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Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML20148U0111997-06-17017 June 1997 Confirmatory Survey of Group E Effluent Discharge Pathway Areas Fsv Nuclear Station Platteville,Co ML20133D7661996-09-16016 September 1996 Confirmatory Survey Plan for Fsv Nuclear Station Decommissioning Project ML20129A4621996-09-11011 September 1996 Rev 0 to Fsv Decommissioning Project Final Survey Requirements for Liquid Effluent Pathway ML20100L3581996-02-22022 February 1996 Proposed Tech Specs,Submitting Corrected Version of Plant Decommissioning TS Updated to Reflect All Approved Amends ML20097C2601996-01-17017 January 1996 Confirmatory Survey Activities Plan for Fsv Nuclear Station PSC Platteville,Co ML20101F2091995-09-18018 September 1995 Issue 7 to DPP 5.4.2, Odcm ML20084B8801995-05-25025 May 1995 Rev 1 to Fsv Nuclear Station Decommissioning Project Final Survey Plan for Site Release ML20084B6881995-05-10010 May 1995 Issue 5 to Fire Protection Operability Requirements (Fpor) FPOR-7, Fire Extinguishers ML20082K2461995-04-14014 April 1995 Proposed Decommissioning Tech Specs Administrative Control 5.3.1,reflecting Organizational Changes That Impact Membership of Decommissioning Safety Review Committee ML20082T2151995-04-12012 April 1995 Issue 7 to Fire Protection Operability Requirements (Fpor) FPOR-12, Fire Detectors ML20082B9411995-03-17017 March 1995 Confirmatory Survey Plan for Repower Area,Fort St Vrain, Platteville,Co ML20082C0801995-03-16016 March 1995 Proposed Confirmatory Survey Plan for Repower Area,Fort St Vrain,Platteville,Co ML20082B9821995-03-15015 March 1995 Instrumentation Comparison Plan Between Orise & Fort St Vrain ML20086S2471995-02-0909 February 1995 Decommissioning Plan for Fort St Vrain Nuclear Generating Station ML20077C7171994-11-30030 November 1994 Issue 9 to FPOR-14, Fire Protection Operability Requirements ML20078C0641994-10-12012 October 1994 Revised Fire Protection Operability Requirements,Including Issue 21 to Depp Table of Contents,Issue 2 to FPOR-22 & Issue 3 to FPOR-23 ML20081J7951994-09-15015 September 1994 Issue 5 to DPP 5.4.2, Odcm ML20063M1551994-02-17017 February 1994 Rev 0 to Fsv Nuclear Station Decommissioning Project Final Survey Plan for Site Release ML20057A6151993-08-30030 August 1993 Issue 2 to FPOR-23, Fire Water Makeup Sys ML17291B3261993-05-18018 May 1993 Proposed TS Section 2.2 Re Activated Graphite Blocks,Section 2.4 Re Channel Calibr & SR 3.2.1 Re Verification of Reactor Bldg Pressure & SR 3.2.2 Re Verification of Pressure Drop Across Each HEPA Filter ML20118B2141992-09-25025 September 1992 Proposed Decommissioning Tech Specs Replacing Radiation Safety with Nuclear Safety, Revising Applicability Requirements for Specs Dealing W/Reactor Bldg Confinement Integrity & Clarifying Items Re Unreviewed Safety Questions ML20114D6871992-09-0101 September 1992 Tritium Leach Test on H-327 Graphite ML20096H1961992-05-19019 May 1992 Decommissioning TS Deleting Section 4.2.15 Re LCO 4.2.15 Covering Pcrv Cooling Water Sys Temps ML20095B0951992-04-14014 April 1992 Proposed Tech Specs Re Organization,Review & audit-administrative Controls ML20094L2831992-03-19019 March 1992 Proposed Tech Specs Re Controls & Limits Appropriate for Decommissioning ML20086C5301991-11-15015 November 1991 Proposed Tech Spec Limiting Condition for Operation 4.2.15 Re Pcrv Cooling Water Sys Temps ML20079M4261991-10-11011 October 1991 Revised Abnormal Operating Procedures,Reflecting Deletion of Issue 9 of EP Class ML20091D7631991-10-11011 October 1991 Proposed,Revised Limiting Condition for Operation 4.2.15 Re Prestressed Concrete Reactor Vessel Cooling Water Sys Temp ML20082L9311991-08-30030 August 1991 Proposed Tech Specs Re Decommissioning ML20082H8851991-08-16016 August 1991 Issue 2 to Abnormal Operating Procedure AOP-I-2, Chemical, Petroleum & Hazardous Waste Spill Response ML20091C4141991-08-0202 August 1991 Issue 58 to Abnormal Operating Procedure AOP-L, Loss of Instrument Air Header ML20024H3341991-05-10010 May 1991 Nonproprietary Rev 2 to FSV-P-SCP-100, Fort St Vrain Initial Radiological Site Characterization Program Program Description ML20072V5291991-04-12012 April 1991 Revised Defueling Emergency Response Plan,Including Section 1 Definitions,Section 2 Scope & Applicability,Section 3 Summary of Fsv Derp,Section 4 Emergency Classifications & Section 5 Emergency Organization ML20070V6871991-03-20020 March 1991 Issue 55 to Abnormal Operating Procedure AOP-R, Loss of Access to Control Room ML20072S0521991-03-15015 March 1991 Public Version of Revised Crisis Mgt Implementing Procedures,Including Rev 9 to CMIP-11, Classification of Emergency for McGuire Nuclear Station & Rev 11 to CMIP-12, Classification of Emergency for Oconee Nuclear Station ML20066J1171991-02-15015 February 1991 Issue 56 to Intro Section of Abnormal Operating Procedure (Aop),Issue 58 of AOP-A,Issue 58 to AOP-B,Issue 56 of AOP D-1 & Issue 2 of RERP-TRANSPORTATION ML20066A3781990-12-21021 December 1990 Proposed Decommissioning Tech Specs Re Reactor Bldg Integrity,Reactor Bldg Ventilation Exhaust Sys,Radiation Monitoring Instrumentation & Pcrv Shielding Water Tritium Concentration ML20059L5891990-09-14014 September 1990 Proposed Tech Specs Changing Design Features Section 6.1 to Permit Removal of CRD & Orifice Assemblies from Core Regions Defueled in Support of Plant Closure Activities ML20058N1071990-08-10010 August 1990 Issue 56 to AOP-I, Discussion of Fire ML20042F3151990-04-26026 April 1990 Proposed Tech Specs Re Defueling ML20006B7921990-01-25025 January 1990 Proposed Tech Specs Re Administrative Title Changes to Section 7.1 ML19332E8901989-12-0404 December 1989 Proposed Tech Specs Re Reactivity Control & Control Rod Pair Position Requirements During Shutdown ML19332F3561989-12-0404 December 1989 Proposed Tech Specs Re Limiting Condition for Operations 4.7.3, Fuel Storage Wells & 4.7.5, Instrumentation. ML19332C8151989-11-21021 November 1989 Proposed Tech Specs Revising Items 2.D.(1) & 2.D.(4) Re Max Power Level & Early Shutdown,Respectively ML20064B2111989-11-0909 November 1989 Fort St Vrain Cycle 4 RT-500L Test Rept ML19324B6961989-10-30030 October 1989 Proposed Tech Specs Re Reactor Core & Reactivity Control ML19327B1321989-10-13013 October 1989 Proposed Tech Specs,Reflecting Deleted Limiting Conditions of Operations 4.1.2 Through 4.1.6,deleted Surveillance Requirements 5.1.1,5.1.2,5.1.3 & 5.1.5 & Newly Added Reactivity Control Section ML19351A3271989-10-13013 October 1989 Proposed Tech Specs 6.1 Re Defueling Phase Document Design Features ML20248G4731989-10-0101 October 1989 Proposed Tech Specs Re End of Operations ML20248G4461989-09-30030 September 1989 Proposed Tech Specs Re Chlorine Detection & Alarm Sys & Control Room Emergency Ventilation Sys 1997-06-17
[Table view] Category:TEST/INSPECTION/OPERATING PROCEDURES
MONTHYEARML20148U0111997-06-17017 June 1997 Confirmatory Survey of Group E Effluent Discharge Pathway Areas Fsv Nuclear Station Platteville,Co ML20133D7661996-09-16016 September 1996 Confirmatory Survey Plan for Fsv Nuclear Station Decommissioning Project ML20129A4621996-09-11011 September 1996 Rev 0 to Fsv Decommissioning Project Final Survey Requirements for Liquid Effluent Pathway ML20097C2601996-01-17017 January 1996 Confirmatory Survey Activities Plan for Fsv Nuclear Station PSC Platteville,Co ML20101F2091995-09-18018 September 1995 Issue 7 to DPP 5.4.2, Odcm ML20084B8801995-05-25025 May 1995 Rev 1 to Fsv Nuclear Station Decommissioning Project Final Survey Plan for Site Release ML20084B6881995-05-10010 May 1995 Issue 5 to Fire Protection Operability Requirements (Fpor) FPOR-7, Fire Extinguishers ML20082T2151995-04-12012 April 1995 Issue 7 to Fire Protection Operability Requirements (Fpor) FPOR-12, Fire Detectors ML20082B9411995-03-17017 March 1995 Confirmatory Survey Plan for Repower Area,Fort St Vrain, Platteville,Co ML20082C0801995-03-16016 March 1995 Proposed Confirmatory Survey Plan for Repower Area,Fort St Vrain,Platteville,Co ML20082B9821995-03-15015 March 1995 Instrumentation Comparison Plan Between Orise & Fort St Vrain ML20086S2471995-02-0909 February 1995 Decommissioning Plan for Fort St Vrain Nuclear Generating Station ML20077C7171994-11-30030 November 1994 Issue 9 to FPOR-14, Fire Protection Operability Requirements ML20078C0641994-10-12012 October 1994 Revised Fire Protection Operability Requirements,Including Issue 21 to Depp Table of Contents,Issue 2 to FPOR-22 & Issue 3 to FPOR-23 ML20081J7951994-09-15015 September 1994 Issue 5 to DPP 5.4.2, Odcm ML20063M1551994-02-17017 February 1994 Rev 0 to Fsv Nuclear Station Decommissioning Project Final Survey Plan for Site Release ML20057A6151993-08-30030 August 1993 Issue 2 to FPOR-23, Fire Water Makeup Sys ML20079M4261991-10-11011 October 1991 Revised Abnormal Operating Procedures,Reflecting Deletion of Issue 9 of EP Class ML20082H8851991-08-16016 August 1991 Issue 2 to Abnormal Operating Procedure AOP-I-2, Chemical, Petroleum & Hazardous Waste Spill Response ML20091C4141991-08-0202 August 1991 Issue 58 to Abnormal Operating Procedure AOP-L, Loss of Instrument Air Header ML20024H3341991-05-10010 May 1991 Nonproprietary Rev 2 to FSV-P-SCP-100, Fort St Vrain Initial Radiological Site Characterization Program Program Description ML20072V5291991-04-12012 April 1991 Revised Defueling Emergency Response Plan,Including Section 1 Definitions,Section 2 Scope & Applicability,Section 3 Summary of Fsv Derp,Section 4 Emergency Classifications & Section 5 Emergency Organization ML20070V6871991-03-20020 March 1991 Issue 55 to Abnormal Operating Procedure AOP-R, Loss of Access to Control Room ML20072S0521991-03-15015 March 1991 Public Version of Revised Crisis Mgt Implementing Procedures,Including Rev 9 to CMIP-11, Classification of Emergency for McGuire Nuclear Station & Rev 11 to CMIP-12, Classification of Emergency for Oconee Nuclear Station ML20066J1171991-02-15015 February 1991 Issue 56 to Intro Section of Abnormal Operating Procedure (Aop),Issue 58 of AOP-A,Issue 58 to AOP-B,Issue 56 of AOP D-1 & Issue 2 of RERP-TRANSPORTATION ML20058N1071990-08-10010 August 1990 Issue 56 to AOP-I, Discussion of Fire ML20154M4361988-09-0909 September 1988 Rev a to EE-FP-0005, Evaluation of Cable Trays Outside of Congested Cable Area ML20154L8751988-05-26026 May 1988 Simulation Facility Program Plan ML20154L8911988-03-31031 March 1988 Rev 2 to Guidance for Development of Simulation Facility to Meet Requirements of 10CFR55.45 ML20148Q4681988-03-31031 March 1988 Rev 2 to Guidance for Development of Simulation Facility to Meet Requirements of 10CFR55.45 ML20150E3141988-03-18018 March 1988 Issue 1 to Procedure SR 5.4.1.3.8.abcd-R1, Steam Line Rupture Detection/Isolation Sys (Slrdis) Calibr & Testing for Panel I-93543 ML20150E2901987-12-31031 December 1987 Issue 5 to Procedure SR 5.3.4b1-A Loop I Shutdown Cooling Power Operated Valve Test ML20238E3541987-08-0707 August 1987 Rev a to EE-ISI-002, Condensate Line Erosion Insp Program ML20236N8681987-08-0505 August 1987 Exercise Manual Fort St Vrain Nuclear Generating Station Nrc/Fema Graded Exercise 870805 ML20235Y7861987-07-29029 July 1987 Issue 2 to MAP-4, Maint Dept Personnel Experience, Qualification & Training Requirements ML20237J6921987-06-0909 June 1987 Issue 6 to MQCIM-1, Maint QC Insp Program. Annotated Page to Rev 4 to Updated FSAR Encl ML20235Y7731987-05-25025 May 1987 Training Mgt Procedure Index ML20237J7151987-05-0101 May 1987 Issue 12 to Q-18, QA Monitoring & Audit Program ML20215H9731987-04-30030 April 1987 Revised Buckle Users Manual:Creep Collapse of Thin-Walled Circular Cylindrical Shells Subj to Radial Pressure & Thermal Gradients ML20215H6101987-04-10010 April 1987 Program Plan for Integrated Validation of NUREG-0737 Initiatives ML20215H6031987-04-10010 April 1987 SOAP-2,Issue 1 of Guidelines for Preparation of Emergency Procedures ML20215H5951987-04-10010 April 1987 Procedures Generation Package:Public Svc Co of Colorado Fort St Vrain Nuclear Generating Station ML20150E3041987-03-20020 March 1987 Issue 1 to Procedure SR 5.4.1.3.8.abcd-R2, Steam Line Rupture Detection/Isolation Sys (Slrdis) Calibr & Testing for Panel I-93544 ML20237J7231987-02-20020 February 1987 Issue 5 to QAAP-1, Planning & Scheduling Fort St Vrain QA Audits ML20212B3081987-02-15015 February 1987 Issue 7 to Procedure G-9, Controlled Work Procedures ML20210E3001987-02-0303 February 1987 Revised Administration Procedures Consisting of Issue 7 to G-3, Action Request-Preparation & Processing, Issue 21 to G-2, Fort St Vrain Procedure Sys & Issue 6 to G-6, Compliance w/10CFR21 Requirements ML20210A7571987-01-30030 January 1987 Fort St Vrain 1987 Power Ascension Plan ML20237J7421987-01-19019 January 1987 QA Audit QAA-502-87-01, Audit Plan - QA Program for Transport of Radioactive Matls ML20212B2851986-10-24024 October 1986 Issue 10 to Procedure Q-3, Design Control Sys ML20238E3461986-10-0202 October 1986 Rev C to EE-ISI-0001, Extraction Steam Lines & Turbine Vent & Drain Lines Erosion Insp Program 1997-06-17
[Table view] |
Text
, PUBLIC SERVICE COMPANY OF COLORADO FORT ST. VRAIN NUCLEAR GENERATING STATION DD-CRT-1
- ISSUE A Page 1 of 5 DESIGN DIRECTIVE FOR CATHODE RAY TUBE SELECTION PRE , Y: REVIEWED BY: APPROVED BY:
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FOREWORD: Cathode Ray Tubes (CRTs) providing interface between the computer output and operating personnel shall be selected for maximum readability. While software generation, CRT location and room lighting conditions are important considerations in determining readability, the factors given in this Design Ofrective shall be applied in the FSV Control Room.
Where given factors are contingent upon software, location, and room lighting conditions, the associated Design Directives are to be evaluated in conjunction with this directive prior to selecting or specifying CRTs.
SELECTION CONSIDERATIONS I. SCREEN LUMINANCE - The following screen background considerations for ambient light environments are preferred; however, where conformity to existing installations is a consideration, only the contrast ration must be met.
A. For low to medium ambient illumination environments (typically 5 to 20 footcandles), utilize light characters on a dark background, with a screen luminance of 23 foot lambert (ft-L) minimum and 45 ft-L preferred.
Contract between light characters and a dark screen background shall be 15:1 minimum and 20:1 preferred, in 20 ft-L of ambient light.
B. For medium to high ambient illumination environm1nts (typically 20 and above footcandles), utilize dark characters on a light background, with a screen background luminance of 23 foot-Lamberts (ft-L) minimum and 46 ft-L preferred.
Contrast between dark characters and a light screen background shall be 1:15 ft-L minimum and 1:20 preferred, in 20 ft-L cf ambient light.
8511060291 851029 PDR ADOCK 05000267 F PDR
PUBLIC SERVICE COMPANY OF COLORADO FORT ST. VRAIN NUCLEAR GENERATING STATION
' DD-CRT-1 ISSUE A Page 2 of 5 II. GEOMETRIC DISTORTION -
The cumulative effects of all geometric distortion shall not displace any point within the viewable area of the screen from its correct position by more than 5% of picture height.
III. RESOLUTION -
Discrimination of fine detail is a function of the number of scan lines or addressable points
(" resolution elements") per unit length.
O
.) A. CRTs for displaying simple aplha-numeric text shall have a minimum of 20 resolution elements per inch.
- 8. CRTs for displaying complex symbols and graphic detail shall have a minimum of 100 resolution elements per inch.
C. Complex symbols which must be distinguished from other complex shapes shall have a minimum of 10 resolution elements for the longest dimension of the
. symbol.
h D. Alpha-numeric characters shall have a minimum of 10 resolution elements per character height.
IV. REGENERATION RATE - The regeneration rate for a particular CRT display shall be above the critical frequency at s fusion so that the occurrence of disturbing flicker is not perceptible.
V. SYMBOLS AND CHARACTERS The dimensional factors of data displayed on a CRT take on greator significance because of the movement of operators from cne benchboard position to another in a control room or other operating area. Distance from the operator to the screen is, therefore, variable, and must be taken into account during CRT selection. As an operator's distance from the CRT increases, the perceived dimensicns of CRT characters, symbols, spacing, etc. decreases proportionately because of a reduction of the " visual angle" (see figure 1). This is the vertical angle subtented at the eye by a viewed object, symbol, or character, utually expressed in minutes of arc. For visual angles less than 600 minutes, this relationship is shown by:
(57.3) (60) L a=
0 FORM 372 22 3643
PUBLIC SERVICE COMPANY OF COLORADO FORT ST. VRAIN NUCLEAR GENERATING STATION g, ,
ISSUE A Page 3 of 5 where "L" is measured perpendicular to the line of sight.
Under optimum conditions (illumination, contrast, etc.)
the human eye can identify characters of the alphabet at visual angles of 5 minutes of arc (defining 20:20 vision).
Since presentations on CRT displays in an operational environment do not approach the optimum conditions of vision testing, this lower level must be increased.
^
g %
% VISUAL ANGLE (4 LENGTH (L) b'p ~
f-I (DISTANCE (D) l FIGURE 1 Visual angle as a function of
. distance and character size.
A. SYMBOL SIZE -
When a displayed symbol of complex shape is to be distinguished from another symbol shape that is also complex, the visual angle of the symbol shall subtend not less than 20 minutes of arc at the required viewing distance.
B. ALPHA-NUMERIC CHARACTER SIZE
- 1. The height of alpha-numberic characters shall have a visual angle of not less than 12 minutes of arc at the required viewing distance.
- 2. Alpha-numberic characters should be uppercase letters. .
C. CHARACTER WIDTH-TO-HEIGHT RATIO -
The width-to-height ration for alpha-numerics shall be between 3:5 and 1:1.
D. LINE (or dot) WIDTH-TO-CHARACTER-HEIGHT RATIO - line (or dot) width-to-character-height ratio shall be between 1:5 and 1:10.
E. GRAPHICS -
A graphic line will appear continuous if the separation between addressable points, or resolution elements, is less than one minute of arc.
To provide the illusion of continuity, graphic lines shall contain a minimum of 50 resolution elements per inch.
PorM 372 22 3643
PUBLIC SERVICE COMPANY OF COLORADO FORT ST. VRAIN NUCLEAR GENERATING STATION DD-GT-1 ISSUE A Page 4 of 5 F. CHARACTER AND SYMBOL SEPARATION
- 1. Horizontal separation between characters or symbols shall be between 10*.' and 65% of character or symbol height.
- 2. Separation shall be not less than 25% of character or symbol height when any of the following degraded conditions exists:
When character or symbol width is less than 85% of height; When character or symbol luminance is less than 12 ft-L; When luminance contrast is less than 88%;
When CRT screen location is greater than 35' to the left or right of the operator's straight-ahead line of sight; When the visual angle subtended by symbol height is less than 15 minutes of arc; When the visual angle subtended by character height is less than 12 minutes of arc.
G. CHARACTER SYTLE (FONT)
- 1. Simple character fonts shall be used, with no serifs, variable stroke widths, slanting, etc.
- 2. When dot-matrix characters are used, a 5x7 dot matrix is considered a minimum with a 7x9 matrix preferred.
- 3. Character styles such as Lincoln / Mitre or Leroy shall be used.
VI. CRT DISPLAY CONTROLS A. Luminance (brightness), and contrast controls shall be visible and accessible from the operator's position. (control location behind hinged panels is acceptable, provided the panel when open, does not restrict operator access or vision.)
POMM 372 22 3643
l PUBLIC SERVICE COMPANY 'OF COLORADO FORT ST. VRAIN NUCLEAR GENERATING STATION gg_gg7,7 ISSUE A Page 5 of 5 1
- 8. A deguassing control shall be visible and accessible from the operator's position, if manually actuated daguassing is required as a part of routine operation.
C. Operator controls shall conform to the following guidelines:
- 1. The minimum distance between the outermost gripping surface of any rotary control and any other control or panel structure shall be one (1) inch.
- 2. The minimum distance between the outermost circumferential edge of any pushbutton and other control or panel structure shall be one-half (1/2) inch.
- 3. Rotary knob length shall be a minimum of five-eighths (5/8) inch in length.
- 4. Rotary knob mean diameter shall be minimum of one-half (1/2) inch.
ASSOCIATED DIRECTIVES 00-00 Requirements and Guidance for Preparing Design Directives DD-CRL Cathode Ray Tube Location DD-SLS Screen Layout and Structuring SOURCE MATERIALS AND REFERENCES NUREG-0700 Human Factors in Engineering, McCormick, 1976 FORM J72 22 364