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Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML20216E6111999-09-0707 September 1999 Proposed Tech Specs 3/4.3.2.1 Re Safety Features Actuation Sys Instrumentation & Associated Bases ML20210H0731999-07-28028 July 1999 Proposed Tech Specs 3/4.7.5.1, Ultimate Heat Sink, Allowing Plant Operation in Modes 1-4 with Water Temp Less than or Equal to 90 F ML20210G4311999-07-27027 July 1999 Proposed Tech Specs,Changing TSs 6.4, Training, 6.5.2.8, Audits, 6.10, Record Retention, 6.14, Process Control Program & 6.15, Odcm ML20210G4801999-07-26026 July 1999 Proposed Tech Specs 3/4.3.2.1 Re Safety Features Actuation Sys Instrumentation & Associated Bases ML20210G9161999-07-26026 July 1999 Proposed Tech Specs 3/4.3.3.1, Radiation Monitoring Instrumentation, 3/4.3.3.2, Instrumentation - Incore Detectors & 3/4.3.3.9, Instrumentation - Waste Gas Sys Oxygen Monitor ML20210G5391999-07-26026 July 1999 Proposed Tech Specs Re Implementation of 10CFR50,App J, Option B for Type B & C Containment Leakage Rate Testing ML20195F9351999-06-10010 June 1999 Proposed Tech Specs,Revising TS 3/4.6.4.4, Hydrogen Purge Sys, TS 3/4.6.5.1, Shield Bldg Emergency Ventilation Sys & TS 3/4.6.5.1, Crevs ML20207E7941999-05-21021 May 1999 Proposed Tech Specs Allowing Use of Expanded Spent Fuel Storage Capability ML20205E5031999-03-19019 March 1999 Proposed Tech Specs Withdrawing Proposed New Action B, Previously Submitted in 981027 Application ML20204F1821999-03-0909 March 1999 Proposed Tech Specs,Adopting Changes in Frequency & Scope of Volumetric & Surface Exams Justified by W TR WCAP-14535A ML20155E4971998-10-28028 October 1998 Proposed Tech Specs 4.0.2 Re Applicability of 25% Surveillance Interval Extension Allowance ML20197G5521998-10-28028 October 1998 Rev 8 to Dbnps,Unit 1 Technical Requirements Manual ML20155E3231998-10-28028 October 1998 Proposed Tech Specs Revising Various Sections of 6.0, Administrative Controls, Including Relocation of 6.11 Contents to Plant Ufsar,Per NUREG-1430,Rev 1 ML20155D7791998-10-27027 October 1998 Proposed Tech Specs Relocating TS SR 4.6.5.1.d.4 Re Evs Negative Pressure Testing to TS 3/4.6.5.2,deleting TS Definition 1.24 & Making Related Changes Associated with Deletion of Subject Definition ML20155D8521998-10-27027 October 1998 Proposed Tech Specs Revising SRs 4.8.2.3.2.d,4.8.2.3.2.e, 4.8.2.3.2.f & Table 4.8-1 Re Testing of 125 Volt DC Station Batteries & Applicable TS Bases ML20155E0721998-10-27027 October 1998 Proposed Tech Specs Revising 3/4.3.1.1 Re RPS Instrumentation & 3/4.3.2.3 Re ARTS Instrumentation,To Provide Potential Reduction in Spurious Trip Rate for Potential Cost Savings in Excess of $50,000 ML20151W3071998-09-0808 September 1998 Proposed Tech Specs Permitting Use of Framatome Cogema Fuels M5 Advanced Alloy for Fuel Rod Cladding & Fuel Assembly Spacer Grids ML20151W2991998-09-0808 September 1998 Proposed Tech Specs Revising Section 3/4.7.6, Plant Systems - CREVS & Associated Bases ML20206D2721998-08-28028 August 1998 Rev 11,change 1 to Odcm ML20217P8351998-04-24024 April 1998 Proposed Tech Specs Clarifying Discussion of Margin Between RPS High Pressure Trip Setpoint & Lift Setting for Pressurizer Code Safety Valves ML20217P8811998-04-24024 April 1998 Proposed Tech Specs 3/4.3.1.1,3/4.3.2.1,3/4.3.2.2 & Associated Bases Relocating Tables of Response Time Limits to Plant USAR Technical Requirements Manual ML20217C4881998-03-20020 March 1998 Proposed Tech Specs SR 4.4.5.3.c.1,providing Greater Specificity as to Location of Addl Insps in Unaffected SG ML20217N4471998-02-27027 February 1998 Proposed Tech Specs Pages Provided to Modify Proposed New Action 3.7.6.1.b to Make More Consistent w/NUREG-1431 ML20203L1111998-02-26026 February 1998 Proposed Tech Specs Pages Re Amend to License NPF-3 Involving Incorporation of New Repair Roll Process for SG Tubes W/Defects in Upper Tube Sheet ML20197J2621997-12-23023 December 1997 Proposed Tech Specs Pages Re Changes to TS Definition 1.2, TS 3/4/9.5 & New TS 3.0.6 & Associated Bases.Ts Index Rev to Reflect Change to TS 3/4.9.5,included ML20197J5971997-12-23023 December 1997 Proposed Tech Specs Pages,Revising TS Surveillance Requirements for ISI Requirements of Internal Auxiliary Feedwater Header,Header to Shroud Attachment Welds & External Header Thermal Sleeves ML20217M5601997-09-0505 September 1997 Rev 11.0 to Davis-Besse Odcm ML20217R2821997-08-26026 August 1997 Proposed Tech Specs,Clarifying LCO 3.6.1.3.a & Revising Surveillance Requirement 4.6.1.3.c ML20217R2871997-08-26026 August 1997 Proposed Tech Specs,Modifying TS 3.2.5 Action Statement to Require Power Reduction to Less than 5% of Rated Thermal Power within Four Hrs If RCS Flow Rate Is Less than Specified Limit for Greater than Two Hrs ML20217G5981997-07-29029 July 1997 Proposed Tech Specs 3/4.4.3 Re Safety Valves & Pilot Operated Relief valve-operating ML20141F1101997-06-24024 June 1997 Proposed Tech Specs,Deleting Requirements for Safety Features Actuation Sys Containment High Radiation Monitors ML20138C3261997-04-18018 April 1997 Proposed Tech Specs 3/4.7.6 Revising Limiting Condition for Operation to Include New Required Actions in Event That One or Both Channels of Radiation Monitoring Instrumentation Becomes Inoperable ML20138A6891997-04-18018 April 1997 Proposed Tech Specs 3/4.5.3.2.1 & 3/4.5.2 Modifying Presently Specified 18-month Surveillance Frequencies to New Specified Frequencies of Once Each 24-months ML20140D9481997-04-0909 April 1997 ODCM, Rev 10 ML20138M1281997-02-14014 February 1997 Proposed Tech Specs 3.5.2 Re Emergency Core Cooling Systems & 4.5.2.f Re Surveillance Requirements ML20134L0561997-02-13013 February 1997 Proposed Tech Specs Re Changes Made Concerning Decay Heat Removal Sys Valve ML20134F1811997-01-30030 January 1997 Proposed Tech Specs Re Possession & Use of SNM as Reactor Fuel ML20134D7621997-01-30030 January 1997 Proposed Tech Specs Revising SR Intervals from 18 to 24 Months Based on Results of DBNPS Instrument Drift Study & TS 2.2, Limiting Safety Sys Settings, Based on Results of Revised Framatome RPS Instrument String Error ML20134B0591997-01-20020 January 1997 Proposed Tech Specs 3/4.5.3 Re ECCS Subsystems ML20132B7031996-12-11011 December 1996 Proposed Tech Specs Revising TS Definitions,Instrumentation TS & ECCS TS for Conversion to 24 Month Fuel Cycle for License NPF-3 ML20134F1891996-10-28028 October 1996 Proposed Tech Specs 3/4.8 Re Electrical Power Systems ML20117P5311996-09-17017 September 1996 Proposed Tech Specs,Supporting Conversion of DBNPS from 18 Month to 24 Month Fuel Cycle ML20117N8531996-09-12012 September 1996 Proposed Tech Specs Re Reactivity Control Systems & Emergency Core Cooling Systems ML20117M2201996-09-0404 September 1996 Proposed Tech Specs 6.2.3,removing Specific Overtime Limits & Working Hours ML20116K2631996-08-0707 August 1996 Proposed Tech Specs Re Definitions,Applicability Bases, Containment Spray Sys & Containment Isolation Valve for Conversion to 24 Month Fuel Cycle ML20117K1911996-05-28028 May 1996 Proposed Tech Specs 3/4.3.1.1 - RPS Instrumentation & TS 3/4.3.2.3 - Anticipatory RTS Instrumentation Increasing Trip Device Test Interval ML20101M1921996-03-29029 March 1996 Proposed Tech Specs 3/4.6.4.4 - HPS,3/4.6.5.1 - Shield Building Evs & 3.4.7.6.1 - CREVS Re Changing Surveillance Requirements for Charcoal Filter Lab Testing to Revise Methodology Used to Determine Operability in ESF AHUs ML20101C6961996-03-0606 March 1996 Proposed Tech Specs,Allowing Deferment of SR 4.5.2.b for ECCS Flowpath Containing HPI Pump 1-2 Until 10th Refueling Outage,Scheduled to Begin 960408 ML20100E0101996-02-0505 February 1996 Proposed TS 3/4.3.2.1,Table 3.3-3,safety Features Actuation Sys Instrumentation,Reflecting Design & Actuation Logic of Plant Sequencers & Essential Bus Undervoltage Relays ML20107C3101995-12-21021 December 1995 Rev 9 to Odcm 1999-09-07
[Table view] Category:TEST/INSPECTION/OPERATING PROCEDURES
MONTHYEARML20197G5521998-10-28028 October 1998 Rev 8 to Dbnps,Unit 1 Technical Requirements Manual ML20206D2721998-08-28028 August 1998 Rev 11,change 1 to Odcm ML20217M5601997-09-0505 September 1997 Rev 11.0 to Davis-Besse Odcm ML20140D9481997-04-0909 April 1997 ODCM, Rev 10 ML20107C3101995-12-21021 December 1995 Rev 9 to Odcm ML20107C3021995-10-16016 October 1995 Rev 8 to Odcm ML20199L1821995-09-0909 September 1995 Rev 3 to DB-OP-00000, Conduct of Operations ML20082V4071995-02-0303 February 1995 Offsite Dose Calculation Manual Rev 7 ML20072S8611994-06-22022 June 1994 Rev 6 to Davis-Besse Offsite Dose Calculation Manual ML20056F3071993-08-0808 August 1993 Rev 3 to Emergency Plan Off Normal (Epon) Occurrence Procedure HS-EP-02820, Earthquake. W/Rev 23 to Epon Occurrence Procedures Manual Table of Contents ML20072S8401992-12-18018 December 1992 Rev 5 to Davis-Besse Process Control Program ML20072S8501992-12-18018 December 1992 Rev 5.2 to Davis-Besse Offsite Dose Calculation Manual, Reflecting Rev 5,Change 2 to ODCM ML20101R1721992-06-11011 June 1992 Rev 1 to Vol I of Inservice Insp Plan,Second 10-Yr Nuclear Interval Pump & Valve Inservice Testing Program ML20114C6321992-05-19019 May 1992 Change 1 to Rev 5 to ODCM ML20114C6301992-03-0606 March 1992 Rev 5 to ODCM ML20217C3661991-07-0808 July 1991 Rev 3 to Administrative Procedure NG-IS-00002, General Nuclear Security Requirements. Pages 7,9,10 & 15 Only ML20084U5911991-02-22022 February 1991 Rev 4 to ODCM ML20217C3481990-12-18018 December 1990 Rev 1 to Security Dept Procedure IS-DP-04007, Performance Test for Alco-Sensor ML20059D4181990-08-28028 August 1990 Second 10-Yr Interval Pump & Valve Inservice Testing Program ML20217C3001990-08-23023 August 1990 Rev 5 to Security Dept Procedure IS-AC-00011, Protected & Vital Area Badge Issuance & Control ML20217C3571990-08-0909 August 1990 Rev 3 to Security Implementing Procedure IS-AC-00516, Unescorted Access Requirements ML20217C3071990-07-27027 July 1990 Rev 2 to Security Dept Procedure IS-AC-00015, Fingerprint Processing & Controls ML20217C3201990-06-27027 June 1990 Rev 1 to Security Dept Procedure IS-AC-00018, Drug & Alcohol Testing Process ML20217C3811990-06-22022 June 1990 Rev 4 to Nuclear Group Procedure NG-IS-00004, Fitness for Duty Program ML20217C4001990-04-0202 April 1990 Corporate Ref Manual - Nuclear NU-102, Fitness for Duty ML20217C3401990-01-12012 January 1990 Rev 1 to Security Dept Procedure IS-DP-00101, Bac Simulation ML20217C3281989-11-0909 November 1989 Rev 1 to Security Dept Procedure IS-DP-00100, Bac Exams ML20217C3141989-10-25025 October 1989 Rev 2 to Security Dept Procedure IS-AC-00017, Denied Access List Control ML20217C3941989-08-0101 August 1989 Corporate Ref Manual - Human Resource HR-604, Drug & Alcohol Policy ML20244A8421989-05-31031 May 1989 Pressurizer Surge Line Thermal Stratification Phase I Program ML20213A0311987-03-31031 March 1987 Rev 2 to Vol IV of Procedure Writers Manual:Operation Procedures Guidelines ML20213A0361987-03-31031 March 1987 Rev 1 to Davis Besse Emergency Procedure Verification & Validation Program ML20212D1621987-01-27027 January 1987 Rev 1 to Maint Procedure MP 1411.06, Preventive Maint for Type Smb & Smc Valve Operators ML20198D2551986-12-27027 December 1986 Rev 2 to Maint Procedure MP 1411.04, Maint & Repair of Limitorque Valve Operators Type SMB-000 & SMB-00. Temporary Mod Request T-9969,indicating Rewiring of Fcr 85-302 MU-11 to Torque Out in Open Direction,Encl ML20212B5721986-12-15015 December 1986 Rev 0 to Security Training & Qualification Plan, Superseding Rev 24 to App B of ISP AD1808.00.W/o Revised Pages ML20212C9481986-11-21021 November 1986 Rev 8 to Maint Procedure Mpo 1410.32, Testing of Motor- Operated Valves Using Movats ML20212D3131986-10-28028 October 1986 Change 3 to Temporary Mods T10161 & T10144 to Rev 0 to Maint Procedure MP 1411.07, Maint & Repair of Limitorque Valve Opr Smc 04, Incorporating Fcr 86-0092,Rev a Re Removal & Installation of Limiter Plate ML20212D1091986-10-21021 October 1986 Change 1 to Rev 2 to Maint Procedure MP 1411.04, Maint & Repair of Limitorque Valve Operators Type SMB-000 & Smb 00, Addressing Need for Procedure to Address Replacement of Defectrive Parts ML20212D1471986-10-0303 October 1986 Rev 1 to Maint Procedure MP 1411.05, Maint & Repair of Limitorque Valve Operators Types SMB-0 Through SMB-4 ML20212C9181986-09-22022 September 1986 Rev 1 to Procedure NEP-092, Establishing D/P Limits & Tests for Q Motor Operated Valves ML20203M0201986-08-21021 August 1986 Specs for Mist Continuous - Venting Tests ML20210V1131986-08-20020 August 1986 Rev 0 to Emergency Plan Implementing Procedure EP-2320, Emergency Technical Assessment ML20206P6511986-06-30030 June 1986 GE Owners Group Action Plan as Result of Davis-Besse Event, June 1986 ML20198D2361986-05-0202 May 1986 Rev 5 to Maint Procedure MP 1410.32, Testing of Motor- Operated Valves Using Movats ML20141J5231986-04-18018 April 1986 Human Engineering Discrepancy Review & Closeout Process for Davis-Besse Dcrdr Program ML20205M6981986-04-0707 April 1986 Rev 0 to Nuclear Engineering Procedure NEP-092, Establish Differential Pressure Limits & Tests for Motor-Operated Valves ML20205M7031986-03-25025 March 1986 Rev 0 to Nuclear Engineering Procedure NEP-091, Motor- Operated Valve (MOV) Data Evaluation ML20141N1501986-02-26026 February 1986 Procedure Fcr 85-227, Main Feedwater Block Valve Interlock ML20141N1561986-02-26026 February 1986 Procedure Fcr 85-200, Main Feedwater Pumps Rapid Feedwater Reduction Speed Setpoint ML20141N1531986-02-26026 February 1986 Procedure Fcr 85-201, Steam Generator Level Setpoint 1998-08-28
[Table view] |
Text
_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ .
Y
.
s Davis-Besse Nuclear Pcwer Station i '
Unit No. 1 Systen Procedure SP 1105.11 Safety Parameter Display Systen Operatim Procedure i . .
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I h1 of Approval and Cunges Prepared By stan Bateh 1 /21 /9 5 Dere .
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/ Sec:x n Head Date
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,. P+= . m ay Aa y MAR 2'71S85 t.... SFS CMiman Date CA Approved Al/A Qualiri Assurance Director Date Appr=ved By AW m _+ - -- x MAR 2 71985 Pian: kunager V Date .
Pevisicn SF3 QA Plant ?hnager No. Pecamendation Cate Approved Date Approval Cate j F
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1 SP 1105.11.0 s 1.0 PL*RPOSE This procedure's main purpose is to describe how to use the Safety Parameter Display System (SPDS). This procedure does not discuss the historical basis for SPDS or go into an extended discussion of the design basis. This information is available in the Davis-Besse SPDS Safety Analysis Report (to be completed by May 1, 1985).
The principal purpose of the SPDS is to aid the Control Room personnel during abnormal and emergency conditions to determine the safety statu.c of the plant. The SPDS displays available in the Control Room are also available in the Technical Support Center (TSC) and Emergency Centrol Center (ECC) to aid in the assessment of plant conditions both during normal and emergency operation.
Information from plant process instrumentation provides input to both the plant process computer (MODCOMP) and a separate multiplexer (Validyne) which is used as the primary source of data to the SPDS.
Information from the plant process computer via the multiplexer is then transmitted to the Davis-Besse Administration Building. The computer system located in the Technical Support Center receives the information, stores the information, and generates the displays necessary for the SPDS displays. The info"mation received from the Station is stored in a circular file for a period of 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
Two different types of display devices are available in both the Control Room and Technical Support Center. The Ramtek units are the primary SPDS display devices. These units have complete
(-
historic capability and contain all the required SPDS displays.
The Chromatics unit is also provided in the Control Room and Technical Support Center to provide increased graphics capabilities and a quicker display capability. Although the Chromatics units have all the required SPDS displays, the Chromatics units cannot be used to review hiscoric data.
Alarm boxes are displayed on the bottom of all displays associated with the SPDS. These alarms are activated by parameters reaching specified setpoints. Associated with each of the alarm boxes is another lower level display showing an historical trend of parameters selected to assist the operator in determining the status of the associated safety function. These six lower level displays and the top level alarm box display constitute the minimum SPDS display format.
Also associated with each of the alarm boxes is an upper level display which can provide the operator with additional information in various formats that may be useful in establishing the status of a given safety function. These upper level displays are not considered a part of the minimum SPDS.
If any alarm logic is satisfied, the appropriate critical safety function box will be lit and flash. Once the operator has called up the upper or lower level display for the alarm, the critical safety function box will no longer flash, but will remain lit for as long as the alarm condition exists. The critical safety function n
2 SP 1105.11.0 box will return to normal (unlit status) automatically after an ;
acknowledged alarm clears its alarm setpoint. If any new alarm
, occurred while a critical safety function box is lit, the new alarm will cause the critical safety function box to again flash until the appropriate upper or lower level display is called up. Space is available on each upper and lower level display to indicate j which alarm condition has caused the critical safety function to be lit. For example, if a low pressurizer level occurs (less than ten inches), the Primary critical safety function box will be lit and i flash until a primary display is selected by the operator. On the 4 primary display there will be a (PRESSURIZER LEVEL LOW) alarm i printed near the bottom of the screen.
The lower level trend displays of the Davis-Besse SPDS are designed
] to provide the operator with historical information useful in l~ determining the status of the critical safety functions. Each lower level display features trends and instantaneous values of
, plant parameters that are primary indicators of the status of the associated critical safety function. Current values of each trend parameter are provided at the right hand margin of each display, j along with the parameter point identification number. This instanta-neous data, the graphically trended data, and the corresponding ,
scale information are color coded to allow simple identification of each parameter. The trend display provides a minimum of 25 minutes 1
of historical data plotted from left to right, up to the zero time scale indication. As current data is displayed, it is added to the trend until the screen-is filled. At that point, the trends are "N scrolled to the left in one five minute increment to return to the /
.end of the trends to the zero time scale. If the computer point is identified as being invalid, that information is being provided to the user by displaying an instantaneous value of -99.0 printed in white in the.right hand margin of the display.
i Additional information on the display parameters and the alarms for each of these displays is available in the Davis-Besse SPDS Safety Analysis Report. Operation of the unit will be discussed in Section 4 of this procedure.
2.0 PRECAUTIONS AND LIMITATIONS None
3.0 REFERENCES
( 3.1 Toledo Edison submittal letter, Serial Number 1011, dated November 30, 1983 3.2 Davis-Besse Unit 1 SPDS Safety Analyis Report 3
, _ -__.._ _.. , , - . _ , , , . . . . , . , _ _ . . .,_m. ..., ...r.,.. ~ . . . . - ~ . , _ _ _ .
3 SP 1105.11.0
- -w 4.0 NORMAL OPERATION k
4.1 Access From the RAMTEK Terminal 4.1.1 Turn terminal on by depressing the upper half of the black power switch (also see Figure 3 for RAMTEK layout).
4.1.2 Type M l RETURN l
- 1. This message will then appear on the screen:
i
'J
- PLEASE BE PATIENT -
< - LOADING FUNCTION KEYS -
- THIS WILL TAKE APPROXIMATELY I MINUTE --
r~
(,"j 2. Af ter approximately oc.e minute, the TSC MENU will be displayed:
TSC MENU fl - SPDS f2 - CRT DISPLAYS f3 - HARDCOPY f4 - GROUP ASSIGNMENTS f5 - DOSE CALCULATIONS f6 - ENGINEERING AIDS
-l f7 - OPERATCR AIDS f8 - SPDS TEST VERSION f9 - SPARE (
fa - TSC MENU - \.
j fb - LOGIN ON SYSTEM B fc - LOGOUT NOTE: The color scheme is as follows:
Blue - Currently Available Yellow - Proposed - Currently Unavailable Green - Special Purpose v
_ _ _ _ _ . _ _ _ _ _ _ . _ _ _ . . _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ . _ _ _ _ _ . _ _ . _ . _ _ _ _ _ _ _ _ _ _ _ _ . . _ . _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ ____..____.___________________._____o
4 SP 1105.11.0
- 3. By depressing l fl I the SPDS Menu will be +-
displayed:
SPDS MENU fl - PRESSURE VS TEMPERATURE (LP 1) cf1 - P/T TRENDS f2 - SPARE cf2 - PRIMARY TRENDS f3 - STEAM GENERATOR cf3 - SECONDARY TRLNDS f4 - SPARE cf4 - RADIATION TRENDS f5 - SPARE cf5 - CONTAINMENT TRENDS f6 - SPARE cf6 - REACTIVITY TRENDS f7 - PRESSURE VS TEMPERATURE (LP 2) cf7 - SPARE 29 - SPARE cf8 - SPARE f9 - SPARE cf9 - SPARE fa - SPDS MENU cfa - TSC MENU fb - REAL-TIME MODE cfb - HISTORICAL MODE fc - SPARE cfc - LOG 0FF SYSTEM
- 4. To get into a specific display, hit the corresponding function key.
- 5. If you are not sure where you are at some particular time:
a) Depress the function key I fa l to bring you back to the specific menu.
(OR) b) Depress the function key l W l l fa l to bring you back to the TSC MENU.
- 6. To Log Off:
i a) Go back to the TSC MENU (depress l W l 1 l fa l TSC MENU) and log off by depressing i the l fc l- LOGOUT function key.
(OR) b) Hit the l BREAK l key on the keyboard.
Type Q l RETURN j.
1 Type Q l RETURN l .
(OR) c) When the program is finished running, after the OK, prompt, type W l RETURN l.
m.
I
~ ,
~
SP 1105.11.0 5
l
. , 7. Once the logged off display comes up, turn
(-n terminal off.
C.
4.1.3 If problems are experienced, attempt to clear the system and start over by:
- 1. Making sure all console switches in the right hand corner of the keyboard are in the UP position (see diagram of keyboard).
- 2. Clearing the system VIEW a) Press ALPHA b) Press the l RESET l button on the back of the keyboard (see diagram of keyboard).
c) Press l BREAK l.
d) Type Q l RETURN l .
e) Look for the OK, on the screen, then type "
l L2 I RETURN l, f) Wait for another OK, on the screen, then type M l RETURN l.
The function keys should be reloaded, and the TSC MENU should appear.
4.1.4 Helpful Hints
- 1. .The l BACKSPACE l key is used to delete
, characters.
- 2. The l BREAK l key halts execution of the current updating pro' gram. When executing the CRT display program, the " break" key sends the user back to Level 1 of the display options.
VIEW
- 3. The ALPHA key displays on the screen all alpha communication between terminal and the
- computer.
VIEW
- 4. The GRAPH key displays on the screen the most recent graphic output.
M
- 5. The BOTH key allows the user to view both the graphic and alpha modes simultaneously.
s_
6 SP 1105.11.0 4.2 Access From the Chromatics Terminal -T 4.2.1 Turn terminal on by depressing the square switch on the front of the unit. (located above the keyboard on the right side) ,
4.2.2 This menu will appear:
TSC MENU fl - SPDS DISPLAYS f7 - OPERATOR AIDS f2 - SPARE f8 - SPARE f3 - SPARE f9 - SPARE f4 - SPARE fl0 - SPARE f5 - SPARE fil - SPARE f6 - SPARE f12 - TSC MENU NOTE: The color scheme is as follows:
^
Blue - Currently Available Yellow - Proposed - Currently Unavailable Green - Special Purpose 4.2.3 To get into a specific program, hit the corresponding 3 function key. j 4.2.4 If you are not sure where you are at some particular time:
- 1) Depress the function key l W l to bring you back to the specific menu.
(OR)
- 2) Depress the function key l s*f12 lto bring you back to the TSC MENU.
4.2.5 To Log Off:
- 1. Go back to the TSC MENU (depress l s*fl2 l -
TSC MENU) and depress the on/off switch.
4.2.6 If problems exist, or the system is not responding as expected, attempt to clear the system and start over by depressing the orange RESET key (top row of keyboard - far left).
1
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i
. 7 SP 1105.11.0 FIGURE 1 SPDS BASIC CONFIGURATION
~ M - - - -
\.'
PLANT PROCESS INSTRUMENTATION i :.
\/
CLASS 1E ISOLATION EQUIPMENT FOR SAFETY ~~
SYSTEM SIGNALS
\/ N/ V \/
PLANT PROCESS g I I COMPUTER PIAvr .. -
i V V V i DEC PROCESSOR I DADS PROCESSOR v V I TSC & ECC TSC DISPLAY DISPLAYS I
i DAVIS-BESSE ADMINISTRATION SUILDING M - - - -
M V V CONIROL ROOM CONTROL ROOM DISPLAT DISPLAY ,
CONTRCL ROOM .
/
1 8 SP 1105.11.0 ,
FIGURE 2 l SPDS HARDWARE CONFIGURATION s
P UNT PROCESS INSTRUMENTATION i
y ., l 1 VALIDYNE DIGITAL & ANALOG Valtex BU.Valt.em i MULTIPLEIER MULTIPT.ErrH Fibr. Fibr. g
~ ,,,
u , s . s ,-s v
EDCOMP '
PLANT PROCESS I COMPUTER 8 PLANT CABD'ET/CCMPLTEF ROOM v
PLANT PROCESS COMPUTER DISPLAY DEVICES ..
u \f RA)CEE g OVERHEAD OVERHEAD I :l1DLOMATICS -
- DISPLAY REPEATER REPEATER l p , DISPLAY I s i KET30ARD KET30ARD 1
gNTROLROCM _ _
- + 4 ygg,g VALTEC VALTEC RECZ~VER
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PRIME A k' PRIME B it
' v 8 n n VMEd s,/ %/
RECE!VER DISK DISK STORAGE STORAGE v ,
DEC 11/ 'b 'b
' k TSC ECC l y DISPuYS DISPLAY RAMIEK RAMIEK
.SC DISPLAY i C11ROMATICS -
l ,
KET30ARD KZT30ARD
-1 xzmA o I i DAVIS-arSSE ADMINISTRATION acILDING i
i
9 SP 1105.11.0
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RAMTEK TERMINAL assey ni N s
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