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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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1985 DIN"5:
APR 5 Central Files EFEB Files (2)
DHFS Files (2)
WRegan HFEB Members MEMORAf100f1 FOR: Ross A. Scarano, Director Division of Radiation Safety and Safeguards Region V FROM: William T. Russell. Acting Director Division of Human Factors Safety Office of Nuclear Reector Regulation
SUBJECT:
HUMAri FACTORS ENGIt'EERING PRANCH IflPUT F0P. TUE tHP-P EMERGENCY RESPDNSE FACILITIES APPRAISA'. REPORT Genrge Lapinsky of the Hunan Factors Enginearing Granch was involved in the liarch 25-29, 1905 appraise 1 of the Energencv Response Facilities et WNP-2. The results of his review arc enclosed for your ute in documenting the overall appraisel results. Any questions regarding this natter should be dirceted te Mr. Lapinsky (492-9694).
C;':'*C f:' wit 5 ,
- a. , .%,a-du ~
Willian T. Russell, Acting Director
-! ' ' ,/ Divicion nf Hunan Factors Sa'etv Office of fluclear Peactor Regulatfon
Enclosure:
As stated cc: E. Willians M. Schuster, R. V R. Fish, R. V G. Temple, R. Y m
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HUMAN FACTORS ENGINEERING BRANCH INPUT FOR THE WNP-2 EMERGENCY RESPONSE FACILITIES '
APPRAISAL REPORT During the week of March 25-28, 1985 an appraisal of the WNP-2 Emergency Response facilities (ERF) was done. The Human Factors Engineering Branch (HFEB) participated in the appraisal and was responsible for the review of certain inspection items in IE Inspection Procedure 82212, Rev. 5. The results of the HFEB review are presented here by inspection cuidance number.
1.0 Technical Support Center (TSC) 1.1.1.1 Size: /
The TSC was designed to accommodate a minimum of 25 people. Useable floor space was estimated by the licensee to be about 3,100 square feet. The staff estimated the number of people assigned to be 30-35 and the area of assigned workspace to be about 2,500 square feet. The TSC walk-through did not provide an opportunity to do a dynamic evaluation, but in the subjective judgment of the staff (based on static, visual inspection), the size of the TSC is adequate for the 30-35 people assigned.
1.1.1.2 Layout:
The layout of the TSC was designed without benefit of a task analysis or information flow analysis. However, users were involved early in the design, and any deficiencies or recomnendations that arose during drills and exercises were formally reported and factored into the design. In addition, the licensee compared the WNP-2 design with the design of other licensee's ERFs to identify whether any important design aspect had been overlooked.
Because of time constraints, the TSC walk-through did not afford the staff an opportunity to evaluate the dynamics of the TSC layout. However, based on static visual inspection and the licensee's onocing deficiency-reporting-
' system, the staff judges the layout of the TSC to be adeouate to support its function.
1.1.1.6 Display Interfaces: '
The TSC has several methods available for display of information which fall into two general categories: (1) computer-baseddisplays,and(2) non-computer-based displays. The non-computer-based displays include plant status boards, accountability logs, significant event logs, historical event records (hand-written Vu-graphs), and printed output from the facsimile copier. The staff found the non-computer-based displays to be easily readable and understandable, and adequate to support TSC functions.
The computer-based displays, on the other hand, had a number of shortcomings that could adversely affect the function and/or the timeliness of response of the TSC. The staff recommends that the licensee address the issues described below as areas needing improvement.
The first observation has to do with several issues that interactively culminate in a condition known as " lock-out." " Lock-out" is a condition in which the computer will not respond to commands from the user's terminal -
the user cannot even escape or interrupt the program to start over.
The issues involved in this problem (from the human factors perspective) are:
(1)computerresponsetimesarevariableandoftenveryslew;(2)nofeedback is provided to tell the user that a command has been received and/or the computer is working on the command; (3) the system " stacks" commands and works on them sequentially, and (4) the systen provides no meaningful error messages and has no " HELP" function. These issues interact in the following way:
Because the response time of the computer is variable, users have no consistent time constant by which to judge whether the computer is responding normally. Because response times are sonetimes very long (greater than 30 seconds), the user cannot quickly discriminate between a slow response and ne response. In addition, the users are generally provided with no feedback messages that could alleviate the problems of slow and variable respense,
i.e., visual or audible indications that a comand has been received and is being executed.
Given the above situation, the staff observed that users had difficulty determining whether a program was executing properly. A comon user response was to hit a function button repeatedly after 5-10 seconds, then to variously hit the " break" key, the " return" key, and/or a control character string. If none of those actions elicited a response, the user would assume that the terminal was " locked-out" and the user would either reset or turn off the tenninal and attempt to reload the program using control character comands.
If unsuccessful, the user would then call a computer professional for help.
o The staff noted that even if a program was executing correctly (albeit slowly) after 5-10 seconds, users tended to assume that the command was not being executed and would start entering new commands, etc. as described above. Since the computer " stacks" comands, the likelihood of sequencing errors is increased and may, in fact, account for some of the " lock-out" problems being experienced. The situation is further exacerbated by the lack of meaningful error messages and the lack of a " HELP" function.
In summary, the users of the computer terminals in the TSC may be
" locked-out" for seconds to minutes. The system provides little or no user feedback for the user to determine program status, and provides few meaningful error messages and no " HELP" function.
The second observation by the staff was that TSC and EOF terminals could affect the " Emergency Classification" status bar on the SPDS in the control room without the knowledge or consent of the control room operators.
The Graphic Display Systen (GDS) is a software subsystem that provides various displays of plant operational data, e.g., major plant variables' current values and trends,= isolation valve status, control rod position, etc.
One of the features of the GDS is a status bar representing " Emergency Class'ification." This status bar is on all cf the top-level or current 4
4 conditions display pages. It is intended to alert the Control R'som, TSC, and EOF personnel to possible changes in Emergency Classification Levels, i.e.,
Unusual Event, Alert, Site Area Emergency, General Emergency. The bar is normally areen but changes to yellow, red, and magenta as the event classification escalates. The inputs determining the classification level are provided by a software routine that takes into account plant symptoms and radiological release data.
The staff found that the Emergency Classification bar could be put into an alerting state from the E0F by doing dose projections on another software subsystem that feeds a calculated value to the Emergency Classification
, routine in GDS.
Although the staff does not believe that this problem will compromise the function of the TSC or E0F, it is a disrupting influence and should be corrected by enhancing facility security at the EOF or terminal security at the TSC and E0F. In addition, confirmatory prompts should be added so that the user knows that he is about to change emergency levels, e.g., " Based on plant conditions, your current proiection of dose rate will change the Emergency Classification Level to (Unusual Event, etc.). Do you want to do this? If so, call the control room, x , and the TSC, x ; inform them of the change in status, they type YES, and press return. If not, press
'F17' to return to the menu." Such prompting would minimize inadvertent changes to the GDS displays-.
The staff also observed that there is no direct display of maxinum integrated dose or dose rate at the 1.2 mile site boundary. Since this value may affect emeroency action levels, and since it is already automatically calculated and is an input to the GDS Emergency Classification status bar algorithms (see above), the staff feels that it should be displayed or made easily displayable. Currently, personnel in the TSC and Control Room must estimate values from grid map displays which are virtually unreadable (data is printed inyellow).
At the exit briefing the licensee protested that this was not th'e case.
Further investigation confirmed that the staff was correct - there is no direct display of dose / dose rate at the site boundary. In addition, control room personnel stated that they probably would use the TRS-80 microcomputer to calculate the 1.2 mile dose rate because estimation from the grid map displays is so cumbersome.
The final observation regarding the TSC computer-based displays was that there was extreme glare on the cathode-ray-tube (CRT) screens that affected the readability of the displays. Of particular concern was the poor readability of the " slave" monitor in the center of the TSC which is intended for use by the Plant Emergency Director and his technical staff. There are several economical methods for reducing CRT glare, such as CRT hoods or egg-crate diffusers for overhead lighting. The licensee should investigate some of these alternatives.
1.2.6.1 Validation and Verification The computer programs supporting the TSC and EOF functions were subjected to an independent Verification and Validation (V&V) Program by NSS Incorporated.
The Program included fourteen simulated transients.and three major pre-ops tests. The front-end data acquisition system (TDAC) was validated by direct correlation with control room indications. Several volumes of V&V results were available, but because of time constraints the staff did not review l these documents.
1.2.6.3 Manual Systems For manually gathered data, the licensee has no extraordinary method for assuring the reliability and validity of the data. Crosschecks and confirmations are done only if the values are deemed to be questionable.
Formal procedures and checklists are generally not used for data gathering, and independent sources of irformation are generally not sought except when the primary source fails (as with meteorological data).
In summary, the staff confirmed that computer software was subjected to a V8V Program to assure its reliability; however, manual data gathering systems are rot normally subjected to a reliability check unless the data is deemed to be questionable.
1.3.1.4 Communication Interfaces During the walk-through the staff observed that the designated communications interfaces between the control room, TSC, OSC, and E0F are easily identifiable and conveniently located. Communication pro:edures were not exercised during the walk-through and, therefore, their adequacy could not be determined.
3.0 Emergency Off-site Facility (EOF) 3.1.1.1 Size The E0F was designed using the guidance of NUREG-0696 and NUREG-0654 as criteria for size. The useable area is estimated to be 20,000 square feet and the design assumption for number of personnel is 50. Generally, all work areas are multipurpose, that is, they serve as office and classroon space on a day-to-day basis and are "taken over" during emergencies. Because the primary use of these spaces is as offices or classrooms, they were amply
' sized and will accommodate greater than the 50 people assumed in the EOF design criteria. The staff concludes that these areas provide adequate workspace for EOF functions to be carried out.
,3.1.1.2 Layout During the initial design development, design guidelines were established for necessary adjacencies and sepa 3tions. These have generally been adhered to.
Although the EOF walk-through did not allow a dynamic evaluation of the EOF layout, the staff's visual inspection identified no obvious problem in the present arrangement. The staff suggests that the licensee consider moving
, the " Decision Center" to a more central location, such as the area now designated as the "Off-site Agency Coordination Center."
3.1.1.6 Display Interfaces '
The staff observed that the non-computer-based displays used in 'the E0F were consistent with those in the TSC and Operational Support Center (OSC), and were easy to read and understand.
Computer-based displays suffered from the same shortcomings as those in the 1SC (described in Section 1.1.1.6), except that glare did not seen to be as bad a problem in the E0F. In addition, output from the printer in the Meteorology and Unified Dose Assessment Center (MUDAC) was almost unreadabic because the ribbon needed changing. Staff suggests that routine maintenance and surveillance should be done on E0F equipment to avoid such problems
. during emergencies. Also, there was no users' manual or other documentation available in the Technical Data Center that described the operation of the Graphics Display System. Finally, hardcopy of operational data and trends is difficult and cumbersome to get - data values must be accessed through a start-up and testing program (STAR) and printed in textual form; copies of graphic displays from GDS cannot be produced at all in the E0F.
3.2.6.1 Validation and Verification and 3.2.6.3 Manual Systems The observations of the staff concerning the TSC (described in Section 1.2.6.1 and 1.2.6.3) apply to the E0F as well .
3_. 3 .1. 4 Communications Interfaces The walk-through of the EOF did not afford the staff an appropriate opportunity to evaluate the functionirg of the ccmmunications interfaces.