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| | issue date = 01/04/1979 | | | issue date = 01/04/1979 |
| | title = Forwards LER 78-045/03L-0,78-046/03L-0 & 78-049/03L-0 | | | title = Forwards LER 78-045/03L-0,78-046/03L-0 & 78-049/03L-0 |
| | author name = STALLINGS C M | | | author name = Stallings C |
| | author affiliation = VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.) | | | author affiliation = VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.) |
| | addressee name = OREILLY J P | | | addressee name = Oreilly J |
| | addressee affiliation = NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) | | | addressee affiliation = NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| | docket = 05000280 | | | docket = 05000280 |
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Forwards Info Concerning Changes to ECCS Evaluation Models & Application in Existing Licensing Analyses for Surry & North Anna Power Stations,Units 1 & 2
ML18152B4231999-05-26026 May 1999
Informs That Vepc Will Revise 180 Day Response to NRC GL 96-05,within 120 Days of Date of Ltr to Incorporate Commitment to Participate in Joint Owners Group Program as Applicable
ML18152B4211999-05-25025 May 1999
Forwards Rev 1 to Relief Request P-11 to Clarify Original Intent of Request by Specifically Requesting Relief from Requirements of Section 6.1 of OM-6
ML18152B4171999-05-17017 May 1999
Provides Notification of Number of Steam Generator Tubes That Were Plugged During Spring 1999 Refueling Outage Planned ISI
ML18152A3701999-05-13013 May 1999
Submits Proposal to Use Provisions of ASME Section XI Code Case N-597 for Analytical Evaluation of Class 1,2 & 3 Carbon & Low Alloy Steel Piping Components Subjected to Wall Thinning as Result of Flow Accelerated or Other Corrosion
ML18152B4121999-05-0303 May 1999
Forwards Application for Renewal of License for SV Ross. Encl Withheld Per 10CFR2.790(a)(6)
ML18152B4101999-04-29029 April 1999
Forwards Scope & Objectives for 990803 Surry Power Station Emergency Exercise.Without Encls
ML18152B6561999-04-23023 April 1999
Forwards Annual Radioactive Effluent Release Rept for Surry Power Station,Jan-Dec 1998, Which Includes Summary of Quantities of Radioactive Liquid & Gaseous Effluents & Solid Waste Released During CY98
ML18152B6491999-04-13013 April 1999
Forwards MOR for Mar 1999 for Surry Power Station,Units 1 & 2.MOR for Feb 1999 Incorrectly Stated Gross Electrical Energy Generated (Mwh) for Unit 2.Rept Should Have Stated Monthly Figure as 568965.0
ML18151A5851999-03-31031 March 1999
Forwards Rept on Status of Decommissioning Funding for Each of Four Nuclear Power Reactors,Per 10CFR50.75(f)(1)
ML18152A2801999-03-30030 March 1999
Forwards Summary of Structural Integrity Evaluation of Thermally Induced Over Pressurization of Containment Penetration Piping During DBA for SPS & Naps,Units 1 & 2,per GL 96-06.Draft Proposed UFSAR Revised Pages,Encl
ML18153A2721999-03-29029 March 1999
Forwards LER 99-002-00 Per 10CFR50.73.Listed Commitments Contained in Ltr
ML18153A3421999-03-26026 March 1999
Provides Updated Medical Status Rept for Wb Gross in Accordance with License SOP-20476-02,Docket 55-5228,as Amended by 980320 License Amend.Informs That Gross Exhibits No Performance Problems & Will Continue on Current Medicine
ML20204H0331999-03-17017 March 1999
Forwards Rev 5 to PSP for Surry & North Anna Power Stations & Associated Isfsis.Description & Justification for Changes Included with Plan Rev.Rev 5 to PSP Withheld Per 10CFR73.21
ML18153A3411999-03-15015 March 1999
Forwards Signed Applications & Medical Certificates for Initial License at Surry Power Station Units 1 & 2 for Listed Individuals.Without Encls
1999-09-08
[Table view]
Category:UTILITY TO NRC
MONTHYEARML18153C3661990-09-20020 September 1990
Forwards Topical Rept VEP-NE-3-A, Qualification of WRB-1 CHF Correlation in VEPCO Cobra Code.
ML18153C3701990-09-18018 September 1990
Forwards Addl Info Re Facility Containment Isolation Valve Type C Test,Per 900914 10CFR50,App J Exemption Request
ML18152A2341990-09-14014 September 1990
Requests Exemption from 10CFR50,App J Section III.D.3 Re Local Leak Rate Testing During Every Reactor Shutdown. Basis & Justification for Exemption Encl
ML20059J3341990-09-13013 September 1990
Forwards Rev 15 to Nuclear Security Personnel Training & Qualification Plan.Rev Withheld
ML18151A2901990-08-31031 August 1990
Forwards Rev 10 to Updated FSAR for Surry Power Station Units 1 & 2,representing Second Updated FSAR Submitted This Yr
ML18153C3451990-08-29029 August 1990
Forwards Proprietary Semiannual Fitness for Duty Program Performance Data Rept for 900103-0630.Rept Includes Summaries of Mgt Sanctions Imposed,Actions Taken to Correct Program Weaknesses & Events Reported to Nrc.Encl Withheld
ML18153C3381990-08-22022 August 1990
Responds to NRC 900723 Ltr Re Violations Noted in Insp Rept 50-280/90-21 & 50-281/90-21.Corrective actions:as-found-as- Left Conditions of Auxiliary Feedwater Evaluated & Found Operable
ML18153C3391990-08-22022 August 1990
Requests Approval for Use of Plugs Fabricated of nickel- chromium-iron Uns N-06690 Matl (Alloy 690) to Plug Tubes in Steam Generators for Mechanical & Welded Applications
ML18153C3161990-08-0101 August 1990
Provides Supplemental Response to NRC 900629 Ltr Re Electrical Crossties,Load Shedding on Nonblackout Unit & Emergency Diesel Generator Reliability.Emergency Diesel Generator Reliability Program in Place,Per Reg Guide 1.155
ML18153C3171990-08-0101 August 1990
Resubmits Synopsis of Changes to Updated Operational QA Program Topical Rept Vep 1-5A
ML18153C3091990-07-30030 July 1990
Provides Outline of Plan to Meet 10CFR50 App G Requirements, for Low Upper Shelf Energy Matls,Per NRC 900521 Request
ML18153C3061990-07-30030 July 1990
Forwards Revised Tech Spec Pages,Addressing Constitution of Quorum & Timeliness of Mgt Safety Review Committe Meeting Minutes,Per NRC Request
ML18153C3051990-07-26026 July 1990
Advises That Util Submitted Decommissioning Funding Plan & Financial Assurance Info W/Isfsi License Application
ML18153C3041990-07-26026 July 1990
Responds to NRC 900626 Ltr Re Violations Noted in Insp Rept 50-281/90-20.Corrective Actions:Leaking Drain Plug & Upper Drain Plug on Motor Replaced W/Oil Drain Assemblies Composed of Piping & Valves
ML18153C3031990-07-26026 July 1990
Advises of Withdrawal of Request for NRC Review & Approval of Engineering Evaluation 8.Revised Evaluation Will Be Maintained Onsite for NRC Audit During Future Insps,Per Generic Ltr 86-10
ML18153C3101990-07-26026 July 1990
Forwards Decommissioning Financial Assurance Certification Rept..., Nuclear Decommissioning Trust Agreement & Nonqualified Nuclear Decommissioning Trust Amended & Restated Trust Agreement, Per 10CFR50.75
ML18153C2901990-07-18018 July 1990
Responds to NRC Bulletin 90-001, Loss of Fill-Oil in Transmitters Mfg by Rosemount. Listed Transmitters Compiled.Transmitters Found Installed within Reactor Protection or ESFAS Have Been Replaced
ML18153C2861990-07-12012 July 1990
Requests Cancellation of Operator Licenses for Listed Individuals.Licenses No Longer Required
ML18153C2871990-07-11011 July 1990
Responds to Violations Noted in Insp Repts 50-280/90-18 & 50-281/90-18.Corrective Actions:Permanent Drain Line Installed & Matrix Which Describes Proper Ventilation Alignment for Plant Conditions Provided for Personnel Use
ML18153C2851990-07-0606 July 1990
Forwards Response to Generic Ltr 90-04 Re Status of Generic Safety Issues
ML18153C2831990-07-0303 July 1990
Advises That MW Hotchkiss No Longer Needs Operator License SOP-20548-1.Cancellation of License Requested
ML18153C2821990-07-0303 July 1990
Requests Exemption from 10CFR50,App J,Paragraph III.A.6(b), Which Requires That When Two Consecutive Periodic Type a Tests Fail to Meet Applicable Acceptance Criteria Type a Test Shall Be Performed at Plant
ML18153C3591990-06-28028 June 1990
Responds to SALP Repts 50-280/90-16 & 50-281/90-16 for Period 890701-900331.Corrective Actions Focus on Issues of Maint Backlog,Maint planning,post-maint Testing,Staffing & Procurement
ML18153C2611990-06-21021 June 1990
Responds to NRC 900522 Ltr Re Violations Noted in Insp Repts 50-280/90-07 & 50-281/90-07.Corrective actions:as-built Configurations of 120-volt Ac & Dc Vital & Semivital Panel Breaker Installations Verified to Be Acceptable
ML18153C2581990-06-18018 June 1990
Forwards Reissued Semiannual Radioactive Effluent Release Rept,Jul-Dec 1989. Rept Contains Info Re SR-89,Sr-90 & Fe-55 Analytical Results for Liquid Composite Samples
ML18153C2591990-06-18018 June 1990
Forwards Response to NRC 900524 Request for Addl Info Re NRC Bulletin 88-004, Potential Safety-Related Pump Loss. Engineering Will Initiate Study to Evaluate Enhancements of Cooldown & Possible Heatup Operation
ML18153C2541990-06-15015 June 1990
Forwards Corrected Tech Specs Page 3.1-3,per Identification of Typo in 900522 Application for Amends to Licenses DPR-32 & DPR-37
ML18153C2521990-06-14014 June 1990
Responds to NRC 900515 Ltr Re Violations Noted in Insp Repts 50-280/90-09 & 50-281/90-09.Corrective Actions:Abnormal Procedures & Fire Contingency Action Procedures Being Upgraded Via Technical Procedure Upgrade Program
ML18153C2501990-06-0808 June 1990
Confirms That Primary Policy Re Onsite Property Damage Insurance,Provided by Nuclear Mutual Limited
ML18153C2361990-05-29029 May 1990
Responds to NRC 900427 Ltr Re Violations Noted in Insp Repts 50-280/90-14 & 50-281/90-14.Corrective Actions:Personnel Involved Counseled as to Importance of Properly Recording & Reporting Surveillance Data
ML18153C1971990-04-24024 April 1990
Responds to Unresolved Items Noted in Insp Repts 50-338/89-12,50-339/89-12,50-280/88-19 & 50-281/88-19 Re Secondary Sys Containment Leakage & Concludes Leakage Need Not Be Quantified & Not Included in as-found Leakage
ML18153C1961990-04-20020 April 1990
Forwards Facility Previous Tests & Projected Leakage Totals for Type C Testing for Valves & Penetrations,Per 900108 Ltr
ML18153C1901990-04-18018 April 1990
Requests That Operator License OP-20447-1 for Ja Yourish Be Cancelled
ML18153C1861990-04-0505 April 1990
Requests Exemption from 10CFR50,App J,Paragraph III.A.6(b). Util Implemented Corrective Action Program Which Meets Intent of Regulation in Establishing Containment Integrity
ML18153C1671990-03-30030 March 1990
Submits Supplemental Response to 10CFR50.63, Loss of All AC Power. Understands That Load Mgt Schemes for Both Blackout & Nonblackout Units Allowed by Station Blackout Rule
ML18151A2551990-03-30030 March 1990
Forwards Rev to, Corporate Emergency Response Plan & Rev to, Corporate Plan Implementing Procedures.
ML18151A4941990-03-29029 March 1990
Forwards Listed Info Re Licensee Guarantees of Payment of Deferred Premiums,Per 10CFR140.21(e)
ML18153C1631990-03-27027 March 1990
Responds to Violations Noted in Insp Repts 50-280/86-05 & 50-281/86-05.Corrective Action:Surveillance Tests Being Performed in Accordance W/Administrative Requirements of Station Procedures & Plans Implementing New Review Process
ML18153C1551990-03-20020 March 1990
Clarifies 900108 Request for Exemption from 10CFR50,App J Re Type C Testing Requirements
ML18153C1511990-03-19019 March 1990
Responds to Generic Ltr 89-19, Request for Action Re Resolution of USI A-47. Operability & Surveillance Requirements for Steam Generator Overfill Protection Sys Will Be Incorporated in Tech Spec Change
ML18153C1661990-03-16016 March 1990
Discusses Waiver of Compliance Re Containment Vacuum Sys Operability,Per 900315 & 16 Telcons
ML18153C1471990-03-14014 March 1990
Discusses Functional Test for High Setpoint for PORVs
ML18153C1571990-03-12012 March 1990
Forwards List of Emergency Operating Procedures in Preparation for 900402-12 Insp.Vol I Is Emergency Operating Procedure Set & Consists of 47 Notebooks.Vol II Contains Fire Contingency Action (App R) Procedures
ML18153C1371990-03-0808 March 1990
Forwards Suppl to 1986 Inservice Insp Summary Rept,Adding Two Missing NIS-2 Forms Containing Info Re Replacement of Bolting Matl on 1-RC-SV-1551C (Flange a) & 1-RC-HCV-1556A
ML18153C1281990-03-0101 March 1990
Submits 1989 Annual Steam Generator Inservice Insp Rept Results.No Steam Generator Tubes Plugged in 1989
ML18153C1261990-03-0101 March 1990
Responds to Generic Ltr 90-01 Re NRC Regulatory Impact Survey.Survey Covers Type of Insp,Audit or Evaluation by NRC Resident,Nrc Regional Ofc,Nrc Teams & INPO
ML18153C1231990-02-22022 February 1990
Responds to NRC 900123 Ltr Re Violations Noted in Insp Repts 50-280/89-32 & 50-281/89-32.Corrective Actions:Use of Lab Hood Attached to F-2 Fan Suction Prohibited & Contaminated & Radioactive Items Removed from Hood
ML18152A4881990-02-0606 February 1990
Responds to NRC 891222 Ltr Re Violations Noted in Insp Repts 50-280/89-34 & 50-281/89-34 on 891029-1125.Corrective Actions:Steps in Operating Procedure 2-OP-1.3 Associated W/ Valve Test Being Evaluated for Inclusion in OP-7.1.1
ML18153C0991990-02-0101 February 1990
Withdraws 891018 Application for Amends to Licenses DPR-32 & DPR-37,increasing Pressurizer Safety Valve Setpoint Tolerance to +/- 3% of Nomical Lift Setpoint.Emergency Tech Spec Change Granted on 891116 Provided Modified Tolerances
ML18153C0951990-01-29029 January 1990
Forwards Response to Generic Ltr 89-13, Svc Water Sys Problems Affecting Safety-Related Equipment. Belief in Appropriateness to Address Generic Ltr 89-13 Concerns within Context of Established Programmatic Improvements Noted
1990-09-20
[Table view] |
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