Letter Sequence Other |
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Results
Other: ML20137L000, ML20206T655, ML20206T679, ML20206T705, ML20206T726, ML20206T748, ML20206T776, ML20206T792, ML20206T817, ML20206T843, ML20206T847, ML20206T875, ML20206T899, ML20206T913, ML20206T921, ML20206T931, ML20206T937, ML20206T949, ML20206T966, ML20206T981, ML20206T986, ML20206U003, ML20212B914, NLS8400108, Forwards Second 10-yr Inservice Insp Plan, NLS8600021, Forwards Addenda to Rev 3 to Inservice Insp Program for ASME Class 1,2 & 3 Components, NLS8600248, Forwards Rev 5 to Inservice Testing Program for ASME Class 1,2 & 3 Components, for Second 10-yr Testing Program. General Pump Testing Procedure 3.9 & General Valve Testing Procedure 3.10 Being Revised to Incorporate Rev 1 Changes
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MONTHYEARML20206T9131978-10-23023 October 1978 Rev 5 to Surveillance Procedure 6.3.16.1, Reactor Equipment Cooling - Pump Operability Test Project stage: Other ML20206T9861981-08-28028 August 1981 Rev 0 to Surveillance Procedure 6.4.1.8, Control Rod Drive Hydraulic Control Unit Accumulator Leakage Test Project stage: Other NLS8400108, Forwards Second 10-yr Inservice Insp Plan1984-04-0303 April 1984 Forwards Second 10-yr Inservice Insp Plan Project stage: Other ML20206U0031984-07-23023 July 1984 Rev 13 to Nuclear Performance Evaluation Procedure 10.9, Control Rod Scram Time Evaluation Project stage: Other ML20100M8071984-11-28028 November 1984 Draft Rev 9 to QA Policy for Calvert Cliffs Nuclear Power Plant Project stage: Draft Other ML20206T9311984-12-0606 December 1984 Rev 6 to Surveillance Procedure 6.3.18.1, Svc Water Pump Operability Test Project stage: Other ML20206T9371984-12-0606 December 1984 Rev 10 to Surveillance Procedure 6.3.18.2, Svc Water Motor Operated Valve Operability Test Project stage: Other ML20206T8751985-01-0303 January 1985 Rev 11 to Surveillance Procedure 6.3.12.2, Diesel Generator Starting Air Compressor Operability Project stage: Other ML20206T9661985-05-0202 May 1985 Rev 13 to Surveillance Procedure 6.3.19.1, Standby Gas Treatment Operability Test Project stage: Other ML20129J6611985-07-12012 July 1985 Submits Revised Inservice Testing Relief Requests RV-03 Re Reactor Recirculation Loops a & B Discharge Bypass Valves, Reflecting Current Pipe Configuration & RP-05 Re HPCI Test Method & Updated Request Index Project stage: Request ML20206T7761985-08-18018 August 1985 Rev 11 to Surveillance Procedure 6.3.8.4, Standby Liquid Control Manual Initiation Test Tank to Reactor Vessel Project stage: Other ML20206T8171985-09-13013 September 1985 Rev 12 to Surveillance Procedure 6.3.10.2, Instrument Line Flow Check Valve Test Project stage: Other ML20137L0001985-10-31031 October 1985 Addenda to Rev 3 to Inservice Insp Program for ASME Class 1,2 & 3 Components Project stage: Other ML20206T7481985-11-21021 November 1985 Rev 15 to Surveillance Procedure 6.3.6.1, RCIC Test Mode Surveillance Operation Project stage: Other ML20206T8431985-12-11011 December 1985 Rev 0 to Surveillance Procedure 6.3.10.16, Check Valves in Cooling Sys of Diesel Generators Integrity Verification Project stage: Other ML20206T9211986-01-16016 January 1986 Rev 12 to Surveillance Procedure 6.3.16.2, Reactor Equipment Cooling Motor Operated Valve Operability Test Project stage: Other NLS8600021, Forwards Addenda to Rev 3 to Inservice Insp Program for ASME Class 1,2 & 3 Components1986-01-17017 January 1986 Forwards Addenda to Rev 3 to Inservice Insp Program for ASME Class 1,2 & 3 Components Project stage: Other ML20206T7051986-01-30030 January 1986 Rev 18 to Surveillance Procedure 6.3.4.1, Core Spray Test Mode Surveillance Operation Project stage: Other ML20154A5251986-02-12012 February 1986 Forwards Request for Addl Info Re Inservice Testing Program, Based on Review of 840615,850522 & 0722 Ltrs Describing Second 10-yr Inservice Testing Program.Response Requested within 45 Days Project stage: RAI ML20206T9491986-03-0606 March 1986 Rev 15 to Surveillance Procedure 6.3.18.3, Svc Water Surveillance Operation Project stage: Other ML20206T8471986-03-0606 March 1986 Rev 17 to Surveillance Procedure 6.3.12.1, Diesel Generator Operability Test Project stage: Other ML20206T7261986-03-13013 March 1986 Rev 21 to Surveillance Procedure 6.3.5.1, RHR Test Mode Surveillance Operation Project stage: Other ML20206T9811986-04-24024 April 1986 Rev 17 to Surveillance Procedure 6.3.20.1, RHR Svc Water Booster Pump Flow Test & Valve Operability Test Project stage: Other ML20211A1361986-04-28028 April 1986 Trip Rept of 860415-16 Site Visit for Pump & Valve Inservice Testing Program Working Meeting Re Questions Resulting from Program Review.List of Attendees,Questions Serving as Agenda for Meeting & Responses to Questions Encl Project stage: Meeting ML20211A0891986-05-30030 May 1986 Forwards Contractor Summary of 860412 & 16 Meetings at Facility Re to Recipient Requesting Addl Info on Second 10-yr Inservice Testing Program.Correction Made on Page 2 of Summary Project stage: Meeting ML20206T7921986-06-0505 June 1986 Rev 1 to Surveillance Procedure 6.3.9.1, MSIV Accumulator Functional Test Project stage: Other ML20206T8991986-06-0505 June 1986 Rev 3 to Surveillance Procedure 6.3.12.8, Diesel Generator Fuel Oil Transfer Pump Flow Test Project stage: Other ML20206T6791986-06-12012 June 1986 Rev 23 to Surveillance Procedure 6.3.3.1, HPCI Test Mode Surveillance Operation Project stage: Other ML20206T6551986-06-12012 June 1986 Rev 13 to Surveillance Procedure 6.3.2.1, Automatic Depressurization Sys Manual Valve Actuation Project stage: Other ML20206T6381986-06-30030 June 1986 Forwards Response to W Long 860212 Request for Addl Info Re Inservice Testing Program & 860415-16 Meetings Re Open Items.Surveillance Procedures,Including Procedure 6.3.2.1, Also Encl Project stage: Meeting NLS8600248, Forwards Rev 5 to Inservice Testing Program for ASME Class 1,2 & 3 Components, for Second 10-yr Testing Program. General Pump Testing Procedure 3.9 & General Valve Testing Procedure 3.10 Being Revised to Incorporate Rev 1 Changes1986-07-30030 July 1986 Forwards Rev 5 to Inservice Testing Program for ASME Class 1,2 & 3 Components, for Second 10-yr Testing Program. General Pump Testing Procedure 3.9 & General Valve Testing Procedure 3.10 Being Revised to Incorporate Rev 1 Changes Project stage: Other ML20212B9141986-07-31031 July 1986 Vols I & II of Rev 5 to Inservice Testing Program for ASME Class 1,2 & 3 Components, for Second 10-yr Testing Program Project stage: Other ML20148C9481988-01-13013 January 1988 Forwards Safety Evaluation of Util Second 10-yr Inservice Testing Program Submitted w/860730 Ltr.Certain Relief Requests Denied Where Proposed Alternative Testing Unacceptable.Technical Evaluation Rept Also Encl Project stage: Approval ML20151H8461988-04-13013 April 1988 Forwards Response to Anomalies Identified in NRC 880113 SER Re Facility Inservice Testing Program.Reactor Equipment Pumps Will Be Tested in Accordance W/Section Xi.Util Evaluating Need for Any Relief Request in Performing Test Project stage: Request ML20151L3111988-07-29029 July 1988 Forwards Revised & New Relief Requests & Program Corrections to Second 10 Yr Inservice Testing Program.Addl Review of Program Identified Need for Further Changes to Program Including Rev of Existing Relief Requests Project stage: Request 1986-01-17
[Table View] |
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Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML20217C7961999-10-0606 October 1999 Marked-up & Type Written Proposed TS Pages,Revising TSs 1.0, 3.6,Bases 3.0,Bases 3.6 & 5.5,to Adopt Implementation Requirements of 10CFR50,App J,Option B for Performance of Type A,B & C Containment Leakage Rate Testing ML20209A7351999-06-23023 June 1999 Proposed Tech Specs Pages 3.3-4 & 3.3-6,replacing Page 3.3-6 Re Recirculation Loop Flow Transmitters & Applicable SRs Associated with Function 2.b ML20196B4741999-06-17017 June 1999 Proposed Tech Specs Bases Changes Made at Plant Subsequent to Receipt of License Amend 178,dtd 980731,for Conversion to Its,Through 990610 ML20195E9101999-06-0808 June 1999 Proposed Tech Specs,Correcting Described Method by Which SGTS Heaters Are to Be Tested ML20207A0761999-05-14014 May 1999 Rev 3 to CNS Strategy for Achieving Engineering Excellence ML20206J2661999-04-22022 April 1999 CNS Offsite Dose Assessment Manual (Odam) ML20205H2891999-03-31031 March 1999 Proposed Tech Specs Modifying ACs for Unit Staff Qualifications for Shift Supervisor,Senior Operator,Licensed Operator,Shift Technical Advisor & Radiation Manager Positions ML20151Q0621998-07-28028 July 1998 Final Version of Improved TS & Bases Re Proposed Change to Conversion to Improved Standard TS ML20236W1141998-07-28028 July 1998 Proposed Tech Specs Re Implementation of BWR Thermal Hydraulic Stability Solution ML20236R9821998-07-16016 July 1998 Proposed Tech Specs Section 6.5.1,re Implementation of BWR Thermal Hydraulic Stability Solution ML20236Q0641998-07-13013 July 1998 Proposed Tech Specs Re Rev B to Conversion to Improved STS ML20206P9051998-07-0707 July 1998 Rev 2, Strategy for Achieving Engineering Excellence, for Cooper Nuclear Station ML20216H0571998-04-15015 April 1998 Proposed Tech Specs 4.2.C,exempting Neutron Detectors from Channel Calibr Requirements ML20216H0801998-04-15015 April 1998 Proposed Tech Specs Sections 2.1.A.1.d & 3.2.C,deleting Max Rated Power for APRM Rod Block Trip Setting ML20216D8971998-04-0808 April 1998 Rev 1 to Strategy for Achieving Engineering Excellence ML20216B4481998-04-0202 April 1998 Proposed Tech Specs 4.2.C,exempting Neutron Detectors from Channel Calibr Requirements ML20203G4271998-02-24024 February 1998 Rev 0 to First Ten-Year Interval Containment Insp Program for Cns ML20202H5311998-02-11011 February 1998 Strategy for Achieving Engineering Excellence ML20216G1571997-09-0505 September 1997 Rev 2.1 to Third 10-Yr Interval Inservice Insp Program ML20210H5641997-08-0707 August 1997 Rev 2 to NPPD CNS Third Interval Inservice Testing Program ML20148G3481997-05-30030 May 1997 Proposed Tech Specs,Changing Frequency of Testing RHR Cross Tie valve,RHR-MOV-MO20,position Indication from Once Per Month to Once Per Operating Cycle ML20148G8531997-05-0909 May 1997 Nebraska Public Power District Nuclear Power Group Phase 3 Performance Improvement Plan, Closure Rept ML20138J0751997-05-0505 May 1997 Proposed Tech Specs,Relocating Control of Standby Liquid Control Relief Valve Setpoint in TS 4.4.A.2.a & Associated Bases ML20148B0041997-05-0202 May 1997 Proposed Tech Specs,Deleting SLC Relief Valve Testing Described in TS Section 4.4.A.2.a & Associated Bases in Bases Section 3.4.A Since Testing Is Already Performed Under ISI Program ML20138H3861997-04-29029 April 1997 Rev 1.2 to CNS Third Interval IST Program ML20134K3771997-02-10010 February 1997 Proposed Tech Specs Re Requirements for Avoidance & Protection from Thermal Hydraulic Instabilities to Be Consistent w/NEDO-31960 & NEDO-31960,Suppl 1, BWR Owners Group Long-Term Stability Solutions.. ML20134E1091996-10-25025 October 1996 NPPD Cooper Nuclear Station Third Interval IST Program, Rev 1 ML20117K3291996-06-0606 June 1996 Proposed Tech Specs Revising Safety Limit MCPR from 1.06 to 1.07 for Dual Recirculation Loop Operation & from 1.07 to 1.08 for Single Recirculation Loop Operation ML20100R4431996-03-0505 March 1996 Proposed Tech Specs,Consisting of Change Request 142, Revising TS, DG Enhancements ML20101L8381995-12-31031 December 1995 Reactor Containment Bldg Integrated Leak Rate Test. W/ ML20113B0531995-12-29029 December 1995 Rev 4.1 to NPPD CNS Second Ten Yr Interval ISI Program for ASME Class 1,2 & 3 Components ML20093L1901995-10-18018 October 1995 Rev 0 to Third Ten-Yr Interval ISI Program for Cns ML20086K4421995-07-14014 July 1995 Revised Proposed Tech Specs Re DG Enhancements Reflecting More Conservative Approach to Enhancing DGs ML20086H7341995-07-14014 July 1995 Rev 7 to CNS Second Ten Yr Interval IST Program ML20086H7601995-06-30030 June 1995 Rev 4 to CNS Second Ten Yr Interval ISI Program for ASME Class 1,2 & 3 Components ML20086B7061995-06-28028 June 1995 Proposed Tech Specs Re Increasing Required RPV Boron Concentration & Modifying Surveillance Frequency for SLC Pump Operability Testing ML20085J2631995-06-15015 June 1995 Proposed Tech Specs Re Extension of Surveillance Intervals for Logic Sys Functional Testing for ECCS ML20083A7241995-05-0505 May 1995 Proposed Tech Specs Reflecting Changes to TSs & Associated Bases for License DPR-46 ML20083A1341995-05-0202 May 1995 Proposed Tech Specs Re Temporary Rev to SR to Extend Two Year LLRT Interval Requirement ML20083M0401995-01-20020 January 1995 Rev 1 to Restart Readiness Program ML20083M0901995-01-13013 January 1995 Rev 2 to Startup & Power Ascension Plan ML20149H8821994-12-27027 December 1994 Proposed Tech Specs Re Control Room Emergency Filter Sys ML20078S5711994-12-22022 December 1994 Proposed Tech Specs Re Definition of Lco,Per GL 87-09 ML20083M0141994-11-0909 November 1994 Rev 3 to Phase 1 Plan, ML20083M0321994-11-0808 November 1994 Rev 0 to Restart Readiness Program ML20073J2371994-09-26026 September 1994 Proposed TS LCOs 3.5.C.1 & 3.5.C.4,increasing Min Pressure at Which HPCI Sys Required to Be Operable from Greater than 113 Psig to Greater than 150 Psig ML20149F9921994-09-15015 September 1994 Rev 1 to CNS Startup Plan ML20071K9311994-07-27027 July 1994 Diagnostic Self Assessment (DSA) Implementation Plan ML20071K1541994-07-26026 July 1994 Proposed Tech Specs to Increase Flow Capacity of Control Room Emergency Filter System ML20070M6671994-04-26026 April 1994 Proposed Tech Specs Re Intermittent Operation of Hydrogen/ Oxygen Analyzers 1999-06-08
[Table view] Category:TEST/INSPECTION/OPERATING PROCEDURES
MONTHYEARML20207A0761999-05-14014 May 1999 Rev 3 to CNS Strategy for Achieving Engineering Excellence ML20206J2661999-04-22022 April 1999 CNS Offsite Dose Assessment Manual (Odam) ML20206P9051998-07-0707 July 1998 Rev 2, Strategy for Achieving Engineering Excellence, for Cooper Nuclear Station ML20216D8971998-04-0808 April 1998 Rev 1 to Strategy for Achieving Engineering Excellence ML20203G4271998-02-24024 February 1998 Rev 0 to First Ten-Year Interval Containment Insp Program for Cns ML20202H5311998-02-11011 February 1998 Strategy for Achieving Engineering Excellence ML20216G1571997-09-0505 September 1997 Rev 2.1 to Third 10-Yr Interval Inservice Insp Program ML20210H5641997-08-0707 August 1997 Rev 2 to NPPD CNS Third Interval Inservice Testing Program ML20148G8531997-05-0909 May 1997 Nebraska Public Power District Nuclear Power Group Phase 3 Performance Improvement Plan, Closure Rept ML20138H3861997-04-29029 April 1997 Rev 1.2 to CNS Third Interval IST Program ML20134E1091996-10-25025 October 1996 NPPD Cooper Nuclear Station Third Interval IST Program, Rev 1 ML20113B0531995-12-29029 December 1995 Rev 4.1 to NPPD CNS Second Ten Yr Interval ISI Program for ASME Class 1,2 & 3 Components ML20093L1901995-10-18018 October 1995 Rev 0 to Third Ten-Yr Interval ISI Program for Cns ML20086H7341995-07-14014 July 1995 Rev 7 to CNS Second Ten Yr Interval IST Program ML20086H7601995-06-30030 June 1995 Rev 4 to CNS Second Ten Yr Interval ISI Program for ASME Class 1,2 & 3 Components ML20083M0401995-01-20020 January 1995 Rev 1 to Restart Readiness Program ML20083M0901995-01-13013 January 1995 Rev 2 to Startup & Power Ascension Plan ML20083M0141994-11-0909 November 1994 Rev 3 to Phase 1 Plan, ML20083M0321994-11-0808 November 1994 Rev 0 to Restart Readiness Program ML20149F9921994-09-15015 September 1994 Rev 1 to CNS Startup Plan ML20071K9311994-07-27027 July 1994 Diagnostic Self Assessment (DSA) Implementation Plan ML20065H7481994-03-31031 March 1994 Near Term Integrated Enhancement Program, 940331 ML20063L2391994-01-31031 January 1994 Jan 1994 Addenda Cooper Nuclear Station IST Program for ASME Class 1,2 & 3 Components, Rev 6 ML20058C3331993-11-17017 November 1993 Rev 1 to Procedure MIUB-W812, Ultrasonic Insp of Pressure Retaining Bolting Two Inches or Greater in Diameter ML20058C3501993-11-15015 November 1993 Rev 0 to Procedure GE-UT-307, Procedure for Ultrasonic Exam of Reactor Pressure Vessel Closure Studs ML20128P0451992-12-21021 December 1992 Dec 1992 Addenda to Rev 6 to Cooper Nuclear Station Inservice Testing Program for ASME Class 1,2 & 3 Components ML20118A6151992-07-31031 July 1992 Jul 1992 Addenda to Rev 6 to Inservice Testing Program for ASME Class 1,2, & 3 Components ML20091K1831991-12-17017 December 1991 Dec 1991 Addenda to Rev 3 to Cooper Nuclear Station Inservice Insp Program for ASME Class 1,2 & 3 Components ML20086E6161991-11-0808 November 1991 Revised Pages to Cooper Nuclear Station Inservice Insp Program ML20085G1841991-08-31031 August 1991 Aug 1991 Addenda to Cooper Nuclear Station Inservice Testing Program for ASME Class 1,2 & 3 Components (Rev 6) ML20082H6371991-08-0101 August 1991 Aug 1991 Addenda to Rev 3 to Cooper Nuclear Station, Inservice Insp Program for ASME Class 1,2 & 3 Components ML20043C7951990-05-25025 May 1990 Rev 6 to Inservice Testing Program for ASME Class 1,2 & 3 Components. ML19332C8181989-10-31031 October 1989 October 1989 Addenda to Rev 3 to Inservice Insp Program for ASME Class 1,2 & 3 Components. ML20246J4271989-07-31031 July 1989 Jul 1989 Addenda to Inservice Insp Program for ASME Class 1,2 & 3 Components, Rev 3 ML20247K7591989-02-28028 February 1989 Addenda to Rev 3 to, Inservice Insp Program for ASME Class 1,2 & 3 Components ML20151U1551988-08-12012 August 1988 Long-Term Plan for Code Qualification of Seismic Class 1S Pipe Supports Cooper Nuclear Station ML20235U4221987-09-21021 September 1987 Reportability Analysis for 10CFR50.50 to Rev 5 to Engineering Procedure 3.3, Station Safety Evaluations. Related Info Encl ML20235U4091987-09-21021 September 1987 Temporary Mod Sheet to Rev 2 to Conduct of Operations Procedure 2.0.7, Plant Temporary Mod Control ML20235T2711987-08-20020 August 1987 1987 Annual Emergency Preparedness Exercise ML20153F0491987-06-0101 June 1987 Addenda to Rev 3 to Inservice Insp Program for ASME Class 1 2 & 3 Components ML20212D6301986-12-18018 December 1986 Fitness for Duty Policy ML20064A6961986-12-0202 December 1986 App I to PEI-TR-870200-01 Test Procedure for Steam Accident Test of Limitorque Control & Power Wiring & Okonite Tape Splices ML20211B4971986-09-30030 September 1986 Rev 5 to Offsite Emergency Plan Prompt Alert & Notification Sys Addendum for Cooper Nuclear Station ML20211B4891986-09-30030 September 1986 Rev 4 to Offsite Emergency Plan Prompt Alert & Notification Sys Addendum for Cooper Nuclear Station ML20214W0111986-08-22022 August 1986 Rev 2 to Procedures Generation Package ML20211B4851986-07-31031 July 1986 Draft Rev 3 to Offsite Emergency Plan Prompt Alert & Notification Sys Addendum for Cooper Nuclear Station ML20212B9141986-07-31031 July 1986 Vols I & II of Rev 5 to Inservice Testing Program for ASME Class 1,2 & 3 Components, for Second 10-yr Testing Program ML20211B4751986-06-30030 June 1986 Rev 2 to Offsite Emergency Plan Prompt Alert & Notification Sys Addendum for Cooper Nuclear Station ML20206T6551986-06-12012 June 1986 Rev 13 to Surveillance Procedure 6.3.2.1, Automatic Depressurization Sys Manual Valve Actuation ML20206T6791986-06-12012 June 1986 Rev 23 to Surveillance Procedure 6.3.3.1, HPCI Test Mode Surveillance Operation 1999-05-14
[Table view] |
Text
. .
COOPER NUCLEAR STATION OPERATIONS MAriUA1.'
SURVEILLANCE PROCEDURE 6.3.12.1 DIESEL GENERATOR OPERABILITY TEST
. , 1 l
, 1 I. PURPOSE -
A. To provide detailed instruction for station pe.;sonnel to check oper-ability of DG-1 and DG-2.
II. DISCUSSION A. The primary purpose for checking the diesel generator operability is to ensure that on a loss of power the diesel generator will come on the line and pick up necessary loads to ensure a safe reactor shutdown.
III. REFERENCE MATERIAL A. USAR. ,
- 1. Volume IV,Section VIII, Subsection 5.0, Amendment 9, 13, 14, 15, and 16.
B. Flow Diagrams.
- 1. B & R Drawing 2011; Turbine Oil Purification and Transfer System and Diesel Oil System, Sheet 1.
- 2. B & R Drawing 2077; Diesel Generator Building Service Water, Starting Air, Fuel Oil, Sump System, and Roof Drains.
- 3. Cooper Bessemer.
- a. KSV-46-5.
- b. KSV-47-8.
- c. KSV-48-5.
- d. KSV-51-6. .
C. Vendor Manuals.
I '. Emergency Diesel Generator System Instruction Manual 69-21-1.
D. Electrical Diagrams.
- 1. B & R Drawing 3002; Auxiliary One Line Diagram.
- 2. B & R Drawing 3004; Auxiliary One Line Diagram.
- 3. B & R Drawing 3019; Auxiliary One Line Diagram.
1 8607080240 860630 PDR ADOCK 05000298 p ,
PDR A
Rsvised By/Date Reviewed By/Date Appro ed By/Date Rev Procedure Pa e 1 Of B. Black 2/24/86 R. Brungardt 3/5/86 % J [f6 17 6.3.12.1 6 Pages
- 4. B & R Drawing 3045; control Elementary Diagram.
- 5. B & R Drawing 3058; DC One Line Diagram.
- 6. Cooper Bessemer GS-262-743, Sheets 1 through 6.
- 7. Cooper Bessemer KSV-36-7.
IV. PREREQUISITES A. The diesel generator (DG-1 or DG-2) to be tested is in a standby condition according to System Operating Procedure 2.2.20, Section C.,
with the exception that the diesel generator Breaker Mode switch position to local or remote depending on the location of operation.
B. Establish communications between the Diesel Generator Rooms and Control Room. ,
C. Ensure the plant is in a steady state condition and no other tests in progress on the diesel generators.
V. LIMITATIONS
~
A. Surveillance Requirements - Technical Specifications Section 4.9.A.2.a.
- 1. Each diesel generator shall be started manually and loaded to not <
50% of rated load for no < 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> once each month to demonstrate operational readiness.
B. Administrative Limits.
- 1. All discrepancies shall be recorded in the Shift Supervisor's log.
- 2. Attachments "A" and "B" shall be used to record the test and filed as part of the station records.
- 3. All testing shall be coordinated with the Control Room Operator.
- 4. The diesel generators should be run > 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> at > 50% of rated load when started for other than monthly tests. Monthly test requires >
4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> and > 80% of rated load. ,
- 5. Test only one diesel generator at a time. .
- 6. The diesel fuel oil day tanks will be checked for water af ter each operation of the diesel where the period of operation was I hour or longer.
VI. PRECAUTIONS A. Wear ear protection in the Diesel Generator Rooms whenever a diesel is running.
Proc; dure Number 6.3.12.1 Date c3-4. ) b Revision 17 Page 2 Of 6 Pages
,. i I
l I
B. The service water system must be in operation prior to starting the' diesel engine.
C. Completely synchronize the generators before closing the breakers when-paralleling the unit with an energized bus.
D. Trip Breaker IAF (Breaker IBG) should the main generator trip. and the startup ~ transformer deenergizes (ACB-3306, ACB-3310, and ACB-3312 tripped) while testing the diesel generators.
When reading the U-tube manometer, add the columns together.to obtain E.
the reading.
VII. TEST EQUIPMENT A. Stopwatch.
VII
I. PROCEDURE
A. Diesel Generator Operability Test.
- 1. Obtain permission and ' signature from the Shift Supervisor before performing the test.
- 2. Establish communications between the Diesel Generator Room for the associated diesel to be tested and the Control Room.
Note: Test only one diesel generator at a time.
- 3. Assure that the proper indication for the test condition is dis-played on the safety system status panel.
- 4. Ensure the diesel generator to be tested is in standby condition according to System Operating Procedure 2.2.20, Standby AC Power System (Diesel Generator), Section C.
- a. Check that the engine base lube oil level is between the normal operating level mark and 2" above on the sight glass.
- b. Check that the engine hydraulic speed governor oil level is in the normal band on its site glass.
- c. Check that the jacket water surge tank level is normal.
- d. Check the diesel fuel oil day tank for i normal level between 42" and 58 1/2". To check the level, open diesel generator day tank level test valve DGDO-57 (DGDO-60), check the level, and then close DGDO-57 (DGDO-60).
- 5. The Breaker Mode selector. switch for the diesel generator is in the REMOTE position .on' Bd-C and in the REMOTE position on the diesel generator board for' operation of the diesel generator from the-Control Room.
Procedure Number 6.3.12.1 Data e? /,,-e b Revision 17 Page 3 Of 6~ Pages
-. =- .- . - . . . . . - . . -
t 2
1
- 6. Place the Droop-Parallel switch in the PARALLEL WITH BUS position.
1
- 7. Place the' Unit-Parallel switch in the PARALLEL WITH BUS position.
i j 8. Turn the Synchronizing switch associated with the diesel generator
- to be tested (Breaker IFE or Breaker IGE) to the ON position.
1 4
,. 9. Close Breaker IFE or Breaker IGE.
1 +
i 10. Run the pre-post lube oil pump for about 1 minute before starting the diesel.
I j 11. Turn the diesel generator Start /Stop switch to START and' hold the b
switch in the START position for 2 to 3 seconds after the Running
, light (red) comes on.
i i a. Check and record the starting time to reach , rated voltage and
- frequency (required only for monthly test).
I-
- 12. Verify engine pressures are normal before loading the diesel (refer
, to the limits on Attachment "B").
- 13. Turn the Synchronizing switch _for, the diesel generator breaker to
, be tested (Breaker EGI or Breaker EG2) to the ON position.
1
, 14. Check the speed of the diesel and adjust the speed as necessary to i cause the synchronizing scope to run slow in a clockwise (fast) l direction by adjusting the Governor Control switch on Bd-C to raise j or lower. -
1
- 15. Check the voltage and ensure that it is slightly higher than the bus on which the generator is going to be paralleled by adjusting; 4
the Manual Voltage Control Adjust switch to the LOWER or RAISE ,
position.
l 16. Check that the synchronizing scope is going slow in a clockwise manner, check that the diesel generator voltage is slightly higher than the bus voltage. Close Breaker EGI or Breaker EG2 for the I associated diesel generator 5* before the 12 o' clock position on ;
the diesel generator synchronizing scope on Bd-C.
- *17. Increase the diesel generator load to > 80% of rated load by
, increasing the speed of the diesel with the Governor Control
] switch.
i 1 *18. Run the diesel generator > 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> at 3200 KW or greater load. !
1 Read and record all parameters after 15 minutes, after i t/2 hours. I j and after 3 1/2 hours.
i'
- a. Read the control air pressure- (Local PI located above the overspeed trip) and record on Attachment "B". Notify the Shift l Supervisor if below 22 psi.
1 4
l ?rocedure Number 6.3.12.1 Date' c9 /,,.dk Revision 17 Page 4 Of 6 Pages
- + _ _ - _ _ _ -_ _ _ . _ _ _ . - _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ . _ _ _ _.___u
- b. Check the engine and governor lube oil levels and verify they are above or at normal level. Notify the Shift Supervisor if.
they are below normal level.
- c. Check for external oil leakage, water leakage, and air leakage.
j
- 19. Af ter the diesel has been run the required time, reduce the gener-ator load to 1000 KW and allow the diesel to cool. Observe that the cylinder exhaust temperatures decrease (S 5 minutes).
4
- 20. Reduce the generator load to < 400 KW and adjust the voltage regulator, as necessary, to keep the KVARs low, i 21. Trip open the associated diesel output Breaker EGI or Breaker EG2.
J
- 22. Trip open the associated bus Breaker 1FE or Breaker 1GE.
i
- 23. Place the Droop-Parallel switch to the DEENERGIZED BUS (' AUT0) position.
- 24. Place the Unit-Parallel switch to the DEENERGIZED BUS (AUT0) position.
i 25. Momentarily place the Rated Speed Reset switch to the RESET position.
. Observe the synchronizing scope to verify it is turning -slow in the
! fast rotation. Return the Rated Speed Reset switch to the OFF position.
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- 26. Adjust the diesel generator voltage to slightly higher than bus voltage.
j 27. Place the diesel engine control switch to the STOP position.
j a. Locally check for proper operation of the air intake manifold I butterfly valves located near the turbocharger inner coolers.
j 28. Run the pre-post lube oil pump for 2 to 5 minutes.
,l 29. Place the diesel generator Breaker Mode switch to the AUTO position.
- 30. Verify the diesel generator is returned to the STANDBY condition t
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per System Operating Procedure 2.2.20, Section C.
- 31. Check the day tanks for water by opening the drain'off the bottom ,
j of the nuction strainer for.the fuel pump. .If it is suspected that I water has been carried on, the entire fuel line from the day tank i to the injectors shall be flushed.
- 32. Restore the safety system status panel to the NORMAL position.
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' roc: dure Number 6.3.12.1 Date 3 Sl3 Revision 17 Page 5 Of 6 Pages
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n IX. -ATTACHMENTS
'A. Diesel Generator Operability Test Data Sheets.
B. Diesel Generator Data Sheet.
C. Diesel Generator Extended Run Data Sheets.
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l l?rccedure Number 6.3.12.1 Date d Jo.& Revision 17 Page 6 Of 6 Pages l i
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ATTACIGIENT "A" SURVEILLANCE PROCEDURE 6.3.12.1 DIESEL CENERATOR OPERABILITY TEST i
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) PROCEDURE DG-1 DG-2 A. Diesel Generator Operability Test. XXXX XXXX 3 1. Obtained permission and signature from Shif t Supervisor.
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- 2. Established communications between Diesel Generator Room and ---
XXXX XXXX
- Control Room.
3.. Assured that proper indication for test condition is displayed XXXX XXXX on safety system status panel. - --- - - - - - - - -- '
j 4.
Ensured diesel generator to be tested is in standby condition XXXX XXXX per System Operating Procedure 2.2.20, Section C.
- a. Checked that engine base lube oil level is between normal -------- -XXXX XXXX operating level mark and 2" above on sight glass.
- b. Checked that engine hydraulic speed governor oil level is XXXX X,u x
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in normal band on its site glass. --- ---- ------------
! c. Checked that jacket water surge tank level is normal. .
- d. Checked diesel fuel oil day tank for normal level.
1 5. Verified Breaker Mode selector switch is in REMOTE. ----w--
l 6. Placed Droop-Parallel suitch in PARALLEL WITH BUS.
! 7. Placed Unit-Parallel switch in PARALLEL WITH BUS.
I 8. Turned Synchronizing switch for Breaker 1FE (1GE) to ON.-
l 9. Closed Breaker IFE (IGE). .
j 10.
Ran pre-post lube oil pump for about 1 minute before starting XXXX XXXX diesel. ------------------------- ------- ---- -
i 11. Started diesel. .
Note: Step a. required only for monthly test. XXXX XXXX j a. Starting Time: DG-1: seconds; DG-2: seconds.
XXXX XXXX l
q 12. Verified engine pressures are normal before loading diesel XXXX XXXX
} (refer to limits on Attachment "B"). "
j 13. Turned Synchronizing switch for Breaker EG1 (EG2) to ON.
- 14. Adjusted speed until synchronizing scope is rotating slowly XXXX XXXX j in FAST direction. *
- 15. Adjusted generator voltage slightly higher than bus voltage.
{ 16. Closed Breaker EG1 (EG2).
- 17. Increaced diesel generator load to > 80% and recorded diesel XXXX XXXX generator parameters on' Attachment "B". ---------- --
- 18. Ran diesel generator > 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> at 3200 KW or greater load and XXXX XXXX
! recorded all parameters after 15 minutes, after 1 1/2 hours, XXXX XXXX 1 and af ter 3 1/2 hours. - --- ---- - - --
l 19. Reduced generator load to 1000 KW and allowed diesel to cool XXXX XXXX
(* 5 minutes).
- 20. Reduced generator load to < 400 KW.
- j 21. Tripped open Breaker EG1 (EG2). '
j 22. Tripped open Breaker 1FE (1GE).
i 23. Placed Droop-Parallel switch to DEENERG1 ZED BUS (AUT0). -- --
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' Placed Unit-Parallel switch to DEENERGIZED BUS (AUT0).
- 25. Momentarily placed Rated Speed Reset switch to RESET, then- XXXX XXXX j t o 0 FF . ----- - - - - - - - - - - ------- -- --------------
! 26. Adjusted diesel generator voltage to slightly higher than XXXX XXXX l bus voltage.
I 1 27. Placed diesel engine control switch to STOP. ,
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- ?rocsdure Number 6.3.12.1 Date s ! 9 4, Revision 17 Page 1 Of 2 Pages
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ATTACilMENT "A" SURVEILLANCE PROCEDURE 6.3.12.1 DIESEL CEKERATOR OPERABILITY TEST PROCEDURE DG-1 DG-2
- a. Checked operation of shutdown butterfly valves. .
- 28. Ran pre-post lube oil pump for 2 to 5 minutes.
- 29. Placed diesel generator Breaker Mode switch to AUTO. ------ -----------
- 30. Verified diesel generator is returned to STANDBY condition XXXX XXXX per System Operating Procedure 2.2.20, Section C.
- 31. Verified no water in day tank. ----------- - - - - - - - - - - - - - - - -
- 32. Restored safety system status panel to NORMAL position.
Test Instrument Number:
START STOP KW LOAD
- DG-1 1 80% Load (3200 KW) *
- DG-2 1 80% toad (3200 KW)
- Tschnical Specifications loaded to not < 50% of rated load for no < 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />; Administrative loaded to not < 80% of rated load for no < 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.
I TESTED BY DATE DG-1 -
DC-2 Discrepancies:
Operator /
Date Shift Supervicor / Permission To Start Date Shift Supervisor / Test Complete And Reviewed Date Shif t Supervisor / NCR Written If Required Date Work Item (s) Initiated If Required Rsviewed By /
Date ;
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?rocedure Number A 1L19.1 Date ( 2 - /o . 9 63 Revision 17 Page 9 Of 9 Pages l
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