee ML19093B3341975-07-17017 July 1975 Request for Amendment to Operating Licenses DPR-32 & DPR-37 for Technical Specification Change No. 31 2023-04-06
[Table view] Category:Letter
MONTHYEARIR 05000280/20244012024-02-0606 February 2024 Security Baseline Inspection Report 05000280/2024401, 05000281/2024401 and 07200002/2024401 IR 05000280/20230102024-01-18018 January 2024 Age Related Degradation Inspection Report 05000280-2023010 and 05000281-2023010 ML23312A1922024-01-18018 January 2024 Issuance of Amendment Nos. 316 & 316 Regarding a Risk Informed Approach for Tornado Classification of the Fuel Handling Trolley Support Structure ML24003A9022024-01-0303 January 2024 Stations, Units 1 and 2, Emergency Plan Revision - Relocation of the Technical Support Center (TSC) - Editorial Correction IR 05000280/20233012023-12-28028 December 2023 NRC Operator License Examination Report 05000280/2023301 and 05000281/2023301 ML23283A3052023-12-20020 December 2023 Review of Appendix F to DOM-NAF2, Qualification of the Framatome ORFEO-GAIA and ORFEO-NMGRID CHF Correlations in the Dominion Energy VIPRE-D Computer Code (EPID L-2022-LLT-0003) (Nonproprietary) ML23352A3692023-12-18018 December 2023 Associated Independent Spent Fuel Storage Installation, Revision to Emergency Plan Report of Change ML23334A2342023-11-30030 November 2023 Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation ML23242A2292023-11-0707 November 2023 Issuance of Amendment Nos. 315 and 315, Regarding Emergency Procedure Relocation of the Technical Support Center ML23200A2622023-11-0202 November 2023 Issuance of Amendment Nos. 314 and 314, Regarding Technical Specification and Spent Fuel Pool Criticality Change IR 05000280/20230032023-10-25025 October 2023 Integrated Inspection Report 05000280/2023003 and 05000281/2023003 ML23286A0372023-10-13013 October 2023 Annual Submittal of Technical Specifications Bases Changes Pursuant to Technical Specification 6.4.J ML23285A0922023-10-12012 October 2023 Inservice Testing Program for Pumps and Valves Sixth Interval Update and Associated Relief and Alternative Requests ML23277A1172023-10-0303 October 2023 Operator Licensing Examination Approval 05000280/2023301 and 05000281/2023301 ML23230A0502023-10-0202 October 2023 5 of the Quality Assurance Topical Report - Review of Program Changes ML23256A2672023-09-21021 September 2023 Review of the Fall 2022 Steam Generator Tube Inspection Report ML23244A2352023-09-18018 September 2023 Request to Use a Subsequent Edition of the ASME Code, Section XI ML23230A0012023-09-15015 September 2023 Request to Use a Provision of a Previous Edition of the ASME Boiler and Pressure Vessel Code, Section XI, for Non-Destructive Examinations IR 05000280/20220042023-09-0101 September 2023 Reissue - Surry Power Station - Integrated Inspection Report 05000280/2022004 and 05000281/2022004 ML23244A0142023-08-30030 August 2023 Inservice Inspection Owner'S Activity Report IR 05000280/20230052023-08-23023 August 2023 Updated Inspection Plan for Surry Power Station, Units 1 and 2 (Report 05000280/2023005 and 05000281/2023005) ML23226A1862023-08-10010 August 2023 Proposed License Amendment Request - Reclassification of Regulatory Guide 1.97 Variable for Low Head Safety Injection Flow Instrumentation ML23220A1492023-08-0707 August 2023 Independent Spent Fuel Storage Installation - Submittal of Cask Registrations for Spent Fuel Storage ML23220A1482023-08-0707 August 2023 Proposed Emergency Plan Revision - Relocation of the Technical Support Center (TSC) Response to Request for Additional Information IR 05000280/20230022023-08-0404 August 2023 Integrated Inspection Report 05000280/2023002 and 05000281/2023002 ML23208A0922023-07-26026 July 2023 Request for Approval of Appendix F of Fleet Report DOM-NAF-2-P Qualification of Framatome ORFEO-GAIA and OORFE-NMGRID CHF Correlations in the Dominion Energy Vipre-D Computer Code Response ML23207A1102023-07-26026 July 2023 NRC Regulatory Issues Summary 2023-01 Preparation and Scheduling of Operator Licensing Examinations ML23198A0322023-07-18018 July 2023 Regulatory Audit Report Regarding Review of License Amendment to Modify Emergency Plan Staff Augmentation Times ML23193A9382023-07-18018 July 2023 Closeout of Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors ML23173A0602023-07-11011 July 2023 Audit Summary for License Amendment Request Revision of the Emergency Plan to Support Relocation of the Technical Support Center ML23136B1392023-06-29029 June 2023 Issuance of Amendment No. 313 Administrative Changes to Subsequent Renewed Operating Licenses and Technical Specifications ML23178A1682023-06-26026 June 2023 2022 Annual Report of Emergency Core Cooling System (ECCS) Model Changes Pursuant to the Requirements of 10 CFR 50.46 ML23152A0432023-06-22022 June 2023 Audit Plan License Amendment Requests to Change Emergency Plan Staff Augmentation Times ML23153A1732023-06-16016 June 2023 Correction to Amendment Nos. 346 & 286 Millstone, 294 & 277 North Anna, 311 & 311 Surry, and 225 Summer to Revise Technical Specifications to Adopt TSTF-554,Rev Reactor Coolant Leakage Requirement ML23163A2352023-06-12012 June 2023 Request to Use a Later Edition of the ASME Boiler and Pressure Vessel Code, Section XI, for the SPS Sixth Inservice Inspection (Isi) Intervals and VCSNS Fifth ISI Interval ML23151A6612023-05-31031 May 2023 ES-2.1-1, Surry 2023-301 Corporate Notification Letter (Revised) ML23167B0072023-05-31031 May 2023 Proposed Emergency Plan Revision - Relocation of the Technical Support Center (TSC) Supplemental Information - LOCA Dose Calculation Summary ML23117A0952023-05-10010 May 2023 Audit Plan License Amendment Request to Support Relocation of the Technical Support Center ML23130A3742023-05-10010 May 2023 Request to Delay NRC Intial Licensing Examination 2024-02-06
[Table view] Category:Response to Request for Additional Information (RAI)
MONTHYEARML23220A1482023-08-0707 August 2023 Proposed Emergency Plan Revision - Relocation of the Technical Support Center (TSC) Response to Request for Additional Information ML23208A0922023-07-26026 July 2023 Request for Approval of Appendix F of Fleet Report DOM-NAF-2-P Qualification of Framatome ORFEO-GAIA and OORFE-NMGRID CHF Correlations in the Dominion Energy Vipre-D Computer Code Response L-04-002, Stations - NRC Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors Fleet Response to Request for Additional Information2023-05-0808 May 2023 Stations - NRC Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors Fleet Response to Request for Additional Information ML23096A1972023-04-0606 April 2023 License Amendment Request - Application of Risk-Informed Approach for Tornado Classification of the Fuel Handling Trolley Support Structure - Response to Request for Additional Information ML23096A2982023-04-0606 April 2023 Units 1 and 2 and Millstone Power Station, Units 2 and 3 - Request for Approval of Appendix F of Fleet Report DOM-NAF-2-P Qualification of the Framatome ORFEO-GAIA and ORFEO-NMGRID CHF Correlations in the Dominion ML23089A3542023-03-30030 March 2023 Response to Request for Additional Information Regarding Proposed License Amendment Request to Revise Emergency Plan Staff Augmentation Times ML23044A0392023-02-11011 February 2023 Alternative Request to Defer ASME Code Section XI Inservice Inspection Examinations for Pressurizer and Steam Generator Pressure-Retaining Welds and Full Penetration Welded Nozzles Response to Request for Additional Information ML23025A1252023-01-25025 January 2023 Response to Request for Additional Information License Amendment Request, NRC Approval of Methodology Change and Reclassification of the Turbine Building as a Tornado Resistant Structure ML22343A0002022-12-0909 December 2022 Response to Request for RAI on ASME Operation & Maintenance Code Inservice Testing Program - Request for Approval of Alternative Request V-01 Use of Mechanical Agitation Process for Pressure Isolation Valve 1-SI-241 Seat Leakage Testing ML22342A4242022-12-0707 December 2022 Response to 3/12/2012 Request for Information Enclosure 2, Recommendation 2.0, Flooding Focused Evaluation Integrated Assessment Submittal Revised Commitment Completion Date ML22312A4432022-11-0707 November 2022 NRC Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors Fleet Response to RAI ML22300A1882022-10-27027 October 2022 License Amendment Request 10-Day Allowed Outage Time for Opposite Unit Auxiliary Feedwater Cross-Connect Capability Response to Request for Additional Information ML22220A2162022-08-0808 August 2022 License Amendment Request 10-Day Allowed Outage Time for Opposite Unit Auxiliary Feedwater (AFW) Cross-Connect Capability Supplemental Information ML22164A8532022-06-13013 June 2022 Proposed License Amendment Request Removal of Refueling Water Chemical Addition Tank and Replacement of Containment Sump Buffer - Response to Request for Confirmation ML22153A1352022-06-0202 June 2022 Proposed License Amendment Request (LAR) - Removal of Refueling Water Chemical Addition Tank and Replacement of Containment Sump Buffer - Response to Request for Additional Information ML21292A3022021-10-19019 October 2021 Response to Question on License Amendment Request to Revise Reactor Core Safety Limit ML21259A0852021-09-15015 September 2021 North Ann, and Surry, Units 1 and 2, Millstone, Units 2 and 3, Request for Approval of Appendix E of Fleet Report DOM-NAF-2-A Qualification of the Framatome BWU-I CHF Correlation in the Vipre-D Computer Code Response to Request for Addition ML21133A4212021-05-13013 May 2021 Response to NRC Request for Additional Information Regarding Proposed License Amendment Request Update of LOCA Alternative Source Term Dose Analysis ML21133A2852021-05-13013 May 2021 Stations, Units 1 & 2 and Millstone Power Station, Units 2 and 3 - Request for Approval of Appendix E Fleet Report DOM-NAF-2-A Qualification of the Framatome Bwui CHF Correlation in the Dominion Energy VIPRE-D Computer Code ML21098A2612021-04-0808 April 2021 Subsequent License Renewal Application, Response to Request for Additional Information Re Environmental Review ML21084A2732021-03-24024 March 2021 License Amendment Request - 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Subsequent License Renewal Application (SLRA) Environmental Review, Response to Request for Additional Information Concerning Aquatic Resources ML20181A4222020-06-29029 June 2020 Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors Response to Request for Additional Information ML20181A3082020-06-23023 June 2020 Response to Request for Additional Information on 2019 Steam Generator Inservice Inspection Report ML20269A4072020-06-0202 June 2020 Enclosure 2 - Dominion Energy Surry Power Station Vpdes Permit No. VA0004090: Application for Permit Reissuance - 316(b) 40 CFR 122.21(r)(2)-(13), Part 2 of 3 ML20269A4062020-06-0202 June 2020 Enclosure 2 - Dominion Energy Surry Power Station Vpdes Permit No. VA0004090: Application for Permit Reissuance - 316(b) 40 CFR 122.21(r)(2)-(13), Part 3 of 3 ML20269A4082020-06-0202 June 2020 Enclosure 2 - Dominion Energy Surry Power Station Vpdes Permit No. VA0004090: Application for Permit Reissuance - 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[Table view] |
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VIRGINIA ELECTRIC AND PowER COMPANY RICHMOND,VIRGINIA 23261 April 27,
- Hr. Edson G. Case, Acting Director Serial No. 222 Office of Nuclear Reactor Regulation PO&M/JTB:das U.S. Nuclear Regulatory Commission Docket Nos. 50-280 Washington, D. C. 20555 50-281 License Nos. DPR-32 Attention: Mr. A. Schwencer, Chief DPR-37 Operating Reactors Branch 1
Dear Mr. Case:
Attached herewith are 40 copies of additional infonnation concerning the steam generator replacement at the Surry Power Station. This information is being submitted as Revision No. 2 to the document "Steam Generator Project, Surry Power Station, Unit Nos. 1 and 211 submitted in our letter dated August 17, 1977, Serial No. 351. The revision contains responses to questions posed by the Staff in your letters of December 27, 1977;- January 20, 1978; February 1, 1978 and February 2, 1978.
The questions and responses are contained in Section 9. For reference purposes, the questions contain an alphanumeric designation. The alpha desig-nation refers to the NRC letter date, i.e. A is for 2/2/78,; B is for 2/1/78, C is for 1/20/78 and Dis for 12/27/77. The numeric designation is the same as the NRC numbering system in a specific letter.
The document should be revised in accordance with the attached instruc-tions. The remaining responses will be submitted in the near future.
If you have any would be pleased to meet with your staff ll(G!Jf.AltJ,1,;
da rD!lttr~
q~l-, ,9.f[CPD. -.
cc: Hr. James P. O'Reilly, Direc~r Office of Inspection and Enforcement 11001 / s I/ 'I-()
e **
COMMONWEALTH OF VIRGINIA )
) s. s.
CITY OF RICHMOND )
Before me, a Notary Public, in and for the City and Common-wealth aforsaid, today personally appeared Sam*c. Brown, Jr., who being duly sworn, made oath and said {1) that he is Vice President-Power
- Station Engineering and Construction, of the Virginia Electric and Power Company; {2) that he is duly authorized to execute and file the fore-1
- going Amendment in behalf of that Company, and {3) that the statements in the Amendment are true to the best of his knowledge and belief.
k~ _\ Giv\?n under my hand and notarial seal this ~day of
__,_~~-.....__\~--' ~-
- My Comm i s s ion exp I r e s ~....-\ ~ I~~& ,
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~~-~ . Notary_P~
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{SEAL)
STEAM GENERATOR REPAIR PROGRAM FOR THE SURRY POWER. STATION UNIT.NOS. 1 AND 2 REVISION 2 Remove Insert Table Of Contents / Pages TC-1 thru TC-3 ~ -
Pages 6.0-1 thru 6.5-1 / ~
Pages T6-l-l thru T6-l-4v-Pages 9.A.1-1 thru 9.D.9-3
~----
1\0 General
~l Purpose 1.0-1 1.£,'\.Reason For Action 1.0-1
- 1. 3 S'cope Of Work 1.2-1
'\,
- 1. 4 Sched.,~e 1.2-1
- 1. 5 Impleme'ri,ta tion Of Repair Program 1.4-1 1.6 Project O~ization 1.4-1 1.7 Quality Assur~~Program 1.6-1 1.8 Steam Generator Components 1. 7-1 2.0 "'"., \
Description Of Modified Steam Generators
- 2. 1 General Description '\ 2.0-1
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2.2 All-Volatile Treatment Chemist~y 2.1-1 2.3 Scope Of Modified Design
',.\, 2.2-5
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2.4 Design Improvements To Prevent And Inhibit Corrosion _ \\ 2.3-2 2.5 Design Refinements To Improve Performanc~ 2.4-3
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2.6 Design Changes To Improve Maintenance And Reliability 2.5-1 2.7 Design Bases \ \ . 2.6-1
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2.8 Engineering Details '\ 2.8-1
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2.9 ASME Code ~ 2.9-1 3.0 Removal And Installation Of Steam Generators \\.,
3.1 General 3. 0..:1 3.2 Guidelines And Criteria 3.0-1 \
\
3.3-1 \
3.3 Preshutdown Activities
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- 3.4 3.5 Postshutdown Activities Removal Activities 3.3-1 3.4-1
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e e Page No.
3.6 Installation Activities 3.5-3 3.7 Post Installation Activities 3.6-1 3.8 Startup Activities 3.6-1 4.0 Safety Considerations 4.1 Introduction 4.0-1 4.2 Comparison Of Modified Steam Generators With Exiting Design 4.0-1 4.3 Accident Analyses 4.3-1 4.4 Safety Implicating Associated With Repair Activities 4.4-1 5.-0 Environmental Activities 5.0-1
...; : 'I"-,
e ABSTRACT This document describes the steam generator repair program which will be conducted at the Surry Power Station, Unit Nos. 1 and 2, during the periods of about May - October 1978 for Unit No. 1 and February - July 1979 for Unit No. 2.
The purpose of the program is to repair the degradation which. has been caused by "denting" and associated affects and to restore the integrity of the genera-tors to a level equivalent to new equipment. The repair program will incorpo-rate a large number of design iniprovments which reflect the "state-of-the-art" technology which currently exists for steam generator design.
The repair program basically consists of the replacement of the existing steam generator lower assembly with a new one, with the upper assembly being refurbished; including new primary moisture separation equipment, and being re-used. The repair program is scheduled to commence at the beginning of a normal refueling outage, with the reactors being completely defueled while the repairs are being made. The repair effort will require that reactor coolant piping, feed-water piping and steam piping be cut, as well as the steam generator itself, to facilitate removal and installation. Access to the containment will be through the currently installed equipment hatch; therefore, concrete parts of the con-tainment pressure boundary will not be disturbed.
The safety implications and other potential effects of the repair program, both during the actual repair work and following the return of the unit to power, have been considered. It has been concluded that the repair program can be com-pleted without any adverse affects on the health and safety of the general public or the personnel engaged in the repair work. *
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