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Category:CORRESPONDENCE-LETTERS
MONTHYEARML20217K4391999-10-18018 October 1999 Provides Response to RAI to Support USI A-46 Program Submittal for North Anna Power Station,Units 1 & 2.Rev 10 to BNL Rept 52361,encl ML20217H3301999-10-14014 October 1999 Forwards Rev 0 to COLR for North Anna 2 Cycle 14 Pattern Su. No New Commitments Intended by Ltr ML18152B3541999-10-12012 October 1999 Requests Use of Code Case N-532 & N-619,per Provisions of 10CFR50.55a(a)(3).Detailed Info Supporting Request,Encl. Attachment 2 Includes Technical White Paper That Provides Further Technical Info ML20216K1681999-10-0101 October 1999 Forwards Vols I-VIII of Rev 35 to UFSAR for Naps.Rev Also Includes Update to Chapter 17 of Ufsar,Which Contains Operational QA Program.Changes to Program Description Do Not Reduce Commitments Contained Therein ML20212J9101999-10-0101 October 1999 Forwards SE Accepting Licensee 990916 & 27 Relief Requests IWE-3 for Plant.Se Addresses Only IWE-3 Due to Util Urgent Need for Relief.Requests IWE-7 & IWE-8 Will Be Addressed at Later Date ML18152B3391999-09-27027 September 1999 Forwards Revised Relief Request IWE-3,which Now Includes Addl Visual Exam Requirement After post-repair or Mod Pressure Testing Is Completed,Per Telcon with NRC ML20212G5091999-09-22022 September 1999 Forwards in Triplicate,Applications for Renewal of Licenses for Listed Individuals.Encls Withheld,Per 10CFR2.790(a)(6) 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 ML18152B3331999-09-17017 September 1999 Forwards Revised 180-day Response to NRC GL 96-05, Periodic Verification of Design-Basis Capability of Safety-Related Motor-Operated Valves. 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 ML20211N2531999-09-0808 September 1999 Responds to Request to Exceed 60,000 Mwd/Mtu Lead Rod Burnup in Small Number of Fuel Rods in North Anna Unit 2.Informs That NRC Offers No Objection to Requested Use of Rods in Reconstituted Fuel Assembly.Se Supporting Request Encl ML18152B4471999-09-0101 September 1999 Requests That NRC Remove Listed Labels from Distribution ML20211L9151999-09-0101 September 1999 Forwards Response to NRC Request for Comments Re Closure of Review of Response to GL 92-01,Rev 1,Suppl 1, Reactor Vessel Structural Integrity ML20211J2211999-08-31031 August 1999 Approves Request to Remove Augmented ISI (Aii) Program for RCS Bypass Lines from North Anna Licensing Basis.Se Re Request to Apply LBB to Eliminate Augmented Insp Program on RCS Bypass Lines Encl ML20211H4131999-08-27027 August 1999 Informs That Util Revised Encl Bases for TS 2.2.1, Reactor Trip Sys Instrumentation Setpoints, Discussing Steam Flow/ Feed Flow Mismatch Portion of Steam Flow/Feed Flow Mismatch & Low SG Water Level Reactor Trip Setpoint ML20138B3241999-08-23023 August 1999 Forwards Draft Response to Question 1 Re NAPS USI A-46 ML20211D9041999-08-20020 August 1999 Forwards Revised Pages to Third Ten Year ISI Program & Relief Requests, Replacing Pages in 990408 Submittal ML20211B3871999-08-17017 August 1999 Requests Permission to Routinely Discharge from SW Reservior to Waste Heat Treatment Facility Under Existing Vpdes Permit Through Outfalls 108 & 103.Discharges Are Scheduled to Commence on 990907,due to High Priority Placed on Project ML20210T0671999-08-13013 August 1999 Informs of Completion of Review of Proposed Revs of Schedule for Withdrawal of Rv Surveillance Capsules Submitted by VEPCO on 981217.Approves Proposed Revs.Forwards Safety Evaluation ML20210Q9841999-08-12012 August 1999 Forwards Rev 1 to Vepc COLR for North Anna Unit 2,Cycle 13 Pattern Ud, Per TS 6.9.1.7.d.COLR Was Revised to Include Temp Coastdown Operation at End of Cycle 13 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) ML20210N2921999-08-0505 August 1999 Discusses Which Submitted Proposed TSs Bases Change for Containment Leakage. Licensee Changes to Bases May Be Subj to Future Insps or Audits ML20210J8861999-08-0202 August 1999 Provides Clarification to Commitment Made in Identifying Extent by Which Existing Plant Design Complied with RG 1.97,specifically Re Variable, Radiation Exposure Rate ML20210F6121999-07-28028 July 1999 Forwards Supplemental Info on Proposed Irradiation of Fuel Rods Beyond Current Lead Rod Burnup Limit,Documenting Info Provided During 990624 Meeting & Suppl Original Submittal 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 ML20209E7621999-07-0909 July 1999 Provides Addl Info to Justify Use of Less than One Gpm Detectable Leakage Rate to Establish Required Margin for Crack Stability in LBB Analysis,Per 980623 Application on Reactor Coolant Loop Bypass Lines 05000338/LER-1999-005, Forwards LER 99-005-00,IAW 10CFR50.73.Commitment Made by Util Encl1999-07-0808 July 1999 Forwards LER 99-005-00,IAW 10CFR50.73.Commitment Made by Util Encl ML20209E3711999-07-0202 July 1999 Forwards Insp Repts 50-338/99-03 & 50-339/99-03 on 990425-0605.Violations Being Treated as Noncited Violations 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 ML20196G2581999-06-23023 June 1999 Discusses Closure of GL 92-01,rev 1,suppl 1,reactor Vessel Structural Integrity ML20212J2951999-06-22022 June 1999 Forwards Corrected Markup & Typed Version of Affected Pages. Requests That Attached Pages for Those Previously Provided in 990506 Submittal Be Replaced & Incorporated Into NRC Review of Proposed TS ML18152B4361999-06-22022 June 1999 Forwards Response to RAI Re Surry & North Anna Power Stations,Units 1 & 2,per GL 96-06 ML20196F1151999-06-22022 June 1999 Forwards Relief Requests NDE-047 & NDE-048 for North Anna Power Station,Unit 1 Re ASME Section XI ISI Program ML20196G2211999-06-21021 June 1999 Forwards Licensee Sampling & Testing Obligations Re Vpdes Permit VA0052451 Reissuance Application.Details of Requests for Sampling & Testing Waivers,Included ML20195J7011999-06-15015 June 1999 Forwards Revised EPIP 2.01 Which Corrects Typo That Was Found in Step 10 of Procedure.Rev Does Not Implement Actions That Decrease Effectiveness of EP ML20195J1391999-06-11011 June 1999 Submits Addl Info as Addendum to Original Application Which Proposed Use of Three Chemicals in Bearing Cooling Tower at North Anna Power Station,Per Reissuance of Vpdes Permit 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 ML20195C6601999-06-0101 June 1999 Forwards Response to NRC 990216 RAI Re Summary Rept of USI A-46 Program ML20207C9851999-05-28028 May 1999 Requests Regrading of Rt Robinson 990408 Written Exam,Based on Listed Reasons.Answer C for Question 18 Is Requested to Be Reconsidered as Correct or Question Be Deleted 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 ML20206U7441999-05-20020 May 1999 Informs That NRC Unable to Conclude That NAPS Has Met Intent of Supplement 4 to GL 88-20.RAI Re Fire Area of IPEEE Encl. Response Requested within 90 Days of Submittal Date ML20207A8541999-05-20020 May 1999 Forwards RAI Re Licensee Listed Responses to GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves. Response Requested within 90 Days of Submittal Date ML20195B5381999-05-14014 May 1999 Forwards Rev 8,Change 2 to North Anna Units 1 & 2 IST Programs for Pumps & Valves. Summaries of Program Changes Provided for Each Unit IST Program.Relief Requests Have Been Removed from IST Programs 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 ML20206L4661999-05-10010 May 1999 Forwards SE Accepting Request to Delay Submitting Plant, Unit 1 Class Piping ISI Program for Third Insp Interval Until 010430,to Permit Development of Risk Informed ISI Program for Class 1 Piping 1999-09-08
[Table view] Category:ENGINEERING/CONSTRUCTION/CONSULTING FIRM TO NRC
MONTHYEARML20245D9851989-06-22022 June 1989 Forwards 21 Insp Rept Executive Summaries,Per NRC Contract NRC-03-87-029,Task Order 037.Individual Quality Evaluations of Insp Repts Also Prepared ML20235A1251987-12-16016 December 1987 Forwards Info Re Resource Technical Svcs,Inc,Including Summary of NRC Contract Work,Nrc Form 26 for Three Existing Contracts,Audit Info,Work History & Lists of Expertise Available for Special Insps & of Current Resource Svcs ML20237G9081987-07-21021 July 1987 FOIA Request for Info Re Us Navy Allowing 400 Ft of Flawed Piping to Remain in Steam Sys of Eight Nuclear Submarines Built at General Dynamics Electric Boat Div & Shutdown at Plant Due to Ruptured Stainless Steel Tube ML20238E3011987-06-29029 June 1987 FOIA Request for All Documents Described in App,Including Listed LERs & Revs for Plants,W/Original Attachments & Encls ML18150A1861987-05-0101 May 1987 Forwards EGG-NTA-7612, Conformance to Generic Ltr 83-28, Item 2.2.2 - Vendor Interface Programs for All Other Safety- Related Components,North Anna Units 1 & 2 & Surry Units 1 & 2, Final Informal Rept ML18150A1171987-04-14014 April 1987 Forwards Final rept,EGG-NTA-7625, Conformance to Item 2.1 (Part 2) Generic Ltr 83-28,Reactor Trip Sys Vendor Interface,North Anna 1 & 2 & Surry 1 & 2. ML20199E7311986-02-0606 February 1986 FOIA Request for Totals of NRC Fees Charged for 1985 Under 10CFR170 for Listed Facilities ML20132F5751985-08-13013 August 1985 FOIA Request for Power Plant Exam Results Summary Sheets for Listed Plants ML20134L5011985-06-19019 June 1985 FOIA Request for Operator Exam Results Summary Sheets for Listed Nuclear Plants ML20133C5961985-05-23023 May 1985 FOIA Request for Section 55.25 Exam Summary Sheets Prepared by Operator Licensing Branch for Operator Candidates & Monthly & Quarterly Repts on Senior Operator Performance on Exams ML20129A9861985-01-31031 January 1985 FOIA Request for Encls to Gulf State Utils 840820 Deficiency Rept Re ITE-Gould Type 2150 Overload Relays & Encls to NRC to VEPCO Re Request for Addl Info on SPDS to Be Placed in PDR ML20126E1901984-12-28028 December 1984 FOIA Request for Info Re Initial Operator Written Exam Results on Number of post-TMI-2 Plants.Info Provided in Did Pertain to Initial Exam Results.Table Listing Dates of Initial Licensing Encl ML20125B1191984-12-14014 December 1984 FOIA Request for 840101 Detailed 5-yr Summary Rept & Rev ,referenced in Util to HR Denton ML20107K6231984-11-0101 November 1984 FOIA Request for Four Categories of Documents Re Results of Written Operator Exams at Listed Facilities,Including Dates of Exams & Number of Candidates Taking Exams ML20083E8281983-09-21021 September 1983 FOIA Request for Listed LERs ML19305D2281980-04-0808 April 1980 Notifies That Review of Util Fire Protection Safety Evaluation Adequately Reflects Consultant Concerns & Recommendations.Concurs W/Nrc That Implementation of Mods Will Be Acceptable ML19305C7111980-03-27027 March 1980 Draft Human Engineering Evaluation Re Control Room.Control Room Exhibited Design Features That Are Inconsistent W/Human Engineering Stds & Practices.Engineering Problems Identified in Emergency Procedures ML19290E6251980-03-10010 March 1980 Submits Info Re Essex Corp Audit of VEPCO Human Engineering Evaluation of Control Room.More Comprehensive Evaluation Must Be Performed & Assignment of Backfit Scheduling Often Does Not Agree W/Safety Interests 1989-06-22
[Table view] Category:INCOMING CORRESPONDENCE
MONTHYEARML20217K4391999-10-18018 October 1999 Provides Response to RAI to Support USI A-46 Program Submittal for North Anna Power Station,Units 1 & 2.Rev 10 to BNL Rept 52361,encl ML20217H3301999-10-14014 October 1999 Forwards Rev 0 to COLR for North Anna 2 Cycle 14 Pattern Su. No New Commitments Intended by Ltr ML18152B3541999-10-12012 October 1999 Requests Use of Code Case N-532 & N-619,per Provisions of 10CFR50.55a(a)(3).Detailed Info Supporting Request,Encl. Attachment 2 Includes Technical White Paper That Provides Further Technical Info ML20216K1681999-10-0101 October 1999 Forwards Vols I-VIII of Rev 35 to UFSAR for Naps.Rev Also Includes Update to Chapter 17 of Ufsar,Which Contains Operational QA Program.Changes to Program Description Do Not Reduce Commitments Contained Therein ML18152B3391999-09-27027 September 1999 Forwards Revised Relief Request IWE-3,which Now Includes Addl Visual Exam Requirement After post-repair or Mod Pressure Testing Is Completed,Per Telcon with NRC ML20212G5091999-09-22022 September 1999 Forwards in Triplicate,Applications for Renewal of Licenses for Listed Individuals.Encls Withheld,Per 10CFR2.790(a)(6) ML18152B3331999-09-17017 September 1999 Forwards Revised 180-day Response to NRC GL 96-05, Periodic Verification of Design-Basis Capability of Safety-Related Motor-Operated Valves. 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 ML18152B4471999-09-0101 September 1999 Requests That NRC Remove Listed Labels from Distribution ML20211L9151999-09-0101 September 1999 Forwards Response to NRC Request for Comments Re Closure of Review of Response to GL 92-01,Rev 1,Suppl 1, Reactor Vessel Structural Integrity ML20211H4131999-08-27027 August 1999 Informs That Util Revised Encl Bases for TS 2.2.1, Reactor Trip Sys Instrumentation Setpoints, Discussing Steam Flow/ Feed Flow Mismatch Portion of Steam Flow/Feed Flow Mismatch & Low SG Water Level Reactor Trip Setpoint ML20138B3241999-08-23023 August 1999 Forwards Draft Response to Question 1 Re NAPS USI A-46 ML20211D9041999-08-20020 August 1999 Forwards Revised Pages to Third Ten Year ISI Program & Relief Requests, Replacing Pages in 990408 Submittal ML20210Q9841999-08-12012 August 1999 Forwards Rev 1 to Vepc COLR for North Anna Unit 2,Cycle 13 Pattern Ud, Per TS 6.9.1.7.d.COLR Was Revised to Include Temp Coastdown Operation at End of Cycle 13 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 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. ML18152B4091999-08-0505 August 1999 Forwards Vepc semi-annual fitness-for-duty Program Performance Data Rept for 990101-990630,IAW 10CFR26.71(d) ML20210J8861999-08-0202 August 1999 Provides Clarification to Commitment Made in Identifying Extent by Which Existing Plant Design Complied with RG 1.97,specifically Re Variable, Radiation Exposure Rate ML20210F6121999-07-28028 July 1999 Forwards Supplemental Info on Proposed Irradiation of Fuel Rods Beyond Current Lead Rod Burnup Limit,Documenting Info Provided During 990624 Meeting & Suppl Original Submittal 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 ML20209E7621999-07-0909 July 1999 Provides Addl Info to Justify Use of Less than One Gpm Detectable Leakage Rate to Establish Required Margin for Crack Stability in LBB Analysis,Per 980623 Application on Reactor Coolant Loop Bypass Lines 05000338/LER-1999-005, Forwards LER 99-005-00,IAW 10CFR50.73.Commitment Made by Util Encl1999-07-0808 July 1999 Forwards LER 99-005-00,IAW 10CFR50.73.Commitment Made by Util Encl 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 ML20196F1151999-06-22022 June 1999 Forwards Relief Requests NDE-047 & NDE-048 for North Anna Power Station,Unit 1 Re ASME Section XI ISI Program ML20212J2951999-06-22022 June 1999 Forwards Corrected Markup & Typed Version of Affected Pages. Requests That Attached Pages for Those Previously Provided in 990506 Submittal Be Replaced & Incorporated Into NRC Review of Proposed TS ML20195J7011999-06-15015 June 1999 Forwards Revised EPIP 2.01 Which Corrects Typo That Was Found in Step 10 of Procedure.Rev Does Not Implement Actions That Decrease Effectiveness of EP 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 ML20195C6601999-06-0101 June 1999 Forwards Response to NRC 990216 RAI Re Summary Rept of USI A-46 Program 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 ML20207C9851999-05-28028 May 1999 Requests Regrading of Rt Robinson 990408 Written Exam,Based on Listed Reasons.Answer C for Question 18 Is Requested to Be Reconsidered as Correct or Question Be Deleted 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 ML20195B5381999-05-14014 May 1999 Forwards Rev 8,Change 2 to North Anna Units 1 & 2 IST Programs for Pumps & Valves. Summaries of Program Changes Provided for Each Unit IST Program.Relief Requests Have Been Removed from IST Programs 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 ML20206H0221999-05-0303 May 1999 Informs That Licensee Changes Bases for TS 3/4.6.1.2, Containment Leakage. Changes Allow Use of Other NRC Staff Approved/Endorsed Integrated Leak Test Methodologies to Perform Containment Leakage Rate Testing.Ts Bases Page,Encl ML20206G9481999-05-0303 May 1999 Informs NRC That Insp of 58 Accessible safety-related Pipe Supports Completed in Response to NOV from Insp Rept 50-338/98-05 & 50-339/98-05.Commitments Made Include Plans to Perform Assessment of Welding & Welding Insp ML20205T1181999-04-16016 April 1999 Requests NRC Approval Prior to Proposed Irradiation of Fuel Rods Beyond Current Lead Rod Burnup Limit.Nrc Concurrence with Irradiation Program Requested by End of June 1999 ML20205P1891999-04-0808 April 1999 Forwards ISI Program for Third ten-yr ISI Interval for North Anna Unit 1 for Class 1,2 & 3 Components & Component Support.Third ten-yr Insp Interval for North Anna Unit 1 Begins on 990501.Page 2-26 of Encl Not Included ML20205K3631999-04-0505 April 1999 Requests That Relief Request IWE-3 Be Removed from 980804 Relief Requests Submitted to Nrc.Subject Relief Request Was Inadvertently Retained in Attachment 1 for Unit 1 ML20205K2191999-04-0101 April 1999 Forwards Response to NRC 990106 RAI Re Util Summary Rept on USI A-46 Program,Submitted 970527.Calculations & Corrected Table 11.1-1,encl 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 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 ML20205E2701999-02-25025 February 1999 Forwards Rept on Status of Decommissioning Funding for North Anna Power Station,Units 1 & 2.Trust Agreement Between Old Dominion & Bankers Trust Co,Effective 990301,attached ML20207A8741999-02-25025 February 1999 Draft Response to NRC Telcon Re Licensee Request for Approval of LBB Evaluation in Support of Elimination of Augmented Insp Program on RCS Loop Bypass Lines.Response Justifies Use of Less than One Gpm Detectable Leakage Rate ML18152B5401999-02-11011 February 1999 Requests Relief from Specific Requirements of Subsection Iwl of 1992 Edition with 1992 Addenda of ASME Section Xi,Per 10CFR50.55a(a)(3) ML20203C8181999-02-0505 February 1999 Forwards Response to NRC 981217 Telcon RAI Re risk-basis of Nitrogen Accumulator Action Statement to Complete NRC Review of 951025 Proposed TS Changes 1999-09-27
[Table view] |
Text
'9 ..
7, 3 r ?=, :
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March 27,19S0
.To: Leo Beltracchi From: Ken Mallory
Subject:
Findings of the Evaluation on North Ar.na - Unit 2 From March 17 to March 21, 1980, the Essex Corporation performed a human
. engineering evaluation of the Control Room at VEPCO's North Anna - Unit 2 Nuclear Power Plant. The procedures and guidelines used by Essex were the latest generation of those to be included in the guidebook for the human engineering review of Nuclear Power Plant Control Room design and operability.
Essex objectives for this review:
- 1. To identify features in the control room design that were contrary to human engineering principles and practices and would contribute to operator error.
- 2. To evaluate, based on human engineering criteria, the general operability of North Anna-2 during emergency operations.
1.0
SUMMARY
CONCLUSIONS 1.1 The North Anna - Unit 2 control room exhibited a number of design features (controls, displays, panel markings, etc.) that are inconsistent with human engineering standards and practices. These features will induce operator error.
1.2 A number of human engineering prob! cms were identified in the content and format of North Anna-2 cmergency procedures. Information accessibility, readability, and usability will be compromised by these problems.
1.3 A number of CR administrative and maintenance problems were identified.
i 2.0 OBSERVATIONS Each of the observations described below is given a Subjective Risk Assessment Weight based on the likelihood that a particular aspect of control room design will lead to ;
an operator error in a critical activity. The likelihood is based on the opinion (s) of the .
Essex human engineer (s) reviewing the control room. l l
Category 1 - High Risk of Operator Error in Critical Activities I Category 2 - Moderate Risk of Operator Error in Critical Activities j l Category 3 - Risk of Operator Error 5 h ' ()
I Category X - Additional Evaluation Required. ,
ESS EX COR L'O RATION 333 North Fairfax Sireet, Alexandria. Virginia 22314. (703) 548-1500 800331g. M
- 1. Control-Display and General Control Room Organization The control room in general appears to lack any real organization. The various controls and displays have poor functional grouping. The colored tape retrofitted on the panels is a good indication of this. The tape, especially on the vertical meters, indicates a lack of symmetrical, orderly grouping. The controls on the benchboard frequently have systems embedded within systems. This lack of a logical grouping requires that the operator use visual scan patterns that are unnatural, possibly causing substitution or temporal error.
In addition, the benchboard, which should contain only primt.ry or priority systems, contains nonpriority systems. Examples of these systems are the flash evaporator and the reheater steam feed purge controls and displays. These controls and displays could be relocated without compromising panel operability. The space taken up by these systems could be given over to more important controls and displays, thereby enhancing visual scan of important displays and perhaps lowering the manpower requirements during emergency procedures. This would reduce dif ficulty in locating and operating critical controls and displays. (Category 1)
- 2. Vertical Meters Vertical meters, particularly those located on the vertical panel behind the benchboard, are difficult to locate and read from the primary benchboard panel.
Problems include:
e In strings, difficult to discrirninate/ locate e Not physically associated with related controls e Vertical integral labels are difficult to read from controls / normal operating position e Labeling font size on horizontal labels well below human engineering recommendeo practices e Inconsistency in numerical coding on labels for controls and asso-ciated meters impedes quick location and ldentification e Limit / range markings are needed to enable accurate interpretation of displayed information e Lack of pattern in some display layouts lends to confusion in location of meters.
_The problems with location and readability of vertical meters could result in misreadmg critical displayed information. (Category 1)
- 3. Annunciators There is no prioritization of the annunciators other than first out. The primary emergency annunciators are intermingled with the nonpriority annunciators and are characterized by the same size and color. The operator's having to visually search for the priority annunciators could lead to temporal errors. A good example of this is the green permissive board. The pre-alarm conditions are intermingled with the status and test annunciators.
Furthermore, when an alarm condition clears, the operator receives no annunciator alarm audible indication. The only indications are the offset of the annunciator light and a printout on the computer printer. As the operator should always be immediately aware of any changes in plunt system status, positive indication of alarm conditions cleared should be available. (Category 1)
- 4. Noise Level in Control Room Ambient noise ranges around 6SdB(A) in the main operating area and as high as 73dB(A) at the meterological panel. With the CR door open, noise level increases to approximately 78dB(A). The Unit 2 annunciator alarm horn registers about 83dB(A),
the computer bell,86+, and the P.A.,88+ at times.
According to MIL-STD-1472B, " areas requiring frequent telephone use or frequent direct communication at distances up to five feet shall not exceed 65dB(A)."
Emergency procedures walkthroughs demonstrated a need for direct communications among four operators stationed at different panels during emergency operations.
For example, the response to safety injection requires one operator to operate Charging Pump controls on the primary benchboard panel while communicating with another operator monitoring flow meters located on the Engineered Safeguards panel. Because of the noise level and distance between panels, communications will
. require shouting and essential messages could easily go unheard or be misinter-preted. (Category 1)
- 5. Inability to Monitor Safety Injection (SI) Status at System Level There is no integrated indication of SI status prior to its initiation. 51 status must be determined by checking various display locations, which requires either leaving the primary panel or communicating with another operator stationed at the vertical
panel. Critical time could be lost in initiating 51. Additionally, there is no integrated indication that - 51 is functioning appropriately following automatic initiation, again requiring checking displays at stations away from the primary benchboard. As a safety-related system, status monitoring information should be readily available to the operator. (Category 1)
- 6. , Core Cooling Monitors (T sat)
The Core Cooling Monitors on the primary vertical panel, which monitor pressure of the core cooling system, read out on horizontal scales that have significant parallax problems. This is compounded by the scale increments which are not readable from the benchboard. During an event, the operator may misinterpret the pressure level and reach saturation before he suspects it, thereby degrading the existing event significantly by losing positive control. The problem is further compounded by the lack of an indication of failure in one of the redundant systems. If each indicator is
- reading at a different poi,st on the scale, the operator has no way of recognizing which indicator is correct. For a precise reading, the operator must go back to the area on the right wing of the CR, climb a ladder, and read the T sat monitors. This takes him away from the primary area of the CR, possibly leading to temporal, interpretation, and reading errors. (Category 1)
- 7. Strip Charts Strip chart recorders have been used frequently in the control room. These recorders are characterized by the following problems: ,
e The third scale on the three pen recorders obscures pen position and trend lines e The chart recorders lack system labeling, making quick identification difficult. The pen labeling is often too long for easy identification and the pen color designation is faded or nonexistent (for example, -
- T-AVE, T-REF) e Some strip charts are mounted so low as to make easy reading and interpretation impossible e The scaling increments do not always agree with the increments on the paper.
e The strip chart recorders that are computer-controlled fail in the last
. position if the computer goes down. Once the computer comes on-line again, the strip charts must be reenergized
e Multi-channel impact recorders print indiscriminable numbers which overlap; trends are often impossible to identif y.
All of these problems contribute to human error. The 'oerator can make substitution errors, reading errors, interpretation errors, and temporo: arrors. All of these can lead to a degradation or even precipitation of an event. (Category 2)
- 8. Lamp Test The vertical panel, the back panel, and most of the benchboard have numerous transilluminated displays. There is no mechanism, procedural or electrical / mechanical, to test the lamps for burned out bulbs. If he suspects a bulb is out, the operator must replace it with a known good bulb. During normal operational procedures and emergency procedures, the operator may be relying on false information (a valve that is cycling with only one indicator on, giving the impression of being open or closed) or may be forced to make assumptions / decisions based on no positive indication of valve, breaker, pump condition. An erroneous decision, based on the lack of positive indication, could degrade the existing condition or precipitate a'new condition by making one of the following error types:
temporal, interpretation, reading (leading to activation error or substitution error).
(Category 1)
- 9. Procedures The emergency procedures in the procedures bench file are fairly easy to access by the operator. They have identifying tabs, by title, with one exception. The abnormal procedures have no tabs for identification and would be more difficult and time consuming to locate. " Working copies" of procedures are readily avai'able but are indexed in file cabinets by number.
Serious problems exist with procedures documents: -
e Steps are nested within other steps or stated in notes e Warnings and cautionary statements are listed as notes e Some instructions are ambiguous and extremely long, up to 57 words in one sentence e Some instructions require overly precise control processor settings, such as 71.73 = 1005 psig e The procedures give little information on what the system response is to a given operator action
e The procedures do not give the location of infrequently used controls or displays e The procedures are incomplete with steps missing e At least one abnormal procedure could not be performed to com-pletion by an operator (did not understand instructions) e Emergency procedures have not been verified by walkthroughs using a full complement of operators. Some abnormal procedures have not been verified at all.
e Certain procedures require the operator to time actions without timers available e There are instances where the terminology used in the procedures is dif ferent from that used on control panel labeling.
These problems were all identified in emergency procedures. Given the criticality of complete, accurate, and timely operator response under emergency conditions, emergency procedures should be of high fidelity to operational requirements and highly usable to the operator.
- 10. Violation of Design Conventions Conventions of switch position and color meaning are easily learned and useful to the operator. Where these conventions are violated or inverted, the likelihood of human error is greatly increased. There are a number of instances of violations of design convention in the North Anna-2 CR:
e Emergency generator exciter voltage switch operates with lef t being the " lower" and right being the " raise" position. This is contrary to the convention established on the secondary benchboard, which is the reverse. (Although the raise - lower convention is contrary to stereotype, human error is more likely to result from an inversion of a plant's established convention). (Category 2) e Feedwater heater switcha s.olate the close - open convention.
Instead, position is open - stop - close. (Category 2) e Boric acid transfer switch position 's contrary to stereotype (fast - -
- slow - off - auto) and is the reverse of the indicator light sequence.
An operator-induced error could result in switching to " fast" rather than "off" or to " auto" rather than " fast." (Category 2) e Four sump pump pushbutton switches violate a color meaning con-vention by having the " start" button green and the "stop" button red.
(Category 3) e Pressurizer safety valve temperature indicators are arranged on the panel C-B-A, contrary to stereotypical and conventional arrange-ment, A-B-C. (Category 3)
e Adjacent Foxboro meters for bearing cooling have contradictory meanings for scale indication. On one, the scale is upper end, "open,"
lower, "close." The other meter scale meaning is reversed.
(Category 3) e Meanirig for the color red in the North Anna-2 CR has an established convention of " start" or " running" condition. This convention is violated, particularly in back panels, and could induce a misinter-pretation of system or component status. (Category 2)
- 11. Computer The computer system has several problems. First is the sensor address point index.
These sensors are indexed by address point rather than by sensor name. if an operator wants to call up a specific sensor value, a list of address points must be scanned. The s.ensor address points should be indexed by three methods; 1) sensor name, 2) address, and 3) by system. Some progress towards this has been made as a partial system index is available.
i Second, the operators, when changing computer alarm setpoints, have no formal procedure for logging these changes. If an operator makes changes and goes off shif t without informing the next shif t of changes, the new operator may be making incorrect assumptions about system status. A formal log should. be kept for all changes made in sensor setpoints.
Third, the computer printer paper tends to jam because of an inadequate take-up mechanism. If the paper jams, all printing will be done on one line. The operator may lose information. A more positive take-up mechanism should be included.
(Category 3)
- 12. Hagan Process Controllers The Hagan process controllers do not give the operator a positive indication of valve
, operation. The indication received by the operator only reflects the control signal being sent. Without this positive indication of valve operation an operator may be acting on erroneous information, assuming that because an input has been made with the hagan, the valve is operating according to that input. As this could be false, a situation could be degraded or precipitated. (Category 3)
There are some specific problem Hagan controllers. The nonregulated heat exchange outlet temperature control reduces temperature by increasing the meter
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value. The Master Pressuri: Controller increases to decrease pressure. Both of these are violations of stereotype and convention. If a control is increased, the display being effected by the control should also increase. In moments of stress, this inverse relationship could induce operator error. (Category 1)
- 13. Pressurizer Relief Valve The only indication of flow in the pressurizer relief line is temperature, which has a very slow response. Without a positive reading of flow (e.g., valve position), th'e
. primary plant can depressurize. (Category 1)
- 14. General Maintenance General maintenance of the CR is inadequate, as evidenced by the fo!!owing:
e Mismatched scales on the paper in at least one strip chart recorder (Category 3) e ink differing from pen color noted in two strip chart recorders (Category 3) e Incorrect labeling noted on primary panel (Category 2) e Unlabeled vertical meter with penciled-in scale (Category 2) e Several lamps out in emergency lighting system (Category 2) e Numerous labels becoming unglued f rom panels (Category 3) e Air pack (breathing apparatus) demonstrated by operator not func-tioning correctly (Category 2) a Bulbs burned out in several indicator lights (Category 2) e Step ladders, cables, and other maintenance equipment obstructing passage around control panels (Category 3) e Five alarm panel legend lights with bulb covers difficult to remove and requiring pocket knife or similar instrument to remove for bulb changing. Bulb size making bulbs difficult to remove from : ncket.
No bulb puller is available. (Category 3) .
- 15. . La,belin g Some labels are of low contrast (particularly the purple with black print) and are of poor readability. Label coding nomenclature is inconsistent with associated L controls. (Category 3) l F
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- 16. Operator Protective Equipment There is an insufficient number of air packs to accommodate the minimum number of operators needed in the CR during an emergency. During the demonstrated donning of breathing apparatus, time to don was unacceptable and the particular air pack was not functioning.
The air packs are mounted too high to be easily donned by most operators.
Communications with the breathing apparatus are unacceptable for a distance of greater than five feet.
There is no protective clothing available to the operators in the CR.
An argument was given that the need for operator protective equipment for the North Anna CR is minimal because of the CR bottled air system. This argument is questionable based on a report in Nuclear News (March 1980) stating that during a transient at North Anna-1 in September 1979 the CR bottled air system failed to initiate. (Category 3)
- 17. Guarding of Exposed Controls North Anna has recognized the need to guard several 3-handic switches located on
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the backboard panels from inadvertent actuation. There are several other switches also needing protection. The circ. water 3-handle controls on the backboard are located about shoulder height and in a high traffic area where they could be easily bumped. The turning gear motor oil pump J-handle controls on the secondary benchboard are close to the edge of the panel and could also be inadvertently activated or deactivated. (Category 2)
- 18. Number of Personnelin the CR A large number of personnel were noted in and around primary operating areas,
.primarily during day shift operations. Unnecessary personnel in the CR present the following problems:
e Impedance of quick operator response in the event of an accident e Distraction to the operator in maintaining cognizance over system and panel status e Additional and h'e avy noise level in the CR. (Category 2)
- 19. Emergency Lighting A full demonstration of emergency lighting was not accomplished so an evaluation of its adequacy could not be made. However, lamps were noted to be out when the emergency system was turned on. Insufficient emergency lighting could lead to improper switch selection or operation, or incorrect assessment of system status during critical operations. (Category X)
- 20. Staf fing Requirements During Emergency Operations Walkthroughs revealed a necessity to monitor and control systems from at least four stations:
o Primary benchboard panel e Secondary benchboard panel e Engineered safeguards on the vertical panel e Backboard panel.
CR appears operational during emergency with a minimum complement of forr operators. Minimum staffing requirements should be further evaluated to ensure adequate personnel for emergency operations. (Category X) 3.0 HUMAN ENGINEERING STRENGTHS Several human engineering strengths which enhance plant operability were identified in the North Anna 2 CR. They are:
- 1. Diagnosis of system failures in enhanced by the first-out capability incorporated into the annunciator system and the channel trip annunciators. Additionally, the diagnostic chart which is an attachment to the reactor trip emergency procedure is a positive aid to the operator in identifying the cause of the emergency.
- 2. The convention established with the placement of simple indicator lights (green - .
red) which is strictly adhered to will prevent misplacement of caps during bulb changing. Any reversalin color would be immediately identified as a mistake.
- 3. North Anna has taken positive steps in guarding exposed switches on the backboard panels by adding guard railing. The few remaining exposed switches should be similarly guarded.
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-4. The checklists incorporated into the emergency procedures provide a very useful job
, performance aid.
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j 5._ .The horizont'al placement of vertical meters on the vertical panel is generally correlated with the placement of associated controls on the benchboard panel.
- 6. CRT can be read from all stations at the benchboard panel. !
- 7. Annunciators are generally grouped over the systems the monitor.
i 8. All filed procedures are immediately accessible to operators.
) 9. The annunciator audible alarms are loud enough to be heard over CR ambient noise l
- level, i 10. Normal lighting appears adequate.
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