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Category:GENERAL EXTERNAL TECHNICAL REPORTS
MONTHYEARML20206T4771999-05-31031 May 1999 Rev 3 to UFSAR Chapter 15 Sys Transient Analysis Methodology ML20203J8581998-01-31031 January 1998 Rev 2 to Catawba Nuclear Station PRA Summary Rept, for Jan 1998.W/one Diskette ML20094N0751995-10-31031 October 1995 Validation of Crest, Interim Rept ML20117M8021995-07-31031 July 1995 CNS Standby Nuclear SW Pond Analysis ML20094N0641995-07-31031 July 1995 Computer Program for Coupled Response Spectrum Analysis of Secondary Sys ML20086F4711995-06-30030 June 1995 Interim Plugging Criteria 90 Day Rept ML20098A4511995-04-30030 April 1995 Stations Replacement SG Topical Rept ML20083N7541995-04-24024 April 1995 Rn Sys Corrosion in Stainless Steel Welds Metallurgical Analysis Rept ML20117M7911995-02-28028 February 1995 Standby Nuclear SW Pond Physical Testing Conducted During Feb 1995 ML20077R7101994-12-20020 December 1994 CNS Units 1 & 2 10CFR50.59 Evaluation of FSAR Change Related Edsfi Deviation 50413,414/92-01-02 (IEEE 308-1974) ML20077C5771994-11-0303 November 1994 1 Cycle 7 Interim Plugging Criteria Assessment & Projected EOC-8 Slb Leakage ML20072T4441994-08-31031 August 1994 Selected Licensee Commitments ML20063E2801994-01-31031 January 1994 Duke Power Co Catawba Nuclear Station Special Rept RHR Pump Vibration ML18010B0841993-05-0505 May 1993 NRC Licensing Submittal Review of Licensing Conditions Imposed by NUREG-1216. ML18010A9521992-11-30030 November 1992 NRC Licensing Submittal Review of Licensing Conditions Imposed by NUREG-1216. ML20062G7271990-11-19019 November 1990 Eddy Current Exam Rept Catawba Unit 2 June 1990 Refueling Outage 3 ML20043E7701990-02-28028 February 1990 Rev 0 to Catawba Unit 2 Cycle 3 Core Operating Limits Rept. ML20043E8101990-02-28028 February 1990 Rev 0 to Catawba Unit 1 Cycle 5 Core Operating Limits Rept. ML20154K2091988-09-0909 September 1988 Rev 0 to Response to NRC Bulletin 88-005,Nonconforming Matls Supplied by Piping Supplies,Inc at Folsom,Nj & West Jersey Mfg Co.... Proprietary Procedure 1404.1, Leeb Hardness Testing (Equotip).... Encl.Procedure Withheld ML20196L6281988-05-20020 May 1988 Rev 2 to ATWS Mitigation Sys Actuation Circuitry (Amsac) ML20212K1201987-01-23023 January 1987 Final Design Description,Atws Mitigation Sys Actuation Circuitry ML20207H9651986-05-13013 May 1986 SPDS Software Verification & Validation Summary Package, Catawba Nuclear Station ML20155F7451986-04-30030 April 1986 Draft Main Bearing Shell Analysis 2B Emergency Diesel Generator-Catawba Unit 2 ML20155F7381986-04-30030 April 1986 Diesel Generator 2B 7 Main Bearing Failure Rept,Low Power License Condition 13,Attachment 1,Item 9 ML20198J4071986-04-30030 April 1986 Rev 1 to Catawba Nuclear Station Diesel Engine 2A Component Revalidation Insp ML20203N4171986-04-30030 April 1986 Rev 2 to Tdi Owners Group App Ii:Generic Maint Matrix & Justifications ML20207H9701986-04-28028 April 1986 SPDS Maint Summary Package,Catawba Nuclear Station ML20207H9601986-04-23023 April 1986 SPDS Human Factors Program Summary Package,Catawba Nuclear Station ML20207H8901986-03-27027 March 1986 SPDS Design Basis Summary Package,Catawba Nuclear Station ML20210E5111986-03-25025 March 1986 Rev 13 to Pages from Analysis of Hydrogen Control Measures at McGuire Nuclear Station, Responding to Questions Transmitted by Youngblood ML20207H9211986-03-14014 March 1986 SPDS Critical Safety Function Selection Summary Package, Catawba Nuclear Station ML20207H9541986-03-14014 March 1986 SPDS Logic Verification Summary Package,Catawba Nuclear Station ML20207H9501986-03-14014 March 1986 SPDS Logic Generation Summary Package,Catawba Nuclear Station ML20207H9331986-03-14014 March 1986 SPDS Status Trees Development Summary Package,Catawba Nuclear Station ML20138P4801985-12-17017 December 1985 Diesel Engine 2B Component Revalidation Insp ML20137V9141985-09-25025 September 1985 Diesel Engine 2A Component Revalidation Insp ML20215C4221985-08-31031 August 1985 Rod Swap Methodology Rept for Startup Physics Testing ML20128E9831985-06-21021 June 1985 Diesels - Tdi Owners Group Design Review/Quality Revalidation Final Rept,Summary of Recommendations ML20115E0231985-04-30030 April 1985 Main Steamline Break Inside Containment, Bimonthly Status Rept for Apr 1985 ML20198B5701985-02-28028 February 1985 Rev 1 to Tdi Diesel Generator Design Review & Quality Revalidation Rept, Vols 1-4 ML20090J0071984-07-31031 July 1984 Description of Deviations from Generic Emergency Response Guidelines (Westinghouse Owners Group ERG-Basic Edition) ML20092N7021984-06-29029 June 1984 Diesel Engine 1A Component Revalidation Insp Final Rept ML20092J2441984-06-20020 June 1984 Duke Power Co 12 H Shift Experience ML20092J2671984-06-0808 June 1984 Util Advisor Evaluation Team Rept on Catawba Nuclear Station Shift Advisor Program,840606-08 ML20091J0561984-06-0101 June 1984 Diesel Engine 1A Component Revalidation Insp Rept ML20091L8721984-05-31031 May 1984 Sqrt Audit Resolution for Ser,Catawba Unit 1 ML20090G6731984-04-30030 April 1984 Nuclear Physics Methodology for Reload Design ML20083P9381984-04-17017 April 1984 Sqrt Audit Resolutions for Sqrt Audit Conducted 840313-16. W/Seven Oversize Drawings.Aperture Cards Are Available in PDR ML20087M6281984-03-28028 March 1984 Nonproprietary, Methodology for Addressing Superheated Steam Releases to Ice Condenser Containments ML20080U4541984-02-29029 February 1984 Rev 10 to Analysis of Hydrogen Control Measures at McGuire Nuclear Station 1999-05-31
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20217H0201999-09-30030 September 1999 Monthly Operating Repts for Sept 1999 for Catawba Nuclear Station,Units 1 & 2 ML20216E5401999-09-0707 September 1999 Special Rept:On 990826,discovered That Meteorological Sys Upper Wind Speed Cup Set Broken,Causing Upper Wind Channel to Be Inoperable.Cup Set Replaced & Channel Restored to Operable Status on 990826 ML20212B4711999-08-31031 August 1999 Monthly Operating Repts for Aug 1999 for Catawba Nuclear Station,Units 1 & 2 ML20217H0321999-08-31031 August 1999 Revised Monthly Operating Rept for Aug 1999 for Catawba Nuclear Station,Units 1 & 2 ML20211B1281999-08-31031 August 1999 Dynamic Rod Worth Measurement Using Casmo/Simulate ML20211A9791999-08-20020 August 1999 Safety Evaluation Granting Licensee Request for Approval of Proposed Relief from Volumetric Exam Requirements of ASME B&PV Code,Section Xi,For Plant,Unit 2 ML20211F3441999-08-17017 August 1999 Updated non-proprietary Page 2-4 of TR DPC-NE-2009 ML20211C1291999-08-17017 August 1999 ISI Rept Unit 1 Catawba 1999 RFO 11 ML20210R1051999-08-0606 August 1999 Special Rept:On 990628,cathodic Protection Sys Was Declared Inoperable After Sys Did Not Pass Acceptance Criteria of Bimonthly Surveillance.Work Request 98085802 Was Initiated & Connections on Well Anode Were Cleaned or Replaced ML20210S2891999-07-31031 July 1999 Monthly Operating Repts for July 1999 for Catawba Nuclear Station,Units 1 & 2 ML20212B4871999-07-31031 July 1999 Revised Monthly Operating Rept for July 1999 for Catawba Nuclear Station,Units 1 & 2 ML20209E4361999-07-0909 July 1999 SER Agreeing with Licensee General Interpretation of TS LCO 3.0.6,but Finds No Technical Basis or Guidance That Snubbers Could Be Treated as Exception to General Interpretation ML20196K6631999-07-0707 July 1999 Safety Evaluation Supporting Licensee 990520 Position Re Inoperable Snubbers ML20210S2951999-06-30030 June 1999 Revised Monthly Operating Rept for June 1999 for Catawba Nuclear Station,Units 1 & 2 ML20209H4501999-06-30030 June 1999 Monthly Operating Repts for June 1999 for Catawba Nuclear Station,Units 1 & 2 ML20209H4561999-05-31031 May 1999 Revised Monthly Operating Rept for May 1999 for Catawba Nuclear Station,Units 1 & 2 ML20206T4771999-05-31031 May 1999 Rev 3 to UFSAR Chapter 15 Sys Transient Analysis Methodology ML20196L1881999-05-31031 May 1999 Non-proprietary Rev 1 to DPC-NE-3004, Mass & Energy Release & Containment Response Methodology ML20196A0001999-05-31031 May 1999 Monthly Operating Repts for May 1999 for Catawba Nuclear Station,Units 1 & 2 ML20206P5201999-05-14014 May 1999 Safety Evaluation Accepting GL 96-05, Periodic Verification of Design-Basis Capability of Safety-Related Motor-Operated Valves ML20206N8391999-05-0404 May 1999 Rev 16 to CNEI-0400-24, Catawba Unit 1 Cycle 12 Colr ML20206R1811999-04-30030 April 1999 Monthly Operating Repts for Apr 1999 for Catawba Nuclear Station,Units 1 & 2 ML20196A0041999-04-30030 April 1999 Revised Monthly Operating Repts for Apr 1999 for Catawba Nuclear Station,Units 1 & 2 ML20206N8261999-04-22022 April 1999 Rev 15 to CNEI-0400-24, Catawba Unit 1 Cycle 12 Colr. Page 145 of 270 of Incoming Submittal Not Included ML20205S5551999-04-21021 April 1999 Safety Evaluation Accepting Response to GL 96-06, Assurance of Equipment Operability & Containment Integrity During Design Basis Accident Conditions ML20205N3651999-04-12012 April 1999 Safety Evaluation Accepting IPE of External Events Submittal ML18016A9011999-04-12012 April 1999 Part 21 Rept Re Defect in Component of DSRV-16-4,Enterprise DG Sys.Caused by Potential Problem with Connecting Rod Assemblies Built Since 1986,that Have Been Converted to Use Prestressed Fasteners.Affected Rods Should Be Inspected ML20206R1931999-03-31031 March 1999 Revised Monthly Operating Repts for Apr 1999 for Catawba Nuclear Station,Units 1 & 2 ML20205P9521999-03-31031 March 1999 Monthly Operating Repts for Mar 1999 for Catawba Nuclear Station,Units 1 & 2 ML20205P9561999-02-28028 February 1999 Revised Monthly Operating Repts for Feb 1999 for Catawba Nuclear Station,Units 1 & 2 ML20204C9111999-02-28028 February 1999 Monthly Operating Repts for Feb 1999 for Catawba Nuclear Station,Units 1 & 2 ML20203A2581999-02-0505 February 1999 Safety Evaluation of TR DPC-NE-3002-A,Rev 2, UFSAR Chapter 15 Sys Transient Analysis Methodology. Rept Acceptable. Staff Requests Duke Energy Corp to Publish Accepted Version of TR within 3 Months of Receipt of SE ML20204C9161999-01-31031 January 1999 Revised Monthly Operating Repts for Jan 1999 for Catawba Nuclear Station,Units 1 & 2 ML20199K8711999-01-13013 January 1999 Inservice Insp Rept for Unit 2 Catawba 1998 Refueling Outage 9 ML20199E3071998-12-31031 December 1998 Monthly Operating Repts for Dec 1998 for Catawba Nuclear Station,Units 1 & 2 ML20216F9931998-12-31031 December 1998 Piedmont Municipal Power Agency 1998 Annual Rept ML20205E9441998-12-31031 December 1998 1998 10CFR50.59 Rept for Catawba Nuclear Station,Units 1 & 2, Containing Brief Description of Changes,Tests & Experiments,Including Summary of Ses.With ML20206P2081998-12-31031 December 1998 Special Rept:On 981218,inoperability of Meteorological Monitoring Instrumentation Channels,Was Observed.Caused by Data Logger Overloading Circuit.Replaced & Repaired Temp Signal Processor ML20203A4101998-12-22022 December 1998 Rev 16 to CNEI-0400-25, Catawba Unit 2 Cycle 10 Colr ML20203A4041998-12-22022 December 1998 Rev 14 to CNEI-0400-24, Catawba Unit 1 Cycle 11 Colr ML20198B1341998-12-14014 December 1998 Revised Special Rept:On 980505,discovered That Certain Fire Barriers Appeared to Be Degraded.Caused by Removal of Firestop Damming Boards.Hourly Fire Watches Established in Affected Areas ML20196J8351998-12-0808 December 1998 Safety Evaluation Granting Relief Request Re Relief Valves in Diesel Generator Fuel Oil Sys ML20199E3221998-11-30030 November 1998 Revised MOR for Nov 1998 for Catawba Nuclear Station,Units 1 & 2 Re Personnel Exposure ML20198E3151998-11-30030 November 1998 Monthly Operating Repts for Nov 1998 for Catawba Nuclear Station,Units 1 & 2 ML20196C0251998-11-27027 November 1998 SER Accepting Clarification on Calibration Tolerances on Trip Setpoints for Catawba Nuclear Station ML20196A6881998-11-25025 November 1998 Safety Evaluation Granting Relief Request 98-02 Re Limited Exam for Three Welds ML20196D4041998-11-19019 November 1998 Rev 1 to Special Rept:On 980618,determined That Method Used to Calibrate Wind Speed Instrumentation Loops of Meteorological Monitoring Instrumentation Sys Does Not Meet TS Definition for Channel Calibration.Procedure Revised ML20195E5521998-10-31031 October 1998 Monthly Operating Repts for Oct 1998 for Catawba Nuclear Station,Units 1 & 2 ML20198E3261998-10-31031 October 1998 Revised Monthly Operating Repts for Oct 1998 for Catawba Nuclear Station,Units 1 & 2 ML20154M7661998-10-12012 October 1998 LER 98-S01-00:on 980913,terminated Vendor Employee Entered Protected Area.Caused by Computer Interface Malfunction. Security Retained Vendor Employee Badge to Prevent Further Access & Computer Malfunction Was Repaired.With 1999-09-07
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Attachment 6 SPDS HUMAN FACTORS PROGRAM SUISIARY PACKAGE CATAWBA NUCLEAR STATION Section I: Description of SPDS Human Factors Program Section II: Summary of Results Section III: Listing of Applicable Correspondence Roland H. White Control Complex Engineering Design Engineering Department l
l April 23, 1986 Page 1 of 9 8607250146 860715 PDR ADOCK 05000414 p PDR
Attachment 6 I. Description of SPDS Human Factors Program General The Safety Parameter Display System (SPDS) Human Factors Program was developed to ensure that the final SPDS display
- system design would provide direct, readily usable informa-2 tion, organized in an effective format to support operator task requirements. The Human Factors Program provided for the review and evaluation of the SPDS displays and operator interface during both the initial concept and development stage of the SPDS system design, and after the implementation of displays on the actual SPDS system hardware.
The activities in the Human Factors Program were performed by members of the Control Room Review Team. These activities were conducted simultaneously with Control Review activities and were coordinated by the Control Room Review Steering Committee. A listing of the members of the Review Team and the Steering Committee, and a description of the Control Room Review and the methodology employed is contained in the Duke Power Company Response to Supplement 1 to NUREG-0737 for Catawba Nuclear Station, Volume 1, Section 3.0.
l The Human Factors Program was conducted in three phases; (1) review and comments during the concept and design stage of the SPDS, (2) a task analysis of the SPDS primary and supporting displays at the conclusion of the concept and design stage of the SPDS, and (3) a human f actors survey of the displays and operator interface after implementation on the actual SPDS hardware in the Control Room.
. Task Analysis The task analysis activity of the SPDS Human Factors Program was conducted using the control board mockup which had been fabricated for use in the task analysis activity of the Control Room Design Review (CRDR). An event scenario was developed using the plant emergency procedures and the Westing-house Emergency Response Guidelines. The scenario provided an
- ordered framework of a set of possible responses to an initia-i ting event against which the SPDS system was evaluated.
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1 Attachment 6 From the event scenario, plant parameter inputs to the SPDS logic were identified. Valuec for these parameters were developed consistent with plant conditions for several selected time intervals during the duration of the scenario.
selected time intervals were chosen to be one minute intervals from 10 minutes into the scenario until 30 minutes after initiation.
The SPDS logic output states were determined for each time interval using the specific plant parameter values. Photo-graphic slides were then produced for each time interval to represent how each SPDS and supporting display would appear for that time interval, t A walk-through of the event scenario was performed by a task analysis team consisting of a senior reactor operator and a mechanical / nuclear systems engineer. During the walk-through, the operator performed the task actions required while the engineer served as observer. In addition, several other members of the Control Room Review Team served as observers
, and slide coordinators.
The proper time sequenced slides for the SPDS displays were projected onto the SPDS display CRT mockup to simulate the
- action of this display during the scenario. Slides represent-ing the proper display for any of the secondary supporting displays at a particular time interval were projected onto the supporting display CRT mockup in response to operator command, simulating the call-up feature of the supporting display system.
The usability and effectiveness of the displays were evaluated by the task analysis team using a set of pre-selected task l analysis principles. These principles, developed from those used in the CRDR task analysis activity, covered such items as i
logical ordering of displays, terminology and abbreviations, labeling, coding, usability of displayed information, and operator task support. In general, the task analysis activity l evaluated the SPDS and supporting displays to determine if the l displays provided a logical, readily usable format to support l the following operator tasks:
l o Monitor Critical Safety Function Status (CSF) o Observe CSF status changes o Determine which CSF is degraded o Determine the severity of the degradation o Identify component / functional area out-of-tolerance Page 3 of 9 i
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Attachment 6 o Determine which confirming displays and restoration procedures to use o Monitor restoration progress o Monitor remaining CSF status during restoration Human Factors Survey A human factors survey of the actual SPDS and secondary supporting displays as implemented on the control room CRT displays was performed. During the survey the control room CRT displays and the operator keyboard were used to call-up, observe, and review each separate display. In addition, the displays were reviewed during a simulated alarm condition.
The survey evaluated the format and arrangement of the dis-plays and the operator keyboard interface using applicable survey principles from the Control Room Survey Principles checklist which was derived from NUREG-0700 for use in the CRDR. These principles covered areas, such as, color usage, character height, room lighting and glare, presentation of data, labels and coding, operator message presentation, and the arrangement and use of the operator keyboard interface.
II. Summary of Results The results from both the task analysis activity and the human factors survey were documented in the form of recommendations for design changes to the SPDS and secondary supporting displays. These recommendations concerned items such as audible alarming upon a change of CSF status, the addition of CSF status blocks to the bottom of the supporting displays in addition to those on the primary SPDS display, alarm message format, display function button position on the operator keyboard, and double spacing of lists for readability. The human factors recommendations from each review activity were resolved and required changes to the SPDS display system were implemented.
III. Listing of Applicable Correspondence A. McGuire Correspondence Date To From Subject 03-29-82 W A Coley C E Muse Control Room Review C P Rogers SPDS Development -
Input Review Page 4 of 9
Attachment 6 Date To From Subject 03-29-82 W A Coley C A Little Control Room Review J O Crow SPDS Pilot Program Dev.
03-30-82 W A Coley C A Little Control Room Review SPDS Development 04-02-82 T C McMeekin W A Coley Announcing Meeting on R S Darke 4/7/82 to discuss CRT H R Lowery Display R B Travis J W Hampton L E Schmid N A Rutherford W H Rasin R E Hall C A Little J O Crow M B Laney C P Rogers G A Copp 05-21-82 Memo to Control W A Coley NRC Staff Review of Rm Rev Steer SPDS Designs Comm 06-03-82 Memo For File C A Little SPDS Responsibility 06-07-82 T C McMeekin R L Brown Comments on SPDS H R Lowery G D Gilbert J W Hampton B C Moore R E Hall N A Rutherford W A Coley W H Rasin C A Little H L Davenport 06-22-82 Memo For File L T Harbinson Meeting items 10-13-82 Memo For File R L Brown SPDS supporting displays 1
! 10-18-82 M R Crews R L Brown Control Room Review l Steering Committee l SPDS Status 1
11-04-82 R L Brown M R Crews SPDS Secondary Display Page 5 of 9
l Attachment 6 Date To From Subject 11-05-82 R L Brown L Firebaugh Supporting Displays 11-05-82 P M Abraham K S Canady Control Room Review ERG /EOP/ Task Analysis inLLriaan 11-30-82 C A Little R L Brown Review of comments from 10-13-82 letter 12-01-82 R L Brown L J Cope Supporting Displays 12-08-82 Memo For File R L Brown Meeting on Supporting Displays 01-06-83 R L Brown L T Harbinson Revised SPDS logic C P Rogers diagrams 02-04-83 Memo To File L T Harbinson Supporting Display 02-14-83 P H Barton M R Crews Integrating of SPDS
+
B C Moore w/ operator roles and functions 02-16-83 R L Brown L T Harbinson Control Room Review C P Rogers Team comments on logic diagrams 02-16-83 T C McMeekin L T Harbinson SPDS Evaluation R L Brown H L Davenport 03-17-83 M R Crews R L Brown Supporting Displays G M Haynes G D Gilbert B Ferguson D Robinson H L Davenport L R Frick R C Collins C P Rogers L Firebaugh C A Little 03-23-83 R L Brown G Swindlehurst Review of SPDS Logic and Displays l
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l Attachment 6 Date To From Subject 04-06-83 R L Brown M R Crews Integrating SPDS with H R Lowery Operator Roles and L Firebaugh Functions J W Hampton B C Moore R C IIsil N A Rutherford R S Darke W H Rasin C A Little T C McMeekin 05-02-83 R L Brown L Firebaugh McGuire Comments on SPDS Review by Reactor Safety
, 05-03-83 R L Brown C P Rogers MNS/CNS Review of I SPDS Logic and Displays 05-12-83 G W Hallman R L Brown Shift Technical C A Little Advisor's Panel 05-23-83 Memo To File R L 3rown Resolution of Reactor Safety Unit Comments 06-28-83 R L Brown L T Harbinson Prompt Event Alarms 09-12-83 R L Brown L T Harbinson Comments on Rev. II of SPDS Logic 10-04-83 G E Vaughn R L Brown Shift Technical i Advisor's CRT Panels 10-07-83 R L Brown G Swindlehurst Review of SPDS Logic W A Hallman and Displays C P Rogers 10-21-83 File C P Rogers Paper on Resolution of Comments to McG SPDS from Reactor Safety 10-24-83 G E Vaughn B C Moore Shift Technical Advisor's CRT Panels 10-24-83 R L Brown L T Harbinson SPDS/ Supporting Displays Review Page 7 of 9
Attachment 6 Date To From Subject 10-25-83 Memo To File L T Harbinson SPDS Evaluation 10-26-83 T C McMeekin L T Harbinson SPDS Evaluation R L Brown 11-04-83 R L Brown G E Vaughn Shift Technical Advisor's CRT Panels 11-11-83 M D McIntosh R L Brown System description G D Gilbert for SPDS H B Tucker C A Little G B Swindlehurst R M Koehler S Frye L Duncan 11-17-83 R M Koehler R L Brown SPDS Training Slides S Frye M D McIntosh G Gilbert 12-02-83 T C McMeekin M R Crews SPDS Evaluation R L Brown 12-06-83 H B Tucker R L Brown Shift Tech. Advisor C A Little CRT Locations B C Moore 12-22-83 Memo To File R H White Control Room Review Team Evaluation of SPDS Operator Displays 01-11-84 T C McMeekin R L Brown Human Factors Review M R Crews 02-07-84 R L Brown M R Crews Human Factors Review 02-14-84 R L Brown R G Morgan Shift Technical Advisor CRT Locations 02-15-84 G W Hallman R L Brown Shift Technical C A Little Advisor Panels T C McMeekin H L Davenport M R Crews 02-15-84 M R Crews R L Brown McGuire ideas for CRT Page 8 of 9
Attachment 6 Date To From Subject 02-15-84 K S Canady R L Brown Supporting Displays G B Swindlehurst 03-13-84 Memo For File R L Brown Supporting Displays 03-14-84 P H Barton A L Kinley STA Station and R G Morgan Control Room Layout 07-30-84 R L Brown C J Wylie Results of Human C B McFadden Factors Survey of CNS L R Frick SPDS 08-06-84 G W Hallman R L Brown Revisions to SPDS per C A Little Human Factors Review K S Canady G B Swindlehurst B. Catawba Correspondence Date To From Subject
! 04-01-82 W A Coley J W Hampton Control Room Review SPDS Development 02-18-83 P H Barton J W Hampton Integrating SPDS with B C Moore operator roles &
functions
'i 03-30-83 M R Crews B C Moore Integration of SPDS Operator Roles 02-14-84 R L Brown R G Morgan Shift Technical Advisor CRT Locations 06-15-84 L R Frick S C Mattix Programming Revision Request 06-15-84 R L Brown S C Mattix Human Factors Survey 07-30-84 R L Brown C J Wylie Summary of Human Factors i'
C B McFadden Recommendations for CNS L R Frick SPDS i
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