Similar Documents at Surry |
---|
Category:Graphics incl Charts and Tables
MONTHYEARML20332A1592020-12-0707 December 2020 Documentation of Completion of Required Actions Taken in Response to Lessons Learned from the Fukushima Dai-Ichi Accident ML20203M1602020-07-20020 July 2020 VA Elec. & Power Co., Dominion Energy Nuclear Co. Inc., Dominion Energy Sc Inc., Millstone Power Station 2, N. Anna & Surry Power Stations 1 & 2, Virgil C. Summer Station 1, Updated Anchor Darling Double Disc Gate Valve Information & Status ML17213A0802017-07-28028 July 2017 Revised Reactor Vessel Materials Surveillance Capsule Withdrawal Schedules ML16130A5642016-05-0202 May 2016 NRC Regulatory Issue Summary 2015-16 Planned Licensing Action Submittals ML16056A1392016-03-11011 March 2016 Correction to the U.S. Nuclear Regulatory Commission Analysis of Licensees' Decommissioning Funding Status Reports ML16049A5422016-03-0101 March 2016 Tables 1 and 2 ML12124A2972010-03-11011 March 2010 Soarca Documents Review/Approval Process ML0806406572008-02-22022 February 2008 Inservice Inspection Owner'S Activity Report (Form OAR-1), Refueling Outage S1R21, Second Period of the Fourth Ten-Year ISI Interval ML0728203072007-10-11011 October 2007 Electronic Distribtion Initiative Letter, Licensee List, Electronic Distribution Input Information, Division Plant Mailing Lists ML0722801962007-08-10010 August 2007 Response to Request for Additional Information 2006 Steam Generator Inservice Inspection Reports ML0609500942006-04-0303 April 2006 North Anna Units 1 and 2, and Surry Units 1 and 2, Response to Generic Letter 2006-02, Grid Reliability and the Impact on Plant Risk and the Operability of Offsite Power ML0508804122005-03-23023 March 2005 Virginia Electric and Power Company Surry Power Station Unit 2, ASME Section XI Fourth Inservice Inspection (ISI) Interval Update, Risk Informed Inservice Inspection (RI-ISI) Program, Response to NRC Request for Additional Information ML0501802572005-01-13013 January 2005 Stations Units 1 & 2, Millstone Power Station Units 2 & 3, Request for Approval of Appendix B of Topical Report DOM-NAF-2, Qualification of Westinghouse WRB-1 CHF Correlation in the Dominion VIPRE-D Computer Code. ML0501202612005-01-12012 January 2005 December Monthly Report on the Status of Open TIAs Assigned to NRR ML0434802422004-12-29029 December 2004 November Monthly Report on the Status of Open TIAs Assigned to NRR 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. ML0424700192004-08-24024 August 2004 Attachment 4 - Table of Where ANSI N18.7 Requirements Are Addressed by NQA-1-1994 Standards And/Or the New QA Topical Report ML0312902322003-05-0808 May 2003 Graph Emergency Diesel Fuel Oil Consumption ML19093B1121978-07-14014 July 1978 Response to Concerns Use of a Certain Type Cable Manufactured by the Continental Wire and Cable Company ML19093B0681978-04-28028 April 1978 Response to Letter of 03/16/1978 Which Requested Certain Information Regarding 11/22/1977 Submittal for Permanent Solution of Low Head Safety Injection & Recirculation Spray Pumps Net Positive Suction Head Problems ML19093B0691978-04-26026 April 1978 Purpose of Letter to Present the Surry Unit No.1 Steam Generator Surveillance Program for the Outage Which Began on 04/22/1978 ML19093B0721978-04-17017 April 1978 Vepco Is Pleased to Provide Attached Responses to Request for Additional Information Dated March 16, 1978. Submittal Contains Program Description for Monitoring Fish Populations in James River Near Power Station ML19093B0201978-02-22022 February 1978 Response to 02/02/78 Letter Possibility That Reactor Cavity Annulus Seal Ring or Associated Biological Shielding Could Become Missiles in Event of Loss of Coolant Accident Pipe... ML19093B0241978-01-23023 January 1978 Response to a Request of 05/18/1977 for Additional Information on the Reactor Vessel Material Surveillance Program ML19093A1511977-12-31031 December 1977 Annual Operating Report 1977, Volume 4 ML19093B0661977-12-14014 December 1977 Forwarding Table 4.3-2, Which Was Omitted from Revision 1 to Steam Generator Program, Surry Power Station, Unit Nos. 1 & 2, Submitted on 12/2/1977, Serial No. 532 ML19093B0671977-12-14014 December 1977 Letter to Inform of a Delay in Final Installation of Reactor Coolant System Overpressure Protection System ML19093B0331977-11-30030 November 1977 Enclosed Justification for Tube Inspection Program & Plugging Criteria, Results of Completed Surry Unit No. 1 Inspection Program with Small Change in Denting ML19093A9811977-10-31031 October 1977 Purpose of the Letter Is to Present the Surry Unit No. 1 Steam Generator Surveillance Program for the Forthcoming Outage ML19094A5601977-09-26026 September 1977 09/26/1977 Letter Proposed Design Change to Allow the Lhsi Discharge Valves to Be Remotely Throttled from the Control Room ML19093A9871977-09-26026 September 1977 a Submission of a Proposed Design Change Which Allows the Lhsi Discharge Valves to Be Remotely Throttled from Control Room. Provides Completed Description of Tests Along with Evaluation of Results ML19093B0081977-08-29029 August 1977 Informs of Necessary Change to Operating Procedures to Require Throttling Lhsi Pump Discharge Valves During Recirculation Mode of Pump Operation in Order to Assure That Lhsi Pump Cavitation Does Not Occur During ... ML19098B4841977-07-0808 July 1977 Forwarding Corrected Pages to 1976 Annual Operating Report ML19098B4441977-06-28028 June 1977 Provide Requested Information Relative to Site Settlement to Close Previously Unresolved Item Identified as 76-15/1, Site Settlement Surveillance ML19098B4411977-06-0202 June 1977 Response to Letter of 4/13/1977, Provide Requested Information Regarding Iodine Spiking ML19098B4241977-04-15015 April 1977 Furnishing Information to Present Unit 1 Steam Generator Surveillance Program for Present Outage ML19094A7491976-07-0101 July 1976 Submits a Copy of the Supplement to Surry Unit Nos. 1 & 2 Startup Reports Dated 05/01 & 07/31/1973 Respectively ML19093B3531975-08-12012 August 1975 Response to Requested for Reasons of Surry Power Technical Specification TS 4.14.A.1 Be Waived on an Interim Basis Until 12:00 PM 09/20/1975 ML19098B3051975-07-23023 July 1975 5/13/1975 Summary of Meeting with NRC Staff, VEPCO, & Stone & Webster Corp to Discuss Possibility of Differential Settlement for Major Safety Related Structures ML19098B3071975-07-18018 July 1975 Confirming Vepco'S Plan to Conduct Large Load Reduction Test on Unit 2, on Tentative Date of 8/2/1975, as Discussed in Meeting of 7/9/1975 ML19093B3351975-05-16016 May 1975 Refers to Letter of 01/17/1975 Which Advised Replacement of Certain Water Temperature Monitoring Equipment at Station & Informing VEPCO of a Purchased & Installed New Monitoring System to Comply with Provisions ML19093B3361975-02-0303 February 1975 Confirms a Report of a Fish Impingement Incident Which Occurred on 01/28/1975 Reported to Paul Leech of Staff by John White of VEPCO on 01/19/1975 2020-07-20
[Table view] Category:Letter
MONTHYEARML24302A1762024-10-22022 October 2024 Core Operating Limits Report Surry 2 Cycle 33 Pattern Hot Revision 0 ML24283A0702024-10-0707 October 2024 Annual Submittal of Technical Specifications Bases Changes Pursuant to Technical Specification 6.4.J IR 05000280/20240102024-10-0202 October 2024 Biennial Problem Identification and Resolution Inspection Report 05000280/2024010 and 05000281/2024010 ML24270A0022024-09-25025 September 2024 Inservice Inspection Owners Activity Report (OAR) ML24248A1712024-09-0303 September 2024 Proposed License Amendment Request - Temporary Service Water Supply to the Component Cooling Heat Exchangers IR 05000280/20240052024-08-26026 August 2024 Updated Inspection Plan for Surry Power Station, Units 1 and 2 (Report 05000280/2024005 and 05000281-2024005), Rev 1 ML24219A2372024-08-23023 August 2024 Issuance of Amendment Nos. 319 and 319, Adoption of TSTF-577, Rev. 1, Revised Frequencies for Steam Generator Tube Inspection, ML24207A0402024-08-21021 August 2024 Summary of July 17, 2024, Public Meeting - TS 3.7/3.14 AOT for SW Piping Maintenance IR 05000280/20240112024-08-13013 August 2024 Comprehensive Engineering Team Inspection Report 05000280/2024011 and 05000281/2024011 ML24164A0012024-08-12012 August 2024 Proposed Alternative Relief Request V-1 Inservice Testing of Pressure Isolation Valves (EPID l-2023-LLR-0060) IR 05000280/20240022024-08-0101 August 2024 Integrated Inspection Report 05000280/2024002 and 05000281/2024002 05000280/LER-2024-001, Troubleshooting Initiated Unknown Turbine Trip Feature in Control System2024-07-30030 July 2024 Troubleshooting Initiated Unknown Turbine Trip Feature in Control System ML24165A1232024-07-17017 July 2024 Proposed Alternative Relief Request P-1, P-2 Inservice Testing of Residual Heat and Containment Spray Pumps (EPID l-2023-LLR-0058) ML24165A2782024-07-17017 July 2024 Issuance of Amendment Nos. 318 and 318, Reclassification of Regulatory Guide 1.97 Variable for Low Head Safety Injection ML24190A4192024-07-0808 July 2024 Inservice Testing (IST) Program for Pumps and Valves Revised Sixth IST Interval Start Date and Updated Technical Specifications References for Alternative Request V-1 ML24179A2932024-07-0101 July 2024 Notification of Inspection and Request for Information for NRC Problem Identification and Resolution Inspection ML24178A2422024-06-25025 June 2024 2023 Annual Report of Emergency Core Cooling System (ECCS) Model, Changes Pursuant to the Requirements of 10 CFR 50.46 ML24177A2792024-06-20020 June 2024 Preparation and Scheduling of Operator Licensing Examinations ML24166A0622024-06-18018 June 2024 – Proposed Alternative Relief Request P-3, P-4 Inservice Testing of Boric Acid, Component Cooling Water Pumps ML24157A0542024-06-13013 June 2024 Audit Summary in Support of License Amendment Request for Proposed Reclassification of Low Head Safety Injection Flow Instrumentation Related to Regulatory Guide 1.97 ML24143A1622024-06-12012 June 2024 – Correction to Issuance of Amendment Nos. 297 and 280 and Surry Units 1 and 2, Correction to Issuance of Amendment Nos. 317 and 317, to Change Emergency Plan Staff Augmentation Times ML24170B0532024-06-10010 June 2024 DOM-NAF-2-P/NP-A, Revision 0.5, Reactor Core Thermal-Hydraulics Using the VIPRE-D Computer Code IR 05000280/20244032024-05-22022 May 2024 Information Request for the Cyber Security Baseline Inspection, Notification to Perform Inspection 05000280/2024403 and 05000281- 2024403 ML24141A2862024-05-22022 May 2024 Information Request for the Cyber Security Baseline Inspection, Notification to Perform Inspection 05000280/2024403 and 05000281- 2024403 ML24141A2512024-05-20020 May 2024 Proposed License Amendment Request - Reclassification of Low Head Safety Injection Flow Indication Regulatory Guide 1.97 Variable - Supplemental Information ML24141A0482024-05-17017 May 2024 EN 56958_1 Ametek Solidstate Controls, Inc ML24136A2302024-05-13013 May 2024 Core 1 Cycle 33 Pattern Mdr Revision 0 ML24130A2032024-05-0909 May 2024 Proposed License Amendment Request Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator Tube Inspections Supplemental Information ML24130A2492024-05-0909 May 2024 Submittal of Information in Support of Surry Power Station Unit 1 Thermal Shield Flexure Replacement Campaign ML24130A1192024-05-0707 May 2024 Inservice Test Program for Pumps and Valves Sixth Interval Update and Associated Relief and Alternative Requests - Response to Request for Additional Information Regarding Alternative Request V-1 IR 05000280/20240012024-04-30030 April 2024 Integrated Inspection Report 05000280-2024001 and 05000281-2024001 ML24142A3852024-04-30030 April 2024 2023 Annual Radioactive Effluent Release Report ML24122C6522024-04-30030 April 2024 Annual Radiological Environmental Operating Report ML24122B3032024-04-29029 April 2024 Associated Independent Spent Fuel Storage Installation, Revision to Emergency Plan Report of Change IR 05000280/20244022024-04-29029 April 2024 Security Baseline Inspection Report 05000280/2024402 and 05000281/2024402 ML24115A1952024-04-24024 April 2024 Notification of Surry Power Station Comprehensive Engineering Team Inspection - U.S. NRC Inspection Report 05000280/2024011 and 05000281/2024011 ML24054A0142024-04-22022 April 2024 Issuance of Amendment Nos. 297 and 280, and Surry Power Station Unit Nos. 1 and 2, Issuance of Amendment Nos. 317 and 317, to Change Emergency Plan Staff Augmentation Times ML24108A1812024-04-15015 April 2024 Proposed License Amendment Request - Reclassification of Low Head Safety Injection Flow Indication Regulatory Guide 1.97 Variable Supplemental Information ML24095A2172024-04-12012 April 2024 – Review of the Spring 2023 Steam Generator Tube Inspection Report ML24088A2482024-03-26026 March 2024 Inservice Testing Program for Pumps and Valves Sixth Interval Update and Associated Relief and Alternative Requests- Response to Request for Additional Information ML24087A2082024-03-22022 March 2024 Proposed License Amendment Request Addition of Containment Limiting Condition for Operation and Surveillance Requirements ML24078A2642024-03-21021 March 2024 – Regulatory Audit in Support of License Amendment Request to Proposed Reclassification of Regulatory Guide 1.97 Variable for Low Head Safety Injection Flow Instrumentation ML24087A1522024-03-18018 March 2024 Annual Changes, Tests, and Experiments Report Regulatory Commitment Evaluation Report ML24023A5762024-03-0808 March 2024 Correction to Issuance of Amendment Nos. 315 and 315, Regarding Revised Emergency Plan for Relocation of the Technical Support Center IR 05000280/20230062024-02-28028 February 2024 Annual Assessment Letter for Surry Power Station, Units 1 and 2 - NRC Inspection Reports 05000280/2023006 and 05000281/2023006 ML24032A4712024-02-20020 February 2024 Exemption from Select Requirements of 10 CFR Part 73 - Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting ML24051A1782024-02-19019 February 2024 Proposed License Amendment Request - Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator Tube Inspections ML24057A0612024-02-19019 February 2024 And Virgil C. Summer Power Nuclear Stations - Nuclear Property Insurance Coverage IR 05000280/20230042024-02-0909 February 2024 Integrated Inspection Report 05000280/2023004 and 05000281/2023004 IR 05000280/20244012024-02-0606 February 2024 Security Baseline Inspection Report 05000280/2024401, 05000281/2024401 and 07200002/2024401 2024-09-03
[Table view] Category:Response to Request for Additional Information (RAI)
MONTHYEARML24141A2512024-05-20020 May 2024 Proposed License Amendment Request - Reclassification of Low Head Safety Injection Flow Indication Regulatory Guide 1.97 Variable - Supplemental Information ML24130A1192024-05-0707 May 2024 Inservice Test Program for Pumps and Valves Sixth Interval Update and Associated Relief and Alternative Requests - Response to Request for Additional Information Regarding Alternative Request V-1 ML23220A1482023-08-0707 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 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 - Application of Leak-Before-Break Methodology to Reactor Coolant System Branch Piping - Response to Request for Additional Information and Clarification ML21056A5412021-02-25025 February 2021 NRC Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors Final Supplemental Response ML21042B9262021-02-11011 February 2021 ASME Section XI Inservice Inspection Program Request for NRC Approval of Proposed Alternative Requests S1-I5-ISl-05 and S2-I5-ISl-06 - Response to Request for Additional Information ML22040A1012021-02-0909 February 2021 Response to Request for Additional Information 2021 Steam Generator Inservice Report ML20296A7272020-10-22022 October 2020 Stations Units 1 & 2 - Proposed License Amendment Requests Addition of Analytical Methodology to the Core Operating Limits Report for a Small Break LOCA Supplement to the Response to Request for Additional Information ML20247J6352020-09-0303 September 2020 Virginia Electric & Power Co - 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 - 316(b) 40 CFR 122.21(r)(2)-(13), Part 1 of 3 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 ML20034F0532020-01-31031 January 2020 Proposed License Amendment Request: Allowed Outage Time Extension for Replacement of Reserve Station Service Transformer C 5KV Cables to Transfer Bus F Response to Request for Clarification and Additional Information ML19350A0042019-12-12012 December 2019 License Amendment Request Addition of 24-Hour Completion Time for an Inoperable Reactor Trip Breaker Response to NRC Request for Additional Information ML19283B6222019-10-10010 October 2019 Subsequent License Renewal Application Safety Review - Documentation of Draft Third Round Requests for Additional Information ML19291B0342019-10-0101 October 2019 Response to March 12, 2012 Request for Information Enclosure 2, Recommendation 2.1, Flooding Focused Evaluation/Integrated Assessment Submittal ML19269B7342019-09-19019 September 2019 Subsequent License Renewal Application - Response to Requests for Additional Information - Sets 3 and 4 Revised SLRA Mark-Ups 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 ML19249B7672019-08-29029 August 2019 Enclosure 1 - Millstone, Units 2 and 3 and ISFSI; North Anna, Units 1 and 2 and ISFSI; and Surry, Units 1 and 2 and ISFSI - Response to EAL Scheme Change RAIs ML19204A3572019-07-17017 July 2019 Subsequent License Renewal Application Response to Request for Additional Information - Set 2 ML19198A0592019-07-11011 July 2019 Subsequent License Renewal Application - Response to NRC Requests for Confirmation of Information ML19196A1102019-07-0909 July 2019 Attachments 2, 3 & 4 - Response to NRC Request for Additional Information and Correction of SBLOCA Analysis Error and Revised Marked-Up/Typed NAPS and SPS Technical Specifications Pages ML19183A3862019-06-27027 June 2019 Subsequent License Renewal Application - Response to Requests for Additional Information - Set 1 ML19148A4212019-05-10010 May 2019 All Enclosures with Coversheets ML18304A3302018-10-25025 October 2018 Proposed License Amendment Request TSTF-490 & Update of Alternative Source Term Analyses Response to Request for Additional Information & Revised Proposed Technical Specifications ML18302A1212018-10-18018 October 2018 Response to Request for Additional Information, Revised Reactor Vessel Materials Surveillance Capsule Withdrawal Schedules ML18303A2882018-10-18018 October 2018 Response to Request for Additional Information Regarding Relief Request S2-I5-LMT-P01 Examination Category R-A, Preservice Weld Examinations ML18267A0682018-09-18018 September 2018 Attachment - Response to Request for Clarification on Proposed Consolidated Emergency Operations Facility License Amendment Requests 2024-05-07
[Table view] |
Text
. .
VIRGINIA. ELECTRIC .A.ND POWER COMPANY RIOHMOND, VIRGINIA. 23261 June 2, 1977
- Mr. Edson G. Case Serial No. 166/041377 Acting Director of Nuclear Reactor Regulation PO&M/ALH:das U. S. Nuclear Regulatory Commission Docket Nos. 50-280 Washington, D. C. 20555 50-281 License Nos. DPR-32 Attn: Mr. Robert W. Reid, Chief DPR-37 Operating Reactors Branch 4
Dear Mr. Case:
This is in response to your letter of April 13, 1977 wherein you requested information regarding iodine spiking. Two controlled plant shutdowns were conducted in 1976 in which iodine spiking data were obtained. This information is provided in the attachment to this letter.
If you or your staff have any questions r.egarding the data please feel free to contact. us.
Very truly yours,
' f -) -
<JP..t1?/l y.d/-a:,tc~ ;~?/,J C. M. Stallings Vice President-Power Supply and Production Operations Attaclnnent cc: Mr. Norman C. Moseley
i
- . .:.) :.....,, * ,, I ',,)) t l,i.>_.: : .
i
' ' I
().n ;_+ l .
b..\TE CLOCK REACTOR RCS RCS*. ' LETDOWN bEMINERALIZH 1-131:
TIME. POWER PRESSURE TEMP, PURIF.. JEC'ON a FCTR.
.. RCS .
- s. . .-,'1 ?o~e<
Sb4-."o t'\....
MW(e) PSIG . OF FLOW . CONCENTRTN
'. ~PM ' uCi/ain__:_
SUGGESTE;)
FREQllcNCY . "jq7(,_ 1/2 hr. 1/2 hr. 1/2 hr .. l/2 hre each 12.hr. 2-hr. .
8/13/76 '1600 . 802/2431 2235 366 ' *104' .- 2. SBE-2 8/13/76 163()° .805/2441 2235 566:4 104 - - " ..
8/13/76 1700 ~ 810/2439 *2235 566.1 104 3.05E-2.
. 8/13{76 *1730 .. .809/2410 2235 566.6 104
- - I:
e 8/13/76 1800 .801 /24i'o 2235 566.6 104 - - -.
I 8/13/76 1830 748/2300" 2235 565 104 - -
8/13/76 1900 675/2058 22315 563 104 - I 2.28E-:2 8/13/76 1930 -625/1912 2235 562 . 104 - -
~,,
8/i3/76 2000 545/1692 . 2i35 558 '104 *. -
- 8/13/.76 2030 436ti418 '2235 556" 104
.355/1220 ' ..
8/13/76 2100 .. '2235 .. 554' *' 104 - . S.,31E~2
. 8/13/76 '2130 276/1015 2'235 552 ~
104 - -
8/13/76 2200 199/746 2235 551 104 -
. 8/13/76 2230 141/603 2235 551 - 104 ..: .. . ' ',
. .54 7. '.- . ...io. 7 - ! . .
'i.~44 off' line 8/13/76. 2300 0 2i35 104 4.91E-2 ' MBEFF = 2.37E-3
- "8/13/.76 2330 0 2235 538 . .: . *104 - *-- '
. 8/1'.3176 2400 0 I 2235 535 t: *' . 104. . ... ..-.. .
I
~
I
.. .. '!I"
- *oATE I *. i CLOCK TIME HEJ\CTO~
PO~!ER
- RCS*. LETDO~JN bEMINER/\LlZR PURIF, bECDN. FCTR, I-'l 3i - ... COE:~ENTS
.RCS MW(e) PSIG . OF FLOW* . .
r,pf,1 . . CONCENTRTN
~,c i / om_:_ . .
SUGGESiED FREQ(J£NCY . 1/2 hr. 1/2 hr. 1/2 hr . 1/2 hr. each . 1~ hr. 2*hr. . .
. 8/14/76 *0030. 0 *2235 524 . 104* .-
8/14/76 0100 0 2235 518" 95 - 2.].5E-1
. 8/14/76 0130
. 8/14176 020'0 .. 0 1800 500 80 - - I 8/.14/76 .0230 0 1453 483 80 . - ' -. ; . .
.. .. ' . ' ' I 8/14/76 0300 0 1398 472 111 - 5.22E-l a
. .90 *.
. . 8/14/76 0330 0 1400 ., . 475 - I - .
8/14/76 0400 0 1450 46.1
.. 80 - - .
. . 80. .
. 8/i4/76 0430 *o . 1469 457 ..., -
8/,14/76 0500 0
- 1473 458 80 5.08E-1 8/14/76 0530 0 '1470 . 457' ' .. so
- . I -
8/14/76
8/14/76 0630 o* 1079 424 *68 - -
S;88E-l',
8/14/76 0700 0 1000 405 ~ 65 .:.
. ; . . 394 ,. . . .- '
8/14/76. 0730 0 . 960
.. 70 -
8/14/76 0800 0 958 409 !
~-
£
' " {'\ J r} I
,, t, t,._. . . . .
~-
' i l .\ . I D.~n: CLOCK REACTOR Res* RCS*. LETDOWN REMXNERAL!ZR 1 1..:131 ' .. . l TIME POWER PRESSURE TEMP11 PURIF uEC'ON. FCTR. RCS . COE:J.ENTS MW(e) PSIG . OF FLOW r,p~
I
\IC i / am._:_
~UGGE5iED FREQIJ'ENCY . 1/2 hr. 1/2 hro. 1/2 hr$ 1/.2 hr. each 12 hr. 2 *hr.* *. .
8/14/76 *0900. 0. 951 403 65* ,327."2 6. 2SE~l . MBEFF = 1.91E-3 8/14/76 0930 0 ;881 ;
384
.8/14/76
. 8/14"/76 10:30
.. 0 439 342 30 - -, e
- ,8/14/76 1100 0 420 341 30 438.4 6.74E-l MBEFf = 1.54E-3 I
8/14/76 1130 O' 423. 336 30 - ..
. 8/14/76 1200*
20 - I - .
8/14/76 1230 ,0 422 317 20 - -**
. 8/i4/76 1300 *o* *440 303. *,
20 . . . 6 .-33E..:l'
I
. e-.
' I a/14/76 1400'. 0 I
418 . 288 'i.
110 I 8/14/76 '1430 0 '426 280 100
- - /
8/14/76 1500 ' o* 437 271
.0 *. ' ...
. 8/14/76 1530 ._:425 '
266
- 92 *- ... - .
. 8-/14/76. 1600 0 ~27
! 26~*- 94 - - 1* : ;
I
. I
' I 1'
I I . .. . ~
,\
VI1i'GINL1 ii'J;,'t.'f,'J.~?J(j Ai.'D ,:'.J':'.ER ao**,,~1.'i'(
.t
-~7'. ;:,:.~:'j Coolant .,'?adi~ forU1:eo
?'h ' '(lfnit,? in .uOi/r.11) *
SPECIAL WESTINGHOUSE TEST \~ .
J-1_):
- % i.
- 'J-::-lel C1te 1'i*.:e I-1]1 I-f]J I-133 I-132 *r.. 131- I- tJ:, Power P.r.1."'..'J/"kt;
-. . -** .I -
lXln I 8-13 I 1600 2.. ?. 5.54-2 .4657 100
- .. -1 i,,,' lXin 8-13 1700 3 05-2 5. 51,-2 .5505 100 8-13 1900 2.28-2 5.16-2 .4419 81
{ lXin lXin I 8-13 2100 s. 31-2.7.39-2 .7185 39 I i t~xErrl lX ln I 8-13 8-13 I 2300 11, 91-2 7. 51-2 .6539 2300 2,37,,3
--- --- 0 DF=20,7
!,I JXin I 8-14 0100 2.15-1 2.05-1 .0488 0 -
- f 1 XI 11 n-111
- 1 lXin 8-111 I I CUl)ll 'i.1.Z**l 1,, *J/1-l I..(].",(, 7 0500 5.08-1 11,26-1 L.1925 I 1Xin I 8-14 07100 5 88-1 l1. 25-1 l,3835 J.Xin 8-111 I 0900 k. 25-1 4 . .1,5-1 h
- . [_ 1 Xl n 8-ll1 __1;100 1~>., 711-l ti, So'-] I. ,l/7.81 0
0 0
0 0
~
I .J).1_11 11- L/1 J. :100. i.....11::..L :1. 11,-1 L. r, :w:1 ()
I lXln 8-14 1500 'j, Q/1-l 2.90-] i':"'7370
~!Jtff.L\ 8-1/, 0900 1.3 1 DF=327.2
}11\l!FF I 8-14 I llOO l 511-3 DF**l1J8 .11 *,
I . :_':h:
I *---
I I l I I , ___
- 1
-- ::" .J c=~. *-- --- " -
\* ... '!. ---*- I I .. ,*
.... ' ***- ---- ... *- ,.... . - . -* -- . **-* *- ~- . --.~.
\
?
DATE ' r\i.,
.- :::i_-.
SURRY POWER CLOCK.
TIME
'i\~i~GTOR POii/ER RC:j PRESSURE TEMP, I LE'CDG\*JN 'J EM 11..:rnf\L XZR PURIF. PEC'ON. FGTR.
X** l J'i RCS
. ~
co11.1-:E;rr~ ..,
STATION MW(c) PSIG . OF FLO\i/ ...
r,p1,1 '
. CONCENTRTN
S'"G-~""Ea J\J :.:>, .
F..,,.~ . 1/2 hr. l/2 hr. 1/2 h~j 112 hr. each 12 hr. 2 hr.
- . u *.,,.,*ry
.: ,,
10-17
- 0730 800 2240 566 60 - - .
0800 800 10-17 2240. 566 104 - . -
10-17 . 224d 566- ..
0830' 800 104 - -
, 17 0900* .. 800 2240 566 104 -
- , I 2.30E-2 10-1,7 0940 800 2240 566-
. *commence Ramp Down ..
- 10-17 1000 760 22,.0. 564 104 ... - .. -
- 10-17 1030 700
. 2240 563 - '104 - : - - .
- 10-17 1100 640 2240 561 104 - 2.0lE-2
- 10-17 I 1130_ .
- '.., 2240,
~
560* 559 i04 -* -
. .r
- 10-17 I 1200 482 2240 553 104 - -
I 10-17 557 io4 i
1230 410 2240 - -
.:I 10 ... 17 'lJOO 330 2240 553 :
104 *
. 3.67E-2
. 10-17/ 1330 250 2240 552* 104 - -
. - ~
f 1 10-17 1400 0 2240 548 104
~
- 10-17 . ..... '
1430 0 2240 544
- 104 -
- 10-17 .
I 1500 0 2240 543 104 - 8,28E-2 10-17 1530. 0 2240* *532 I 104 - *
°DATE CLOCK 1 i,;C.:/\C1 ui{ i HCS fl.cs*. i LLJ UO\-/N i)U*ili~~i{1\LU.i"l, X'" i :J I 1 TIME PO~JER PRESSURE TEMP. :puRI F. DECDN. FCTR. RCS ' C0/1MEifl'~ , *L.
. . 'J!
M1~(e) PSIG . °F :FLOW .. -
~-----**..,1-----4----+----~----+----II r,p),{ * -11C1/a~i-------*- - - - - - ~
- 1GG:5iED
,:- n "= *. ,. y * '
1 1/ 2 hr . 1/ 2 hr
- =*~=I.J==*=='"'='..===:f==i===f.===:::;::===*===,t===== -
l * .
1-- - - * -....;..~__.1;;...o_-_1_14--*..;1;.;.6*~30;.__~~o~-1l--21_5_0_+-_53;...o__ ~*- ~6~0 -:i---- -~~--------i--------~---:
.. r 10-17 0 55
- -- r 173(), 2180 525 60 10-17 0 1 Hnn 2159 524 60*
10-17 1830 0 2100 523 60 ..
10-17 1900. 0 ,,. c:.n 488 45 :L64E-1
. 10-17 1930 o i4oo . . 475 32 - , - . ' */
i----4-----i...;...~. --4-----l---~1----+-----t-----t----~-~--~----~;
10-17 2000 0 1375' 450 80
- 10-17 2030 O* , 1350 410 , 80 10-17. 0 925. 380 80 3.0SE-1
?100 10-17 2130 0 875 370*
- 70 10-17 2200 0 67.S 350 50 10-17 2230 0 600 325 45 10..;.17 0 3.64E-1 2300 305
- 42 10-17 2330 o* 403 298 .65
- 10-17 '2400 ()
400 .. 290 100 I
I 10-18 0030 0 400 278 100 .. ..
~*
DATE CLOCK REACTOR RCS RCS.
1 LETUO~/N bE1*1I Nt:rrnL I ZH: 1.~13*1 .. .
~
co*.,,,,.,,.,,~-
TIME POWER PRESSURE TEMPo
. OF PURIF. '.JEC'ON. FCTR.
. RCS I 11'1~1\
I. .,~_:'*
h~,
i"lW(c) PSIG FLO\i/ CONCENTRTN ri pl,{. .. . "Ci / CTQL:._ .
J~G.:5iEQ
.:£0.:£:;~y . 1/2 hr., 1/2 hr. 1/2 1/2 hr. each 12 hr. 2 hr. ;
. 10-18 . 0130 0 390
- 104 - - .
0200 0 390 232 100 - :
~-
0300 0 387 202 104 2.86E-l
. . 0330 0 . 387
0 180. \
0400 387 *1 104 - - ,.
0430 0
0500 *I1*31.
- O 392 170 102 4~5* 2.23E-l 4.96E-2 0530
~
n
'} 350 164 ~: 95 -
I 0600 -
0 392 154 102 -.
. . 0630 0
381 . *145. * - -
372 145 - 1. 82E-l 0730 0 .363 95 -
f 143 0800 0 334 143 90 - :
~ ;
I I
. 0830 0 400 145*
.. 105 - -
. *I131 ::: 1.0SE-2 0900 0 4o'O 144 102 16.3* 1. 71E-l
. 0930 0 400
143 101. -
. DATE CLOCK REACTOR. RCS RCS. !\E*1 DO~/U i J Er,1 IN SRI\L r Zf1 ' L.. 1:n i
. ~
C0'I111'1!:.I\
TIME PO\.lER MW(e)
PRES5Ul1E PSIG TEMP.
OF
- ruRIF.
- FLOW ...
JEC'ON. FCTR. RCS CONCENTRTN
' ,,.,,..,.~
L*
I Geff . ,1Ci /qnL:...,_
'"G*~*Ea i .
. 1/2 hr. 1/2 hr. 1/2 hr. *112 hr. *each 12 hr. 2 hr.
- £0 .£:~:Y ,..__ --
I I.
10-18 *1030 .0 400 111 QR - - .
0 400 .. 115* I I
1100 90 1. 52E-l I
I
- 0. 400
, , 'l.n 107 .. 88 - - '-
~
. 1230 0 123 103 62 - - ..
1300 0 45 10~ 50 - 2.35E-l .. *,
- ' 0 1330 0 108 35 - - . ;
1400 0 0 108 55 -* - '
. 107 *.
1430 0
0 *ss - -
1500 0 2.79E-1 *I131=. 2.49E..:3 0 110 20 112*
1530 0 0 110
1600 0 0 110 30 - . - '
1630 () 0 110 30. -
1700 0 Q 110 30 - 2.87E;-1 .
1730 ()
0 110 30 -. -. ..
1800 0 0 110 30 - -
.' 1830 0 0 110
=--~ ~
30
. . DATE CLOCK l<~J\1,;I Ui\ RCS j RGS. ' LC i't)Gtl/N ~ i",, .. , ,
.;,1*1il\
SpI\ ..i\:L.~, ...i h*; j l 0 * .'i JI I
- \
TIME POWER PRESSURE TEM?o PURlF. JEC'ON FCTR. RCS I
co*.o.,,**r OF . I I II I C:.I I ,
h~,
. ~!W(e) PSIG FLOW
. .. .co~~~~~ 1~T~
I
r,p1,f .
,... ,.. -..... En .
11.H.l.:..) I ,
,:r, r. ,*ry . 1/2 hr. l/2 hr.. 1/2 1/2 hr. *eilch 12 hr. 2 hr.
I
...... 'J.~,, ...
. 10-18 *1900 0 0 110 30 .... 3,0QE-1 1930 b 0 30 -* - .
110
.. 2000. 0 0 110 30
~
2030 .. 0 0 110 30. - -
. . 2100 0 0 110 30 - . '
2.70E-1 ..
2130- 0 0 110 .. : 30 - - ,, '
2200 0 0' 110 30* - : - . '
2230 0 0 110 30 - -
\
2300 :0 --. a 110 40 -. 2.41E-1 '
. 2330 0 a 110 40 *- -*
1~19 0000 0 0 . 110 40. - -
110 .
0100 0 0 42 -
- 2.0SE-1 0130 0 0 . 110 42 0200 0 0 110 42 -. .- *'
0230 n n .. 110 32 - -
---~- --
0300 0 0 110 3i*
-~ ')
l.80E-l . "
- DATE HEACTOR
)\ I CLOCK RCS RCS. . LETDNIN bEMINrn1\L !ZR I
TIM~ PmJER
~IW{e)
PRESSU!1E *TEMP~
PSIG op PURIF. lJEC'ON. FCTR.
C0i1/.:Elfi':i c'
. CONCENTRTN
I GPM - I i:_C-1./-U~
. ~
.. ri .,. **ry F..,:.IJ.i:,,~ .. l/2 hr. 1/2 hr. 1/2 hr. 1/2 hr. euch 12 hr. 2 h*r.
I.--.
I
. no !
10-19 0400 0 0 bl, - .
I 10-19 0430 0 :
0 105 I.
48 -
" 0500 0 0. 105 .I 50 - l.43E-l
.. 0530 .. 0 0 105 50 - -
. . 0600 0 0 105 50 *- .... *' . ..
0630. 0 0 105 50 - - ,,
' 105 ..
.0 ,,
50 : l.35E-1 0730 0 0 105 50. - - *,
0800 0 0 1
105 50 -* -
0830 0 0 105* 50 0900 0 0 . 110 50 - 1.13E-l '
110
1000 0 0 110 - -
50
. . 1030 0 O*
106" 50 - - .
.1.llE-1 1100 0 0 106
~o *-. '
. V'llWL'lIA il'J,,\!,'JJi U A1.'i) .,';J':'J!-'.U vu*11~1::,y
.tlarU o fad ;'1:as
'(/Jnitr. in .}..l0'i/ml) *
~**:'!"', :.o._1_ __ D:i :a__o_c_t_._19_7_6_ _
SPECIAL TEST
~eJI
!rx C1ti?
110 _17 i 7'f*:~ i-131 I-1.:~
0900J2.Jo-2,5.11=::
~=;~,;~1
.1,1,49 r I-132 ~
..WI______
I-13:, J'o~c~. -= L 10 Rc,"'Jrks
!______________1
__ /
I Ix 110-12 I noq2:01-2 s.1,7- .3675 ,.51..-1 *~ I
'I rx io-111 uotlJ.01-2 s.2s- .4L132 :t.:'*~7::.L...:*':., _ _ _-1---1-------------------------,l-*----------------1*
IXEFF!1n_17 :UUl N\J ~'°ND*--*- -l----l----J-D::..F:.....:F..:::.t..::::C.:.:TO~R~"'__:_?_ _ _ _ _ _ _ _ _ _ _ __,_ _ _ _ _ _ _ -jr-*-----------~
1 f IX 110-17 I 1500 8. 28-2 ~~ _ _ ,,/,QI -- j I
- rr-j10-17 I 17002.113-12 ~Tl .9455 , - - 7 t . .
- . . * ~ 3 : : . . . 8 ' * . . : . 1 . 1 - - - t - - - i - - - - - - - - ' - - - - - - - - - - - - - - - - - - - - f - - - - - - - - - - - - - -
!1xEFF il0-17 \ 1/UL 5.07-3 NO NO DF *= 41,9 i IX \rn_,.,
- .. 19003.M-13,98- 1 .9146 /,05
-;;-,;-;-::-']t-*-c-:-*l---l..:......::-c=--.,-1---+---1--------------------------t--------~-~,---,..j
, ~ 1x 110 _ 1 7 I ?inr 3. os-1 2.9r 1.037 .1----1-1..:::.*:.::$-=.Z*..:.'.1----i-----+-------------------------*r--*---------~
1 i IX 110-1.7 2300\3. 54-i [J. Jti- 1.077 l---1-i~*..J..£. i&'_-l'....1---1---+---.!------------------~---*--+-------------,
- I LX \10-*13 \ 0100\J.Gr' 3.10- 1 1.190 /.2 .,/ 1x 110-18 \ 0300 iz.s6-:- 1 2.25- 1 1.210+---+-~<J.(;,-~--J-1---t-~-
l...1.L-! JQ-1 B I 0500 2. :)3:.. 1 2. 2r 1 .l~. _1,_s_s_*,..___ 1_7~..:Z_7-,...l ,_ __, _ _ _ 1_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _
0
~~-----,-------,--------1 I RI! 10-1 8. /) 'inn ::.:2*:..:2:.:2:....--'+.Jl..;Jl,..OR..:.":'_1'+lL....Sl.Ullnn-l---4-'-'..;.::*o~<f..,__l,_--f----f--'...;..;~RllR SYSTEM rn SE.::.'R,..:.V.::.IC;:.;E:....s_ ; @ ; . . _ 0 0 _ 3 ~ 0 - - - - - - - - - - - - - ' - - / - - - - - - - - - - - - , 1
!.u;r-:'r-*r*-110-18 I 0500 4. 95-2 NO I *No 1.--_.--"D~F_*"'_4'--"-4..::.8_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ ~ - - - - - - - - - - - - , \
I Ill! jJ.ll-lB I 0700 I .n2-1 *.1, :rn-11..117,_?.ct---f*-f'._.1_,_-I r---*----l----------------'-----------*r------*-------l f r~n 1.lu-_.Lb I 090011.n-1 .1.12-* 1,435c l*5D-I I lniir-:FF 110-:1s I 09001.05-2 _. No, - : *_Nn_f----~--i-~-1..---J.---"n~F:....::-~*6::.:1::.;;:3:.___ _ _ _ _ _ _ _ _-'---'----------+-----------,---
)t Ill\
1 j10-l8 I llOO l.52- s.srr1. 7211\---!-71..!*..!...l:::.2_-l+---i---f---@-1_1_3_0_P_R_I_M_P_RE_s_s_-_A_T_M_-_-:-----*---------- -----*---------!
1m 110-18 I uoo*2. 35-* 1* 1.4s-ti.5871 -I
- I RH Jl0-18\ 15002,79- 1 -1,55-ll.788'
- ~rnr.:r.1' 10-18 1500 2,49-3 °ND ND
,. 1?
/.Z.J DF=112.Q lI RH 10-1s I 1700 z. 8Tl 1.42-J 2. 0211:_-_ -_-:1..i..l;.;:*":...5"-l----1----i--------------------.,--------4*-------------,.--; !
Rll 110-18 \ 19003.00-' 1,,28- 112.343! /.77
\ Rd 110-18 I 210012.?0-' 1.11i- l2.368 1
- - * /.7q 1 - * - - - - ! - - - - - - - - - - - - - - - - - - - - - - ' - - * - l*
I RH jlU-.lb nou12.1i1-' 1 04-*1,2,3171---1-J..:./*~5:.=D::::_1.--+---l--------------'---~----------1~~--------*_j .
Rll 110-19 I 01002.08-*' ~?r:J2,884 _ _ J.:.fl___ l A 2
RI! 1
]0-19 0300\J Rn-I1 (i 10- 7 2,951 - - ~ - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - * .,
RII 10-19 0500 L,l,:J- 5,19- 2.207:_ _ _ .l.:..;J2_ ___ -----,-i---------*----------------------------*-----*--
l<il .LO-L9 0700 ~ 1,,31-* .1....Jjj.; , .LJl*'I , * . - - - * - - - - - - - - - - - - - - ' - - - - - - - - - - - - - * - _____________1
~ nr=:rcr ~I~ 3.111:::.:* i..'.i.2.6...: - - ~ - - _,_ -*----------------"----------*-
LIJL__ fo-11)" 1.1.00 ~ ?.. 72-21.6....illl..O.! - - ?,.2.<f*/ - - ---1------------------------~---, *------------
l-----J..---.----1-----1---,,-.--,--~~-~-:....--1--------~-------------...:..---::----~---~~----------1 L__l_-l_-L--L--1----l--..L--.L.--1-~'------'----......__-:--_._-t--:___._ _ ___.__,,_.....,--:----------' *
. -* *-**-*-*--****-. -- .... --*--*-. **- -'-****-**-** -~----- .' ..