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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
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Text
PUBLIC SERVICE COMPA N Y U t- COLUHADO FORI ST VR AIN NUCLE AR GENE R AT!NG ST ATION DD-CRL-1 1ssue A 6
Page 1 of 6 DESIGN 0:RECTIVE for CATHODE RAY TUBE
- LOCATION PREPARED BY: REVIEWED BY: APPROVED BY:
lht) ~ Is & '[bg hy h
/ 4 FOREWORD: Cathode Ray Tubes (CRTs) providing interface between the computer output and operating personnel shall be located for maximum readability with respect to the operators position and activity with the operating environme,t. The location of CRT displays falls in three categories: t,a) the CRT is mounted in a desk-type console at whicn the operat)r is seated; (b) the CRT is mounted above a benchboard or canel with tne operator having some lateral freecem of movement at tN work station; (c) the CRT is mou,ted on a stand, or pe'-haps on a desktop, with some capability for rotating or moving it to suit the needs of a variety of users. The guidance in this directive deals with those factors which should be considered regardless of type of installation, as well as the parameters which are dependent on the type of installation and the rature of the physical relationship between CRT and operator.
SELECTION CONSIDERATICNS I. VIEWING OISTANCE - Viewing distance should be greater than 18 inches.
II. VIEWING ANGLE - The minimum angle between the operator's actual line-of-sight (LOS) as measurec from the acerator's normal wark station, and tne plane of the display screen shall be 45 or greater in either the horizontal or vertical direction. See Figure 1)
III. MOUNTING IN CONSOLES - When CRTs are permanently mounted in consoles, the console configuration, dimensions, and type of use (such as seated, sit-stand, or standing) affects the CRT/ operator interface. Consoles in which CRTs are installed shall conform to the guidelines of directive CON-1.
IV. VISIBILITY OF DATA -
All data and messages on the CRT screen shall be within the unoDstructed view of an I operator at the normal work station.
l 8511060280 851029 l hDR ADOCK 05000267 n PDR FORM 372 22 3643
PUBLIC SERVICE COMPANY OF COLORADO FORT ST VRAIN NUCLE AA GENERATING STATION CD{RM Issue A Page 2 of 6 V. REFLFCTED GLARE CRT screens shall be installed to
_ minim ze or eliminate reflected light (or glare) at normal i
operatar viewing angles.
VI. SREEEN .UMINANCE - Ambient illumination should contribute no more t>an 25% to screen luminance through diffuse reflection and phosphor excitation.
VII. SCREEN LOCAT.'ON, SEATED OPERATORS A. CRT di s,,l ay s which require frequent or continuous monitorin,1, or which may display important (e.g.,
alarm) in'ormation, shall be located within the following limits as measured from the normal operator work station (see figure 2).
- 1. Horizontal limits-Not more than 35 to the left or tight of the operator's straight-ahead LOS.
- 2. Vertical lirits-Not more than 20 above and 40*
below the operator's horizontal LOS.
B. CRT displays which do not require frequent or continuous monitoring and which will not display important (e.g., alarm) i n .'o rma ti o n , shall be located whithin the foilowing limits (as measured from normal operator work stations which permit full operator head and eye rotation (see figure 3).
- 1. Horizontal limits-Net more than 95* to the lef t or right of the operator's straight-ahead LOS.
- 2. Vertical limits-Not more than 70 above and 90 below the operator's horitontal LOS.
VIII. SCREEN LOCATION, STANDING GPERATORS A. CRT displays which require freq.ent or continuous monitoring, or which may display 'mportant (e.g.,
alarm) information, shall be located within the following limits as measured from the normal operator work station:
- 1. Horizontal limits-Not more tha.1 35* to the lef t or right of the operator's st aight-ahead LOS.
- 2. Vertical limits-Not more than 35 above and 25 below the operator's horizontal LOS.
FORM 372 22 36 4 J
PUBLIC SERVICE COMPANY OF COLORADO 50RT ST. vR AIN NUCLEAR GENE R ATING ST ATION , , , , , ,
us unL-1 Issue A Page 3 of 6
- 8. CRT displays which do not require frequent or continuous monitoring, and which will not display important (e.g., alarm) information, shall be located within the following limits (as measured f rom normal operator work stations which permit full cperator head and eye rotation):
- 1. Horizontal limits-Not more inan 95 to the lef t or right of the operator's straight-aheac LOS.
- 2. Vertical limits-Not more than 80 above and 90 below the operator's horizontal LOS.
ASSOCIATED DIRECTIVES 00-00 Requirement and Guidance for Preparing Design Directives DD-CRT Cathode Ray Tube Selection DD-CON Consoles DD-SLS Screen Layout and Structuring SOURCE MATERIALS AND REFERENCES
- NUREG-0700
- Human Factors in Engineering McCormick, 1976
- Human Factors in Design ERDA 76-45-2 FORM 372 22 36 0
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DD-CRL-1 ISSUE A Pace 4 of 6 m
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. m McRIE NTAL M ACTUAL 45*
Los =
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FIGURE 1
(
MINIMUM CRT VIEWING ANGLE (Shawn only for vertical angles) l FORM 372 22 - 3843
PUBLIC SERVICE COMPANY OF COLORADO FORT ST. VR AIN NUCLEA A GENEG A *i'.O STATION DD-CRL-1 ISSUE A Page 5 of 6 VERTICAL LIMITS D g llt* mum.
? WOM6 L::5 W T g,* men. -
/
m3HT AHEAD" d
- Is* 35*
nums. m HORIZONTAL LIMITS FIGURE 2 CRT SCREEN LOCATION LIMITS (Seated operator - frequently nonitored displays)
Fomu 372 22 3843
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DD-CPL-1 IS5DE A '
. Page 6 of 6 l
_ I v.-no AnF8 45* mA VERTICAL LIMITS 7c8 man.
1 w.m.ms t.::s 4
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vie =ne w
4s* mm. v HORIZONTAL LIMITS 4se osa moi. ss* men.
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_M -~I FIGURE 3 CRT SCREEN LOCATION LIMITS (Seated operator - infrequently monitored displays) onu sn - 22 1sc