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| | issue date = 04/07/1981 | | | issue date = 04/07/1981 |
| | title = Responds to NRC 810313 Ltr Re Violation Noted in IE Insp Repts 50-280/81-06 & 50-281/81-06.Corrective Actions: Disputes Violation.Qc Inspector Misunderstood NRC Inspector. QC Inspector re-examined & Found to Have Adequate Knowledge | | | title = Responds to NRC 810313 Ltr Re Violation Noted in IE Insp Repts 50-280/81-06 & 50-281/81-06.Corrective Actions: Disputes Violation.Qc Inspector Misunderstood NRC Inspector. QC Inspector re-examined & Found to Have Adequate Knowledge |
| | author name = SYLVIA B R | | | author name = Sylvia B |
| | 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, 05000281 | | | docket = 05000280, 05000281 |
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| | page count = 3 | | | page count = 3 |
| }} | | }} |
| See also: [[followed by::IR 05000280/1981006]]
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| =Text= | | =Text= |
| {{#Wiki_filter:* * * i ' -.. '\I-, " ,,...... .-VrRGINIA ELECTRIC AND PowE*~'G~~;~~ | | {{#Wiki_filter:i ' -.. ' \ I - , " ,,...... .- |
| RIC:aMOND,VIRGINJ:A. | | VrRGINIA ELECTRIC AND PowE*~'G~~;~~ |
| 23261 : 1 f.P:\ i'.3 P,\\. 3b April 7, 1981 Mr.* James P. O'Reilly, Director Office of Inspection
| | * RIC:aMOND,VIRGINJ:A. 23261 April 7, 1981 |
| and Enforcement | | :1 f.P:\ i'.3 P,\\. 3b Mr.* James P. O'Reilly, Director Serial No. 203 Office of Inspection and Enforcement NO/RMT:ms U. S. Nuclear Regulatory Commission Docket Nos. 50-280 Region II 50-281 101 Marietta Street, Suite 3100 License Nos. DPR-32 Atlanta, Georgia 30303 D:PR-37 |
| U. S. Nuclear Regulatory | | |
| Commission | | ==Dear Mr. O'Reilly:== |
| Region II 101 Marietta Street, Suite 3100 Atlanta, Georgia 30303 Dear Mr. O'Reilly: | | |
| Serial No. 203 NO/RMT:ms
| | We have reviewed your letter of March 13, 1981 in reference to the inspection conducted at Surry Power Station between February 9-12, 1981, and reported in IE Inspection Report Nos. 50-280/81-06 and 50-281/81-06. Our response to the specific infraction is attached. |
| Docket Nos. 50-280 50-281 License Nos. DPR-32 D:PR-37 We have reviewed your letter of March 13, 1981 in reference
| | We have determined that no proprietary information is contained in the reports. Accordingly, the Virginia Electric .and Power Company has no obj ec-tion to these inspection reports being made a matter of public disclosure. |
| to the inspection | | The inf.ormation contained in the attached pages is true and accurate to the |
| conducted | | * best of my knowledge and belief. |
| at Surry Power Station between February 9-12, 1981, and reported in IE Inspection | | Very truly yours, a._ 7~ |
| Report Nos. 50-280/81-06 | | M.n!~er - R. Sylvia Operations and Maintenance Nuclear Attachment City of Richmond Commonwealth of Virginia |
| and 50-281/81-06. | | *7-c L /' |
| Our response to the specific infraction | | Acknowledged before me this~- day of 0;e,.--,~, |
| is attached. | | *Notary Public My Commission expires: --? - .:J_ b 19 Ji.':,-- |
| We have determined | | cc: Mr. Steven A. Varga, Chief Operating Reactors Branch No. 3 Division of Licensing 8105070L/~f |
| that no proprietary | | |
| information | | Attachment Page 1 SURRY POWER STATION RESPONSE TO NOTICE OF VIOLATION APPENDED TO INSPECTION REPORT 50-280/81 50-281/81-06 NRC COMMENT 10 CFR 50, Appendix Criterion IX as implemented by Topical Report VEP-l-3A Section 17.2.9 requires in part that measures shall be established to assure that special processes are controlled and accomplished in accordance with applicable codes, standards, specifications, criteria, and other special requirements aimed at assuring adequate fillet throat for piping fillet welds are depicted in the applicable code (USAS B31.l-1967 edition). |
| is contained | | Contrary to the above, of February 11, i98 l, a de qua te measures had not been established to assure proper measurement in that a QC inspector, whose func-tion included verification of piping fillet weld sizes, could not demonstrate the fillet weld size measurement process. |
| in the reports. Accordingly, the Virginia Electric .and Power Company has no obj tion to these inspection | | This is a Severity Level V Violation (Supplement !I.E.). |
| reports being made a matter of public disclosure. | | VEPCO RESPONSE |
| The inf.ormation | | : 1. ADMISSION OR DENIAL OF THE ALLEGED VIOLATION; The violation is not correct as stated. |
| contained | | : 2. THE REASONS FOR THE VIOLATION IF ADMITTED; Although exception has been taken to the alleged violation, the following description of circumstances is provided. It is felt that there was a misunderstanding rather than an inadequate knowledge of inspection criteria. The QC inspector in question stated that he thought the NRC inspector was asking a general question about the use of the fillet gauge rather than a specific question about the acceptance criteria of B31.l. |
| in the attached pages is true and accurate to the best of my knowledge | | The question that was asked by the NRC inspector was whether or not the fillet gauge had to touch the center of weld. The QC inspector responded by stating it was not necessary in all cases. It should be noted that the piping systems are inspected to B31.1 and the structural welds inspected the AWS Dl .1. AWS Dl. 1 allows 1/16 inch clearance between the center of the weld and fillet gauge. Both QC inspectors stated that they had the impression that they were only demonstrating the use of the fillet gauge and were not actually conducting an inspection to any particular acceptance criteria. The situation is considered to be a misunderstanding between the NRC inspector and the QC inspector. The QC inspector in question was re-examined and was able to adequately demon-strate knowledge of the measurement process. |
| and belief. Attachment | | : 3. CORRECTIVE STEPS WHICH HAVE BEEN TAKEN AND THE RESULTS ACHIEVED; The QC inspector in question was found to have adequate knowledge during re-examination. All welds previously - accepted by this inspector were re-inspected. No discrepancies were found. In addition, SO welds in Containment Ill and 25 welds outside Containment were randomly selected and re-inspected. These were welds previously accepted by other QC inspectors. No discrepancies were found. |
| City of Richmond Commonwealth | | |
| of Virginia L *7-c /' Acknowledged | | Attachment Page 2 VEPCO RESPONSE (Cont'd) |
| before me this~-day of 0;e,.--,~, *Notary Public My Commission | | : 4. CORRECTIVE STEPS WHICH WILL BE TAKEN TO AVOID FURTHER VIOLATIONS; Mockups of typical fillet welds were made and each QC inspector was required to demonstrate his proficiency. The results were satisfactory. |
| expires: --? -.:J_ b cc: Mr. Steven A. Varga, Chief Operating | | Each QC inspector had received additional instruction to ensure that there is n~ misunderstanding in the use of the fillet gauge. |
| Reactors Branch No. 3 Division of Licensing | | S. THE DATE WHEN FULL COMPLIANCE WILL BE ACHIEVED; Full compliance has been achieved. |
| 8105070L/~f | | * ,J , . _ * |
| 19 Ji.':,--Very truly yours, 7~ _ a._ R. Sylvia M.n!~er -Nuclear Operations
| | *}} |
| and Maintenance
| |
| -.*
| |
| * * SURRY POWER STATION RESPONSE TO NOTICE OF VIOLATION
| |
| APPENDED TO INSPECTION | |
| REPORT 50-280/81-06 | |
| -50-281/81-06
| |
| Attachment
| |
| Page 1 NRC COMMENT 10 CFR 50, Appendix Criterion
| |
| IX as implemented | |
| by Topical Report VEP-l-3A Section 17.2.9 requires in part that measures shall be established | |
| to assure that special processes | |
| are controlled | |
| and accomplished | |
| in accordance | |
| with applicable | |
| codes, standards, specifications, criteria, and other special requirements | |
| aimed at assuring adequate fillet throat for piping fillet welds are depicted in the applicable | |
| code (USAS B31.l-1967 | |
| edition). | |
| Contrary to the above, of February 11, i98 l, a de qua te measures had not been established | |
| to assure proper measurement | |
| in that a QC inspector, whose tion included verification | |
| of piping fillet weld sizes, could not demonstrate | |
| the fillet weld size measurement | |
| process. This is a Severity Level V Violation (Supplement | |
| !I.E.). VEPCO RESPONSE 1. 2. 3. ADMISSION | |
| OR DENIAL OF THE ALLEGED VIOLATION; | |
| The violation | |
| is not correct as stated. THE REASONS FOR THE VIOLATION | |
| IF ADMITTED; | |
| Although exception | |
| has been taken to the alleged violation, the following | |
| description | |
| of circumstances | |
| is provided. | |
| It is felt that there was a misunderstanding | |
| rather than an inadequate | |
| knowledge | |
| of inspection | |
| criteria. | |
| The QC inspector | |
| in question stated that he thought the NRC inspector | |
| was asking a general question about the use of the fillet gauge rather than a specific question about the acceptance | |
| criteria of B31.l. The question that was asked by the NRC inspector | |
| was whether or not the fillet gauge had to touch the center of weld. The QC inspector | |
| responded | |
| by stating it was not necessary | |
| in all cases. It should be noted that the piping systems are inspected | |
| to B31.1 and the structural | |
| welds inspected | |
| the AWS Dl .1. AWS Dl. 1 allows 1/16 inch clearance | |
| between the center of the weld and fillet gauge. Both QC inspectors | |
| stated that they had the impression | |
| that they were only demonstrating | |
| the use of the fillet gauge and were not actually conducting | |
| an inspection | |
| to any particular | |
| acceptance | |
| criteria. | |
| The situation | |
| is considered | |
| to be a misunderstanding | |
| between the NRC inspector | |
| and the QC inspector. | |
| The QC inspector | |
| in question was re-examined | |
| and was able to adequately strate knowledge | |
| of the measurement | |
| process. CORRECTIVE
| |
| STEPS WHICH HAVE BEEN TAKEN AND THE RESULTS ACHIEVED; | |
| The QC inspector | |
| in question was found to have adequate knowledge | |
| during re-examination. | |
| All welds previously | |
| -accepted by this inspector | |
| were re-inspected. | |
| No discrepancies | |
| were found. In addition, SO welds in Containment | |
| Ill and 25 welds outside Containment | |
| were randomly selected and re-inspected. | |
| These were welds previously | |
| accepted by other QC inspectors. | |
| No discrepancies | |
| were found. | |
| * VEPCO RESPONSE (Cont'd) Attachment
| |
| Page 2 4. CORRECTIVE
| |
| STEPS WHICH WILL BE TAKEN TO AVOID FURTHER VIOLATIONS; | |
| Mockups of typical fillet welds were made and each QC inspector | |
| was required to demonstrate | |
| his proficiency. | |
| The results were satisfactory. | |
| Each QC inspector | |
| had received additional | |
| instruction | |
| to ensure that there is n~ misunderstanding | |
| in the use of the fillet gauge. S. THE DATE WHEN FULL COMPLIANCE | |
| WILL BE ACHIEVED; | |
| Full compliance | |
| has been achieved. | |
| * ,J ,._ * -:': | |
| }} | |
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ML18152B6671999-09-17017 September 1999 Forwards Two NRC Forms 536,containing Info on Proposed Site Specific Operator Licensing Exam Schedules & Estimated Number of Applicants Planning to Take Exams And/Or Gfes,In Response to NRC Administrative Ltr 99-03 ML18152B3341999-09-16016 September 1999 Requests Relief from Specific Requirements of Subsection IWE of 1992 Edition with 1992 Addenda of ASME Section XI Re Containment Liner Examination Requirements,For North Anna & Surry Power Stations ML18152B4521999-09-14014 September 1999 Forwards Comments on Review of Preliminary Accident Sequence Precursor Analysis of Operational Event That Occurred at Plant,On 980508,as Reported in LER 98-009 ML18152B4501999-09-0808 September 1999 Submits in Triplicate,Application for Renewal of License for Rd Scherer,Iaw 10CFR55.57.Requests That Certification of Medical Exam by Facility Licensee,Nrc Form 396,be Withheld from Public Disclosure,Per 10CFR2.790(a)(6) ML18152B4471999-09-0101 September 1999 Requests That NRC Remove Listed Labels from Distribution ML18152B3711999-08-27027 August 1999 Forwards LER 99-005-00,per Plant TS Table 3.7.6.Rept Has Been Reviewed by Station Nuclear Safety & Operating Committee.Commitment Made by Util,Listed ML18152B3851999-08-23023 August 1999 Forwards Revised TS Basis Pages for TS 3.1.B,deleting Reactor Vessel Toughness Data Duplicated in Ufsar.Ref to Applicable UFSAR Section Included in TS Basis ML18152B3651999-08-20020 August 1999 Requests Removal of License Condition from Sh Wightman Operator License SOP-21538.Updated NRC Form 396 Is Encl.Form NRC 396 Withheld,Per 10CFR2.790(a)(6) ML18152B3681999-08-20020 August 1999 Submits 30-day Rept Re Two Instances in Which Conditions of Approval in Coc Were Not Observed in Making Shipment.Two Type B Shipments Using Model CNS 8-120B Package Were Made After Expiration of QA Program Approval Between 990531-0628 ML18152B3661999-08-20020 August 1999 Provides Medical Status Rept for E Washington,As Required by License Conditions.Summary of E Washington Current Physical Exam & Pertinent Lab Data Attached.Encl Withheld,Per 10CFR2.790(a)(6) ML18152B3801999-08-18018 August 1999 Forwards Technical Rept NE-1206,Rev 0, Surry Unit 2,Cycle 16 Startup Physics Tests Rept, Summarizing Results of Physics Testing Program Performed After Initial Criticality on 990525 ML18152B3781999-08-13013 August 1999 Forwards ISI Summary Rept for Surry Power Station,Unit 2 for 1999 Refueling Outage.Rept Provides Summary of Examination Performed During Outage for Third ISI Interval.No New Commitments Were Made ML18152B3751999-08-13013 August 1999 Forwards LER 99-004-00,IAW 10CFR50.73.Commitment Made by Util,Listed ML18152B4081999-08-0606 August 1999 Forwards Response to NRC 990520 & 0525 RAIs Re North Anna & Surry Responses to GL 95-07, Pressure Locking & Thermal Binding of SR Power-Operated Gate Valves. ML20210Q7661999-08-0606 August 1999 Requests Exception to 10CFR50.4 Requirement to Provide Total of Twelve Paper Copies When Submitting Surry & North Anna UFSAR Updates.Seek Approval to Submit Only Signed Original & One CD-ROM Version,Per Conversation with J Skoczlas ML18152B4091999-08-0505 August 1999 Forwards Vepc semi-annual fitness-for-duty Program Performance Data Rept for 990101-990630,IAW 10CFR26.71(d) ML18152B4001999-07-29029 July 1999 Requests Relief from Certain Impractical Requirements of ASME Section XI Code Associated with Partial Exams Conducted During 1998 Surry Unit 1 Refueling Outage.Relief Request SR-020 Encl ML18152B3981999-07-28028 July 1999 Forwards 60-day Response to GL 99-02, Lab Testing of Nuclear-Grade Activated Charcoal. Commitments Contained in Ltr,Listed ML18152B3971999-07-26026 July 1999 Provides Estimates of Licensing Actions Expected to Be Submitted in Fys 2000 & 2001,in Response to NRC AL 99-02 ML18151A6281999-07-23023 July 1999 Forwards Revised Epips,Including Rev 19 to EPIP-4.02,rev 14 to EPIP-4.16,rev 8 to EPIP-4.21 & Rev 7 to EPIP-4.30.EP & EPIPs Continue to Meet Stds of 10CFR50.47(b) ML18152B3991999-07-23023 July 1999 Requests That License for Jz Laplante Be Canceled as License Is No Longer Required ML18152B3961999-07-23023 July 1999 Forwards Preliminary,Uncertified License Application & Medical Certification for License to Operate Surry Power Station Units 1 & 2 for Ds Cobb.Encl Withheld,Per 10CFR2.790 (a)(6) ML18152B3931999-07-16016 July 1999 Forwards Updated NRC Form 396 & Ltr,Which Documents Medical Status of Mb Gross,License SOP-20476-2.Encl Withheld from Public Disclosure,Per 10CFR2.790(a)(6) ML18152B4401999-07-0101 July 1999 Informs NRC That on 990511,Dominion Resources,Inc,Executed Amended & Restated Agreement & Plan of Merger with Consolidated Natural Gas Co ML18152B4371999-06-24024 June 1999 Forwards Response to NRC Request for Clarification of Relief Requests Submitted on 990212,requesting Relief from Performing Hydrostatic Testing for Certain Small Diameter Class 1,RCS Pressure Boundary Connections ML18152B4361999-06-22022 June 1999 Forwards Response to RAI Re Surry & North Anna Power Stations,Units 1 & 2,per GL 96-06 ML18152B4301999-06-0303 June 1999 Informs of Util Intention to Revise Schedule for Submittal of License Renewal Applications for Surry & North Anna Power Stations to March 2002 ML18152B4261999-05-28028 May 1999 Provides Formal Notification of Effect of Recent Organizational Restructuring on OLs of North Anna & Surry Power Stations,Per NRC 990513 Telcon Request ML18152B4221999-05-27027 May 1999 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] |
Text
i ' -.. ' \ I - , " ,,...... .-
VrRGINIA ELECTRIC AND PowE*~'G~~;~~
- RIC:aMOND,VIRGINJ:A. 23261 April 7, 1981
- 1 f.P:\ i'.3 P,\\. 3b Mr.* James P. O'Reilly, Director Serial No. 203 Office of Inspection and Enforcement NO/RMT:ms U. S. Nuclear Regulatory Commission Docket Nos. 50-280 Region II 50-281 101 Marietta Street, Suite 3100 License Nos. DPR-32 Atlanta, Georgia 30303 D:PR-37
Dear Mr. O'Reilly:
We have reviewed your letter of March 13, 1981 in reference to the inspection conducted at Surry Power Station between February 9-12, 1981, and reported in IE Inspection Report Nos. 50-280/81-06 and 50-281/81-06. Our response to the specific infraction is attached.
We have determined that no proprietary information is contained in the reports. Accordingly, the Virginia Electric .and Power Company has no obj ec-tion to these inspection reports being made a matter of public disclosure.
The inf.ormation contained in the attached pages is true and accurate to the
- best of my knowledge and belief.
Very truly yours, a._ 7~
M.n!~er - R. Sylvia Operations and Maintenance Nuclear Attachment City of Richmond Commonwealth of Virginia
Acknowledged before me this~- day of 0;e,.--,~,
- Notary Public My Commission expires: --? - .:J_ b 19 Ji.':,--
cc: Mr. Steven A. Varga, Chief Operating Reactors Branch No. 3 Division of Licensing 8105070L/~f
Attachment Page 1 SURRY POWER STATION RESPONSE TO NOTICE OF VIOLATION APPENDED TO INSPECTION REPORT 50-280/81 50-281/81-06 NRC COMMENT 10 CFR 50, Appendix Criterion IX as implemented by Topical Report VEP-l-3A Section 17.2.9 requires in part that measures shall be established to assure that special processes are controlled and accomplished in accordance with applicable codes, standards, specifications, criteria, and other special requirements aimed at assuring adequate fillet throat for piping fillet welds are depicted in the applicable code (USAS B31.l-1967 edition).
Contrary to the above, of February 11, i98 l, a de qua te measures had not been established to assure proper measurement in that a QC inspector, whose func-tion included verification of piping fillet weld sizes, could not demonstrate the fillet weld size measurement process.
This is a Severity Level V Violation (Supplement !I.E.).
VEPCO RESPONSE
- 1. ADMISSION OR DENIAL OF THE ALLEGED VIOLATION; The violation is not correct as stated.
- 2. THE REASONS FOR THE VIOLATION IF ADMITTED; Although exception has been taken to the alleged violation, the following description of circumstances is provided. It is felt that there was a misunderstanding rather than an inadequate knowledge of inspection criteria. The QC inspector in question stated that he thought the NRC inspector was asking a general question about the use of the fillet gauge rather than a specific question about the acceptance criteria of B31.l.
The question that was asked by the NRC inspector was whether or not the fillet gauge had to touch the center of weld. The QC inspector responded by stating it was not necessary in all cases. It should be noted that the piping systems are inspected to B31.1 and the structural welds inspected the AWS Dl .1. AWS Dl. 1 allows 1/16 inch clearance between the center of the weld and fillet gauge. Both QC inspectors stated that they had the impression that they were only demonstrating the use of the fillet gauge and were not actually conducting an inspection to any particular acceptance criteria. The situation is considered to be a misunderstanding between the NRC inspector and the QC inspector. The QC inspector in question was re-examined and was able to adequately demon-strate knowledge of the measurement process.
- 3. CORRECTIVE STEPS WHICH HAVE BEEN TAKEN AND THE RESULTS ACHIEVED; The QC inspector in question was found to have adequate knowledge during re-examination. All welds previously - accepted by this inspector were re-inspected. No discrepancies were found. In addition, SO welds in Containment Ill and 25 welds outside Containment were randomly selected and re-inspected. These were welds previously accepted by other QC inspectors. No discrepancies were found.
Attachment Page 2 VEPCO RESPONSE (Cont'd)
- 4. CORRECTIVE STEPS WHICH WILL BE TAKEN TO AVOID FURTHER VIOLATIONS; Mockups of typical fillet welds were made and each QC inspector was required to demonstrate his proficiency. The results were satisfactory.
Each QC inspector had received additional instruction to ensure that there is n~ misunderstanding in the use of the fillet gauge.
S. THE DATE WHEN FULL COMPLIANCE WILL BE ACHIEVED; Full compliance has been achieved.