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Category:INTERNAL OR EXTERNAL MEMORANDUM
MONTHYEARML20205N9871999-04-14014 April 1999 Forwards NRC Approved Operator Licensing Exam (Facility Outline & Initial Exam Submittal & as-given Operating Exam) for Tests Administered on 990308-11 ML20203G0081999-02-12012 February 1999 Forwards NRC Approved Operator Licensing Exam (Facility Outline & Initial Exam Submittal & as-given Operating Exam) for Tests Administered on 981102-06 ML20211M5671997-10-0303 October 1997 Forwards Regulatory Documents Comprising Regulatory History of Notice of Proposed Rulemaking Entitled Financial Assurance Requirements for Decommissioning Nuclear Power Reactors, Which Amended 10CFR50,published in Fr on 970910 ML20149D7851997-07-14014 July 1997 Notification of Significant Licensee Meeting W/Util on 970731 in Arlington,Tx to Discuss Case Studies (Response Time & Reactor Feedwater Pump Trip Test) & Common Themes ML20137C9201997-03-20020 March 1997 Forwards Documentation of Meeting Conducted in Region 4 Office on 970225 to Discuss NRC Enforcement Policy as Applied to Nonescalated Enforcement ML20134P5931997-02-21021 February 1997 Forwards Order Imposing Civil Monetary Penalty for Transmittal to Ofc of Fr for Publication.W/O Encl ML20132F5421996-12-19019 December 1996 Forwards NRC Approved Operator Licensing Exam (Facility Outline & Initial Exam Submittal & as-given Operating Exam) for Tests Administered on 961007-11 ML20134E9191996-10-29029 October 1996 Forwards Rationale for Inital Plants Selected for Design Insps & for Plants Considered for Second Quarter FY97 Design Insps ML20203B9891995-11-20020 November 1995 Discusses OI Rept 4-95-032 Re Alleged False Statements by Fire Watches to NRC Inspectors.Oe Will Consider Matter Closed from Enforcement Perspective Unless Different View Received within 3 Wks of Date of This Memo ML20211M6231994-11-30030 November 1994 Provides Info to Commission on Status of Rulemaking Activities Re Power Reactor Decommissioning Cost Issues,Per 930714 SRM ML20236L5631994-08-10010 August 1994 Responds to Former Region V 930422 Request for NRR Evaluation of WPPSS Practices Associated W/Testing RHR Sys While Aligned in SPC Mode ML20056E5141993-08-12012 August 1993 Submits SALP Schedule for FY94 Per Mgt Directive 8.6 ML20056E4571993-08-0505 August 1993 Forwards Technical Review Rept Re, Tardy Licensee Actions Initiated Because of Delayed Replacement of Batteries in Uninterruptible Power Supplies at Plant ML20247G1561989-05-15015 May 1989 Forwards Director'S Decision 89-03 in Response to 2.206 Petition Re BWR Stability.Petition Filed by Hiatt on Behalf of Ocre Expressing Concerns Re 890309 Power Oscillattion Event & Requested Action W/Respect to All BWRs ML20245B6421989-04-15015 April 1989 Forwards Engineering Evaluation Rept on BWR Overfill Events Resulting in Steam Line Flooding.Though Little Actual Damage Experienced,Potential for Equipment Damage Believed to Exist & Any Damage Occurring Should Be Fixed Prior to Restart ML20245B6531989-04-15015 April 1989 Forwards Evaluation Rept on BWR Overfill Events Resulting in Flooding of Steam Lines.Events Determined to Involve Deficiencies in Control Sys ML20245B6191989-04-15015 April 1989 Forwards Evaluation Rept Re BWR Overfill Events Resulting in Steam Line Flooding.All Events Included Reactor Depressurization Followed by Uncontrolled Condensate or Condensate Booster Pumps Injection or Both ML20245B7501989-04-15015 April 1989 Forwards Engineering Evaluation Rept on BWR Overfill Events Resulting in Flooding of Steam Lines.Potential for Equipment Damage Believed to Exist & Any Damage Occurring Should Be Fixed Prior to Restart ML20147E3621988-02-28028 February 1988 Summary of 880223 Operating Reactors Events Meeting 88-008. List of Attendees,Tabulation of long-term Followup Assignments to Be Completed & Summary of Reactor Scrams Encl ML20195G7981987-07-31031 July 1987 Partially Deleted Memo Forwarding SALP Rept & Recommendations Re NRC Actions for Plant.W/O Encl IR 05000397/19870061987-07-0101 July 1987 Forwards Draft SALP Rept 50-397/87-06 for Feb-May 1987 for Review.Comments Requested at SALP Board Meeting Schedule for 870707 in Region V.Update of Tables 1-4 Included in Draft. W/O Rept ML20236B1451987-06-18018 June 1987 Forwards Response to DF Kirsch 870507 Memo Requesting Performance Analysis Info for Input to Facility SALP Rept. Review Results Provided in Encl.Encl Withheld ML20214M1381987-05-26026 May 1987 Provides Enforcement Guidance to Regions for Issues Re Control Room Habitability/Control Room Emergency Ventilation Sys Deficiencies.Summary of Plants Reviewed & Documents Describing Findings Encl ML20195G7931987-05-12012 May 1987 Forwards Insp & LER Data Tables for Use in Preparing Performance Analyses for Salp,Per DF Kirsch 870507 Memo. Tables Subj to Review & Comment Until SALP Process Complete. W/O Encls ML20214A0311987-05-12012 May 1987 Notifies of 870514 Briefing on Licensing & Operational Status of Plants Assigned to Project Directorate V,Including Diablo Canyon,Palo Verde,Rancho Seco,San Onfore,Trojan & WPPSS 2 ML20212M8601987-03-0909 March 1987 Forwards SER Re Concerns Identified in Plant Fire Protection Program,As Described in FSAR Through Amend 33.Concerns Resolved Except for Listed Items,Including Adequacy of Safe Shutdown Procedures.Review Excluded Amend 37 Items ML20154A2831986-12-13013 December 1986 Forwards Assessments by Enforcement Staff of Regional Performance in Enforcement Area from Jul-Nov 1985 ML20215G1361986-10-14014 October 1986 Summary of 861006 Operating Reactor Events Meeting 86-35 Re Events Since Last Meeting on 860929.Assignees Should Review Identified Responsibilities & Completion Dates & Advise If Dates Cannot Be Met.Attendance List & Viewgraphs Encl ML20215F2751986-10-0606 October 1986 Forwards Action Timetable Re Coordinated Approach to Resolution of Fire Protection Issues at Facility ML20209A8611986-09-0202 September 1986 Forwards Matls Needed to Complete Assignment During Emergency Preparedness Exercise on 860916-19.W/o Encl IR 05000397/19860121986-08-25025 August 1986 Notification of 860828 Meeting W/Util in Walnut Creek,Ca to Discuss Apparent Violations Involving Equipment Qualification (50-397/86-12),Region V Team Insp 50-397/86-11 & Control of Combustible Matls ML20204G4051986-08-0404 August 1986 Notification of 860909 Meeting W/Utils in Bethesda,Md to Discuss Nrc/Util Living Schedules,Util Performance,Legal Considerations,Tech Spec Improvements & Severe Accident Policy/Degraded Core Programs.Proposed Agenda Encl ML20207J2451986-07-16016 July 1986 Forwards Request for Addl Info Re Util Application to Amend Tech Spec 4.6.4.1 Concerning Drywell Vacuum Breakers,For Transmittal to Licensee.Receipt of Info After 860731 Will Require Rev to 860831 Anticipated Review Completion Date ML20058K6041986-07-0303 July 1986 Informs of Telcon on Status of EA-86-110 Re Health Physics/ Emergency Planning & EA-86-070 Re Fire Protection ML20203B0881986-07-0202 July 1986 Forwards SALP Rept for Feb 1985 - Jan 1986,for Review.Salp Board Rated Licensee Performance Category 1 in Area of Outages & Category 2 in All Other Areas Except Fire Protection.W/O Encls ML20236Y1311986-04-25025 April 1986 Forwards List of Primary Containment Isolation Valves & Valve P&ID Locations as Referenced in Util 860117 & 0218 Request for Amend to License NPF-21 ML20198D7151986-04-24024 April 1986 Forwards Insp Rept 50-397/86-05,notice of Violation & Enforcement History,For Consideration & Action.Civil Penalty Unwarranted Since Fire Watches Immediately Posted & Safety Significance of Fire Loadings Limited ML17278A7091986-04-16016 April 1986 Advises That Deletion of Technical Memo 1227 Overlooked During Issuance of Amend 31 to Fsar.Memo Deleted as Result of Incorporation of Scn 83-135 Into Amend ML20195G7731986-03-14014 March 1986 Forwards Draft SALP Rept for Feb 1985 - Jan 1986,for Review & Comment at 860319 Meeting at Region V.Updated Tables 1 & 4 Also Encl.W/O Encl ML20154K1511986-03-0303 March 1986 Notifies That SALP Board 860312 Meeting Rescheduled for 860319 at Region V.Deviation from Instruction 0701 to Permit a Toth Attendance at B&W Training Course on 860303-15 in Best Interest of SALP Process ML20199D1311986-02-19019 February 1986 Informs That Proposed Recirculation Pump Vibration Testing Plan Acceptable,Based on Licensee Testing Procedure & Supporting Stress Analysis ML20203B1101986-02-13013 February 1986 Forwards Assessment of Lers,Including Results for Input Into SALP Rept for Feb 1985 - Jan 1986.LERs of Above Average Quality ML20195G7801986-02-0909 February 1986 Forwards Data Tables for Use in Preparing Performance Analysis for Salp.Insp Results & LERs Occurring During Last Month of SALP May Not Be Included in Tables.Tables Subject to Review & Comment Until SALP Process Completed.W/O Encl ML20215N3041986-01-30030 January 1986 Provides Summary of Review of Past Experience as Related to Handling of Nonradiological Issues.State of Wa Notified by NRC of Industrial Safety Concerns at Facility.Dm Kunihiro 851213 Memo to State of Wa Encl ML20151Q9751986-01-29029 January 1986 Requests Identification of Div Contact for Regional Insp Team Leaders to Arrange NRR Alternative Shutdown & Fire Protection Reviewer Technical Assistance on region-based post-fire Safe Shutdown Insps.Schedule of Insps Submitted ML20149M8611986-01-24024 January 1986 Discusses 851202-06 Observation of Seven INPO Members & Two Industry Peer Evaluators During Conduct of Site Visit to Evaluate Three Training Programs at Plant.Significant Milestones Toward Accreditation of Training Programs Listed ML20198H2291986-01-22022 January 1986 Requests Date & Subj of Application for OL Issued on 840413.Info Needed to Complete Review of 850318 Transmittal of License Fee Data & Assessment of Fees & Contractual Costs Through 841222 ML20198G8771986-01-16016 January 1986 Forwards Brief Description & Evaluation of Util 850911 Proposed Tech Spec Change to Revise Composition of Corporate Nuclear Safety Review Board.Proposed Change Acceptable ML20198G8291986-01-0606 January 1986 Forwards Draft Response to 850718 Memo Re Inspector Feedback /Request for Technical Assistance on NUREG-0737,Item II.F.1.Response Based on Review of Util Position on Iodine plate-out ML20141E9281985-12-26026 December 1985 Recommends Survey of Plants Re Licensee Review of Preservice Insp Rept & Submittal of Relief Requests.Relief Requests from Preservice Insp Should Be Submitted Before Issuance of OL & Plant Startup to Permit NRC Review 1999-04-14
[Table view] Category:MEMORANDUMS-CORRESPONDENCE
MONTHYEARML20205N9871999-04-14014 April 1999 Forwards NRC Approved Operator Licensing Exam (Facility Outline & Initial Exam Submittal & as-given Operating Exam) for Tests Administered on 990308-11 ML20203G0081999-02-12012 February 1999 Forwards NRC Approved Operator Licensing Exam (Facility Outline & Initial Exam Submittal & as-given Operating Exam) for Tests Administered on 981102-06 ML20211M5671997-10-0303 October 1997 Forwards Regulatory Documents Comprising Regulatory History of Notice of Proposed Rulemaking Entitled Financial Assurance Requirements for Decommissioning Nuclear Power Reactors, Which Amended 10CFR50,published in Fr on 970910 ML20149D7851997-07-14014 July 1997 Notification of Significant Licensee Meeting W/Util on 970731 in Arlington,Tx to Discuss Case Studies (Response Time & Reactor Feedwater Pump Trip Test) & Common Themes ML20137C9201997-03-20020 March 1997 Forwards Documentation of Meeting Conducted in Region 4 Office on 970225 to Discuss NRC Enforcement Policy as Applied to Nonescalated Enforcement ML20134P5931997-02-21021 February 1997 Forwards Order Imposing Civil Monetary Penalty for Transmittal to Ofc of Fr for Publication.W/O Encl ML20132F5421996-12-19019 December 1996 Forwards NRC Approved Operator Licensing Exam (Facility Outline & Initial Exam Submittal & as-given Operating Exam) for Tests Administered on 961007-11 ML20134E9191996-10-29029 October 1996 Forwards Rationale for Inital Plants Selected for Design Insps & for Plants Considered for Second Quarter FY97 Design Insps ML20203B9891995-11-20020 November 1995 Discusses OI Rept 4-95-032 Re Alleged False Statements by Fire Watches to NRC Inspectors.Oe Will Consider Matter Closed from Enforcement Perspective Unless Different View Received within 3 Wks of Date of This Memo ML20211M6231994-11-30030 November 1994 Provides Info to Commission on Status of Rulemaking Activities Re Power Reactor Decommissioning Cost Issues,Per 930714 SRM ML20236L5631994-08-10010 August 1994 Responds to Former Region V 930422 Request for NRR Evaluation of WPPSS Practices Associated W/Testing RHR Sys While Aligned in SPC Mode ML20056E5141993-08-12012 August 1993 Submits SALP Schedule for FY94 Per Mgt Directive 8.6 ML20056E4571993-08-0505 August 1993 Forwards Technical Review Rept Re, Tardy Licensee Actions Initiated Because of Delayed Replacement of Batteries in Uninterruptible Power Supplies at Plant ML20247G1561989-05-15015 May 1989 Forwards Director'S Decision 89-03 in Response to 2.206 Petition Re BWR Stability.Petition Filed by Hiatt on Behalf of Ocre Expressing Concerns Re 890309 Power Oscillattion Event & Requested Action W/Respect to All BWRs ML20245B6421989-04-15015 April 1989 Forwards Engineering Evaluation Rept on BWR Overfill Events Resulting in Steam Line Flooding.Though Little Actual Damage Experienced,Potential for Equipment Damage Believed to Exist & Any Damage Occurring Should Be Fixed Prior to Restart ML20245B6531989-04-15015 April 1989 Forwards Evaluation Rept on BWR Overfill Events Resulting in Flooding of Steam Lines.Events Determined to Involve Deficiencies in Control Sys ML20245B6191989-04-15015 April 1989 Forwards Evaluation Rept Re BWR Overfill Events Resulting in Steam Line Flooding.All Events Included Reactor Depressurization Followed by Uncontrolled Condensate or Condensate Booster Pumps Injection or Both ML20245B7501989-04-15015 April 1989 Forwards Engineering Evaluation Rept on BWR Overfill Events Resulting in Flooding of Steam Lines.Potential for Equipment Damage Believed to Exist & Any Damage Occurring Should Be Fixed Prior to Restart ML20147E3621988-02-28028 February 1988 Summary of 880223 Operating Reactors Events Meeting 88-008. List of Attendees,Tabulation of long-term Followup Assignments to Be Completed & Summary of Reactor Scrams Encl ML20195G7981987-07-31031 July 1987 Partially Deleted Memo Forwarding SALP Rept & Recommendations Re NRC Actions for Plant.W/O Encl IR 05000397/19870061987-07-0101 July 1987 Forwards Draft SALP Rept 50-397/87-06 for Feb-May 1987 for Review.Comments Requested at SALP Board Meeting Schedule for 870707 in Region V.Update of Tables 1-4 Included in Draft. W/O Rept ML20236B1451987-06-18018 June 1987 Forwards Response to DF Kirsch 870507 Memo Requesting Performance Analysis Info for Input to Facility SALP Rept. Review Results Provided in Encl.Encl Withheld ML20214M1381987-05-26026 May 1987 Provides Enforcement Guidance to Regions for Issues Re Control Room Habitability/Control Room Emergency Ventilation Sys Deficiencies.Summary of Plants Reviewed & Documents Describing Findings Encl ML20195G7931987-05-12012 May 1987 Forwards Insp & LER Data Tables for Use in Preparing Performance Analyses for Salp,Per DF Kirsch 870507 Memo. Tables Subj to Review & Comment Until SALP Process Complete. W/O Encls ML20214A0311987-05-12012 May 1987 Notifies of 870514 Briefing on Licensing & Operational Status of Plants Assigned to Project Directorate V,Including Diablo Canyon,Palo Verde,Rancho Seco,San Onfore,Trojan & WPPSS 2 ML20212M8601987-03-0909 March 1987 Forwards SER Re Concerns Identified in Plant Fire Protection Program,As Described in FSAR Through Amend 33.Concerns Resolved Except for Listed Items,Including Adequacy of Safe Shutdown Procedures.Review Excluded Amend 37 Items ML20154A2831986-12-13013 December 1986 Forwards Assessments by Enforcement Staff of Regional Performance in Enforcement Area from Jul-Nov 1985 ML20215G1361986-10-14014 October 1986 Summary of 861006 Operating Reactor Events Meeting 86-35 Re Events Since Last Meeting on 860929.Assignees Should Review Identified Responsibilities & Completion Dates & Advise If Dates Cannot Be Met.Attendance List & Viewgraphs Encl ML20215F2751986-10-0606 October 1986 Forwards Action Timetable Re Coordinated Approach to Resolution of Fire Protection Issues at Facility ML20209A8611986-09-0202 September 1986 Forwards Matls Needed to Complete Assignment During Emergency Preparedness Exercise on 860916-19.W/o Encl IR 05000397/19860121986-08-25025 August 1986 Notification of 860828 Meeting W/Util in Walnut Creek,Ca to Discuss Apparent Violations Involving Equipment Qualification (50-397/86-12),Region V Team Insp 50-397/86-11 & Control of Combustible Matls ML20204G4051986-08-0404 August 1986 Notification of 860909 Meeting W/Utils in Bethesda,Md to Discuss Nrc/Util Living Schedules,Util Performance,Legal Considerations,Tech Spec Improvements & Severe Accident Policy/Degraded Core Programs.Proposed Agenda Encl ML20207J2451986-07-16016 July 1986 Forwards Request for Addl Info Re Util Application to Amend Tech Spec 4.6.4.1 Concerning Drywell Vacuum Breakers,For Transmittal to Licensee.Receipt of Info After 860731 Will Require Rev to 860831 Anticipated Review Completion Date ML20058K6041986-07-0303 July 1986 Informs of Telcon on Status of EA-86-110 Re Health Physics/ Emergency Planning & EA-86-070 Re Fire Protection ML20203B0881986-07-0202 July 1986 Forwards SALP Rept for Feb 1985 - Jan 1986,for Review.Salp Board Rated Licensee Performance Category 1 in Area of Outages & Category 2 in All Other Areas Except Fire Protection.W/O Encls ML20236Y1311986-04-25025 April 1986 Forwards List of Primary Containment Isolation Valves & Valve P&ID Locations as Referenced in Util 860117 & 0218 Request for Amend to License NPF-21 ML20198D7151986-04-24024 April 1986 Forwards Insp Rept 50-397/86-05,notice of Violation & Enforcement History,For Consideration & Action.Civil Penalty Unwarranted Since Fire Watches Immediately Posted & Safety Significance of Fire Loadings Limited ML17278A7091986-04-16016 April 1986 Advises That Deletion of Technical Memo 1227 Overlooked During Issuance of Amend 31 to Fsar.Memo Deleted as Result of Incorporation of Scn 83-135 Into Amend ML20195G7731986-03-14014 March 1986 Forwards Draft SALP Rept for Feb 1985 - Jan 1986,for Review & Comment at 860319 Meeting at Region V.Updated Tables 1 & 4 Also Encl.W/O Encl ML20154K1511986-03-0303 March 1986 Notifies That SALP Board 860312 Meeting Rescheduled for 860319 at Region V.Deviation from Instruction 0701 to Permit a Toth Attendance at B&W Training Course on 860303-15 in Best Interest of SALP Process ML20199D1311986-02-19019 February 1986 Informs That Proposed Recirculation Pump Vibration Testing Plan Acceptable,Based on Licensee Testing Procedure & Supporting Stress Analysis ML20203B1101986-02-13013 February 1986 Forwards Assessment of Lers,Including Results for Input Into SALP Rept for Feb 1985 - Jan 1986.LERs of Above Average Quality ML20195G7801986-02-0909 February 1986 Forwards Data Tables for Use in Preparing Performance Analysis for Salp.Insp Results & LERs Occurring During Last Month of SALP May Not Be Included in Tables.Tables Subject to Review & Comment Until SALP Process Completed.W/O Encl ML20215N3041986-01-30030 January 1986 Provides Summary of Review of Past Experience as Related to Handling of Nonradiological Issues.State of Wa Notified by NRC of Industrial Safety Concerns at Facility.Dm Kunihiro 851213 Memo to State of Wa Encl ML20151Q9751986-01-29029 January 1986 Requests Identification of Div Contact for Regional Insp Team Leaders to Arrange NRR Alternative Shutdown & Fire Protection Reviewer Technical Assistance on region-based post-fire Safe Shutdown Insps.Schedule of Insps Submitted ML20149M8611986-01-24024 January 1986 Discusses 851202-06 Observation of Seven INPO Members & Two Industry Peer Evaluators During Conduct of Site Visit to Evaluate Three Training Programs at Plant.Significant Milestones Toward Accreditation of Training Programs Listed ML20198H2291986-01-22022 January 1986 Requests Date & Subj of Application for OL Issued on 840413.Info Needed to Complete Review of 850318 Transmittal of License Fee Data & Assessment of Fees & Contractual Costs Through 841222 ML20198G8771986-01-16016 January 1986 Forwards Brief Description & Evaluation of Util 850911 Proposed Tech Spec Change to Revise Composition of Corporate Nuclear Safety Review Board.Proposed Change Acceptable ML20198G8291986-01-0606 January 1986 Forwards Draft Response to 850718 Memo Re Inspector Feedback /Request for Technical Assistance on NUREG-0737,Item II.F.1.Response Based on Review of Util Position on Iodine plate-out ML20141E9281985-12-26026 December 1985 Recommends Survey of Plants Re Licensee Review of Preservice Insp Rept & Submittal of Relief Requests.Relief Requests from Preservice Insp Should Be Submitted Before Issuance of OL & Plant Startup to Permit NRC Review 1999-04-14
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NOV 2 51993 Central Files HFEB Files DHFS R/F VMoore HFEB Members 6q r o "g i,Ei!0R/4!!DUtl FOR: Thomas it. l'ovak, Assistant Director D for Licensing Division of Licensing FR0ft: Lifllian T. Russell, Deputy Director Division of Hunan Factors Safety
SUBJECT:
lluf!Aff FACTORS EllGIffEERIflG SRAflCll SER IrlPUT FOR WASillfiGT0f!
PUBLIC PO!!ER SUPPLY SYSTEl!flUCLEAR PROJECT fl0. 2 The enclosed SER provides the results of our preliminary design assessnent (PDA) audit of the UflP-2 control roon and renote shutdown facility. The applicant requested a PDA review in February 1982, and subnitted an acceptable PDA report in April 1983. Our on-site audit was conducted June 6-9, 1983 and our audit report was fornally transmitted to the applicant on September 20, 1983. The applicant responded to our audit report on October 14, 1983 and a staff / applicant neeting to discuss our audit report and the applicant response was held _cn f!ovenber 2, 1983.
The applicant will be required to subnit a Detailed Control,Roon Design Review (DCRDR) Progran Plan, cond ct a post-licensing DCRDR, and submit a Sunnary Report. The agreed upon schedules for these actions are addressed in the SER.
Ilith conpletion of those SER f tens recuired prior to licensing, before exceeding 5 percent power and within 4 nonths of licensing, we conclude that frcn a human factors standpoint an operating license can be granted for 1flP-2. The license should be appropriately conditioned to require conpletion of the identified post-licensing actions.
This report was prepared by R.11. Froelich (x24883) of the Hunan Factors Engineering Branch. The reviewer knows of no differing technical opinions.
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/ Willian T. Russell, Deputy Director Division of Hunan Factors Safety 7 ~
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HUMAN FACTORS ENGINEERING BRANCH CONTROL ROOM DESIGN REVIEW SAFETY EVALUATION REPORT SUPPLEMENT WASHINGTON PUBLIC POWER SUPPLY SYSTEM NUCLEAR PROJECT N0. 2 Position All licensees and applicants for an operating license are required to conduct a Detailed Control Room Desict Review (DCRDR) in response to NRC Task Action Plan Item I.D.1 (NUREG-0660, May 1980; and NUREG-0737, November 1980 as supplemented by Generic Letter 82-33, December 17,1982). The purpose of the DCRDRistoidentifyandcorrecthumanengineeringdiscrepancies(HEDi)that might affect the operator's ability to prevent or cope with an accident.
NUREG-0700, " Guidelines for Control Room Design Reviews," dated September 1981, provided guidance for conducting the DCRDR. Applicants who had a supplement to their Safety Evaluation Report published before June 1983 may be licensed on the basis of a DCRDR or a Preliminary Design Assessment (PDA).
Applicants whose license is based on a PDA must also conduct a DCRDR following licensing. That DCRDR will be conducted on a schedule to be negotiated with the NRC.
Discussion The applicant submitted a Preliminary Control Room Human Engineering Report in January 1982 and informed the NRC in February 1982 of its intent to conduct a PDA before licensing. The staff's SER, issued in March 1982, concluded that it was appropriate for the applicant to seek a PDA review of the control room, but that the Preliminary Control Room Human Engineering Report did not satisfy the NUREG-0737 requirements for a PDA report. The SER
noted that an acceptable PDA report would be needed before any additional control room review could be accomplished by the staff. In April 1983 the applicant submitted a Control Room Design Review Preliminary Report which satisfied the requirements for a PDA report. The staff conducted an on-site audit of the WNP-2 control room on June 6-9, 1983. The staff was assisted by consultants from Lawrence Livermore National Laboratory. The audit was based on the applicant's Control Room Design Review Preliminary Report and an independent assessment of the WNP-2 control room and remote shutdown facility. The staff's audit report summarizing the results of a review of the applicant's PDA report and of the on-site audit was transmitted to the applicant September 20, 1983. The report addressed the following:
- a. Control room features that could not be evaluated at the time of the audit
- b. Applicant identified HEDs that had been satisfactorily correcteif at the time of the audit
- c. Applicant identified HEDs for which the proposed correction was satisfactory but which had not been corrected at the time of the audit
- d. HEDs identified by the staff during the audit
R
- e. Applicant identified HEDs for which the proposed correction was judged unsatisfactory,
- f. Applicant identified HEDs for which the proposed correction was satisfactory but.which had unsatisfactory implementation schedules.
The applicant's response to the audit report was submitted to the staff on October 14, 1983. It addressed parts a, d, e and f of the staff's audit report. A meeting with the staff and applicant to discuss the audit report and the applicant's responses was held November 2, 1983.
Conclusions l
At the November 2, 1983 meetfng, the applicant verbally proposed, and the NRC accepted, schedules for correcting certain HEDs prior to escalation above 5 percent power, and within four months after licensing. The NRC believes that the proposed schedules for correcting HEDs will not present a significant safety risk to the public. However, the staff will require correction of the most significant HEDs before licensing, and some HEDs which require further analysis are being deferred to the DCRDR. Many of the HEDs were identified by the applicant in its PDA report, and plans for their correction '
are in progress or completed. The NRC has accepted interim solutions for some HEDs which require further analysis to arrive at permanent or optimum solutions. The NRC believes that correction of HEDs discussed under Paragraphs B and C below prior to escalation above 5 percent power and within four months after licensing, respectively, will not impact safe operation of the plant during that period.
, ~ - _ -,
A. HEDs To Be Corrected Before Licensing
- 1. Attachment A lists those HEDs for which acceptable solutions were proposed by the applicant in its Control Room Design Review Preliminary Report. The NRC will verify that the proposed design improvements have been implemented before licensing.
- 2. Attachment B lists those HEDs for which acceptable solutions were provided by the applicant in its August 26, 1983 response to NRC's Human Factors Engineering Preliminary Design Assessment Audit Report. The NRC will verify that the proposed design improvements have been implemented before licensing.
I j B. HEDs To Be Corrected Before Exceeding 5 Percent Power Attachment C lists those HEDs for which acceptable solutions were proposed by the applicant in its response to NRC's Human Factors Engineering Preliminary Design Assessment Audit Report. The proposed
, corrections are to be implemented and verified before exceeding 5 percent power. The applicant verbally committed to provide a letter report to the staff verifying correction of these HEDs.
l C. HEDs Which The Applicant Proposed To Correct Within 4 Months After Licensing l Attachment D lists thosed HEDs for which acceptable solutions were proposed by the applicant in its response to NRC Human Factors l Preliminary Design Assessment Audit Report. The proposed corrections i
are to be implemented and verified not later than 4 months after licensing. The applicant verbally committed to provide a letter report to the staff verifying correction of these HEDs.
D. HEDs To Be addressed In The DCRDR Attachment E provides a list of HEDs which have been identified at this time as problem areas to be addressed in the DCRDR. These HEDE do not represent the entire scope of the DCRDR process as described in Supplement 1 to NUREG-0737. A complete review of annunciator control l system design, location and operation is also required as a part of the DCRDR.
E. HEDs To Be Addressed On A Special Case Basis The following HEDs require special treatment:
- 1. Finding A 1.2 - Panel P-813.
Portions of Panel P-813 were under construction and could not be reviewed during the staff's on-site audit. The applicant shall complete this review, identify any HEDs, describe design l solutions and establish an implementation schedule for their correction prior to licensing. Review results shall be provided to the staff in a letter report. Verification of HED improvements shall be addressed in the DCRDR.
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6-2.' .Fidding A 1.17 - Operator Protective Equipment.
The applicant shall verify operator vision and communication capability while wearing Scott Air Packs. The review shall be y completed prior to licensing, and verification shall be reported to the staff by letter report.
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- 3. Finding D 1.30 - Glare At Remote Shutdown Panel.
Glare elimination at Panel P-001 shall be corrected no later than 4 months after licensing. Temporary resolution of this HED is permissable pending installation and confirmati6n of permanent glare-eliminating diffusers.
F. Detailed Control Room Design Review The applicant will comply with the requirements of Supplement 1 to NUREG-0737 addressing the DCRDR. The applicant shall submit a Program Plan for this review no later than 2 months after licensing, and shall submit a Summary Report not later than 6 months pri.or to the scheduled first refueling outage.
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REFERENCES
- 1. NUREG-0660, Volume 1, May 1980; NRC Action Plan Developed as a Result of the TMI-2 Accident.
- 2. NUREG-0737, November 1980; Clarification of TMI Action Plan Requirements.
- 3. NUREG-0700, September 1981; Guidelines for Control Room Design Reviews.
- 4. Supplement 1 to NUREG-0737, December 1982; Requirements for Emergency Response Capability (Generic Letter No. 82-33).
- 5. Letter to A. Schwencer from G. D. Bouchey, January 11, 1982; Nuclear Project No. 2 Preliminary Control Room Human Engineering Desigd Report.
- 6. Letter to Director of Nuclear Regulation from G. D. Bouchey, April 14, 1983; Nuclear Project No. 2 Control Room Design Review, Submittal of Preliminary Report.
- 7. Letter to D. W. Mazur from A. Schwencer, September 20, 1983; Nuclear Project No. 2 Preliminary Design Assessment Audit Report.
- 8. Letter to Director of Nuclear Regulation from G. C. Sorensen, October 14, 1983; Nuclear Project No. 2 (Response to) Preliminary Design Assessment Audit Report.
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ATTACHMENT A HEDs TO BE CORRECTED BEFORE LICENSING The following HEDs are identified by the Finding number as given in Part C of the staff's Human Factors Engineering Preliminary Design Assessment Audit, and the corresponding WNP-2 HED number as given in the applicant's Control Room Design Review Preliminary Report. Staff comments associated with some of these HEDs are identified by a parenthetic number following the finding number. These staff comments are listed at the end of this section.'
Finding WNP-2 HED Finding WNP-2 HED Finding WNP-2 HED 1.13 '24.5.1 3.3 24.3.3 3.30 (5) 14.3.8.a 1.14 23.3.2 3.6 14.3.20 3.31 (5) 14.3.8.b 1 15 (1) 3.3.1.d 3.7 14.3.9 3.32 (5) 14.3.8.c 1.16 (2) 24.5.10 3.12 24.3.8 3.33 (5) 14.3.8.d 1.19 (3) 19.3.1 3.19 (4) 18.3.1 3.34 (5) 14.3.8.e 3.1 24.3.1 3.22 14.5.3.3 3.38 (5) 14.3.8.1 3.2 24.3.2 3.29 14.3.4 3.39 (5) 14.3.8.j 3.40 (5) 14.3.8.k 5.13 10.3.5 6.12 7.3.43 3.41 14.3.8.1 5.14 24.6.3 6.13 7.3.40.a 3.42 24.3.9.a 5.18 10.3.16 6.14 7.3.40.b 3.43 24.3.9.b 5.19 24.4.6 6.15 7.3.40.c 3.44 24.3.9.c 5.20 24.4.7 6.16 7.3.40.d 3.45 24.3.9.d 5.21 24.4.8 6.17 7.3.40.e 3.46 14.3.10 5.23 24.6.25 6.18 (8) 7.3.41 3.47 14.3.5 5.24 10.3.13 6.19 7.3.42 3.51 14.5.5.2.c 5.25 10.3.15 6.20 24.6.21
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I Finding WNP-2 HED Finding WNP-2 HED Finding WNP-2 HED 3.52 (4) 14.5.3.2 .5.26 6.3.2 6.21 5.3.4 3.53 14.5.4.3 5.27 24.4.4 6.22 7.3.33 3.54 14.3.12 5.28 24.6.30 6.23 7.3.34 4.9 13.3.7.c 5.29 24.6.22 6.24 7.3.8 4.10 13.3.13 5.30 (6) 11.3.7 6.25 7.3.35 4.11 3.3.2.b 5.64 (7) 12.3.2 6.26 7.3.36 4.12 13.3.1.a 5.65 (7) 12.3.3 6.27 7.3.37 4.13 13.3.1.c 6.1 7.3.1 6.28 13.3.17 4.14 13.3.3 6.2 6.3.8 6.29 24.6.7 4.15 13.3.2 6.3 7.3.2 6.30 24.6.14 4.16 13.3.15 6.4 -
7.3.4 6.31 24.6.16 4.17 13.3.16 6.5 7.3.7 6.32 24.6.17 4.18 24.6.33 6.6 7.3.9 6.33 24.6.18 5.2 10.3.6 6.7 11.3.6 6.34 24.6.19 5.5 11.3.2 6.8 24.6.8 6.35 5.3.14 5.9 24.7.2 6.9 24.6.9 6.36 7.3.3 5.10 24.4.3 6.10 7.3.10 6.37 7.3.6 5.12 24.4.2 6.11 7.3.3.2 6.38 7.3.38 6.39 7.3.39 6.70 5.3.1 8.25 24.5.2 6.40 11.3.8 6.71 5.3.2 8.27 5.3;19 6.41 11.3.9 6.73 24.6.1 8.28 24.6.6 6.42 11.3.10 6.74 6.74 8.29 5.3.18 6.43 7.3.15 6.75 5.3.3 8.30 5.3.12 6.44 7.3.16 6.77 5.3.8 8.49 5.3.16.b
Finding WNP-2 HED Finding WNP-2 HED Finding WNP-2 HED 6.45 7.3.25 6.79 24.6.3 6.47 7.3.17 6.80 5.3.5 6.48 7.3.18 6.81 5.3.6 6.49 7.3.19 7.2 15.3.2 6.50 24.6.10 8.1 5.3.16.h 6.51 24.6.11 8.4 12.3.4.d 6.52 8.3.13 8.5 24.5.6 6.54 7.3.21 8.8 5.3.16.j 6.55 7.3.22 8.10 24.5.8 6.56 7.3.23 8.12 13.3.10 6.57 7.3.24 8.13 -
12.2.4.a 6.58 7.3.26 8.14 12.3.4.b 6.59 7.3.27 8.15 12.3.4.b 6.60 24.6.12 8.16 5.3.16.d 6.61 24.6.15 8.17 5.3.16.f 6.62 24.6.20 8.18 5.3.16.g l 6.63 13.3.4 8.19 24.6.5
! 6.64 (9) 7.3.28 8.20 24.7.5 6.65 7.3.5 8.21 5.3.10 6.66 7.3.11 8.22 5.3.11 6.67 13.3.5 8.23 5.3.20 l
. 6.69 10.3.7 8.24 5.3.22 1
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Notes for Attachment A HED Listina
- 1. Legibility of illuminated status indicators should be reviewed and verified before licensing.
- 2. Glare and parallax should be reviewed and verified as acceptable before licensing.
- 3. See Finding 1.36. Diffusers for remote shutdown panel light fixtures should be installed before licensing. Temporary solutions are acceptable.
- 4. This HED should be reviewed in conjunction with Finding 3.22.
- 5. The wording of these alarm panels does not clearly define the meaning of the alarm.
- 6. Pen color parameter should be noted on all recorders.
- 7. Shift turnover procedures should be reviewed and verified before licensing. A detailed review of the single indicating light problem and potential design solutions should be made during the DCRDR.
- 8. Verification that an administrative procedure controlling the use of temporary labels should be provided before licensing.
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- 9. See Finding 6.108 concerning labels with.too narrow stroke width.
(Section A.2)
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ATTACHMENT B HEDs TO BE CORRECTED BEFORE LICENSING The following HEDs are identified by the Part and Finding number as given in the staff's Human Factors Engineering Preliminary Design Assessment Audit Report. The applicant's proposed solutions were given in his response to the staff's Human Factors Engineering Preliminary Design Assessment Audit Report,
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and reference the staff's Part and Finding number.
Finding Finding Finding Finding Part A Part D (Cont'd) Part D (Cont'd) Part D (Cont'd) 1.1 5.33 6.95 8.33 6.99 8.34 1.18 5.34-1.20 5.36 6.100 (1) 8.35 1.31 5.37 6.102 8.36 3.5 5.41 6.103 8.40 5.43 6.104 8.41 Part D 5.45 6.107 8.42 1.21 5.48 6.108 8.44 1.28 5.50 6.109 3.57 6.87 6.110 Part E 3.58 6.88 6.111 1.32 3.62 6.89 6.112 3.67 3.64 6.90 7.4 3.68 4.20 6.93 7.10 3.71 (2) 4.24 6.94 8.31 4.31
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Finding Finding Finding Finding Part E (Cont'd) Part F Part F Cont'd) Part F (Cont'd) 5.8 3.72 5.60 5.76 3 5.62 (3) 3.74 5.68 8.48 6.53 4.32 5.71 6.113 4.36 5.73 w
Notes:
- 1. Temporary labels acceptable until permanent labels are installed.
- 2. Mushroom heads, main bench boards, i
- 3. Temporary markings on selected indicators.
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l ATTACHMENT C HEDS TO BE CORRECTED BEFORE EXCEEDING 5 PERCENT POWER The following HEDs are identified by the Part and Finding number as given in the staff's Human Factors Engineering Preliminary Design Assessment Audit Report. The applicant's proposed solutions were given in its response to the staff's Human Factors Engineering Preliminary Design Assessment Audit Report,
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and reference the staff's Part and Finding number.
Finding Finding Finding Part A Part D (Cont'd) Part E 5.17 5.40 5.61 7.15 5.44 5.69 5.46 Part D 6.101 Part F 3.59 8.38 4.37 4.23 8.43 9.5
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ATTACHttENT D HEDs TO BE CORRECTED NOT LATER THAN 4 MONTHS AFTER LICENSING The following HEJs are identified by the Part and Finding number as given in the staff's Human Factors Engineering Preliminary Design Assessment Audit Report. The applicant's proposed solutions were given in its response to the staff,'s Audit Report, and reference the staff's Part and Finding number.
Finding Finding Finding Finding Part A Part D Part E Part F 3.4 4.22 3.71 6.115 5.49 4.27 6.116 e
ATTACHMENT E HEDs To Be Addressed In the DCRDR The following HEDs are identified by the Part and Finding number as given in the staff's Human Factors Engineering Preliminary Design Assessment Audit Report.
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Finding Finding Finding Finding Part A Part D (Cont'd) Part E (Cont'd) Part E (Cont'd) 1.3 6.97 4.29 5.70 6.105 5.11 Part D 7.3 5.51 Part F 1.27 7.6 5.52 3.76 2.2 7.14 5.53 5.72 3.55 9.6 5.54 5.73 3.57 9.8 5.55 5.75 3.59 5.56 6.114 5.32 Part E 5.58 8.50 5.38 1.
33 5.59 8.51 5.39 1.34 5.62 8.52 5.47 3.66 5.63 6.91 3.71 5.66 A complete review of annunciator control system design, location and operation is also required as a part of the DCRDR. HEDs that currently address the annunciator control system are as follows:
Finding . Finding Finding D 3.60 0 3.70 F 3.79 0 3.61 F 3.18 F 3.80 D 3.63 F 3.77 O