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 ML20211B4891986-09-30030 September 1986 Rev 4 to Offsite Emergency Plan Prompt Alert & Notification Sys Addendum for Cooper Nuclear Station ML20211B4971986-09-30030 September 1986 Rev 5 to Offsite Emergency Plan Prompt Alert & Notification Sys Addendum for Cooper Nuclear Station ML20214W0111986-08-22022 August 1986 Rev 2 to Procedures Generation Package 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 ML20211B4851986-07-31031 July 1986 Draft Rev 3 to Offsite Emergency Plan Prompt Alert & Notification Sys Addendum for Cooper Nuclear Station 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
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Text
'
, COOPER NUCLEAR STATION OPERATIONS MANUAL -
DIESEL GENERATOR STARTING AIR COMPRESSOR SUR'VEILLANCE PROCEDURE 6.3.12.2 OPEPARILITY I. PURPOSE -
A. To provide a detailed instruction for station personnel to check r
operability and reliability of the ., diesel generator starting air compressors to recharge the air receivers. -
- A. The primary purpose of this test is to ensure that starting air com-pressors will operate to maintain approximately 245 psig in the air receivers to enable the diesels to start or restart as soon as possible.
III. REFERENCE MATERIAL
} A. USAR. '
) 1. Volume IV,Section VIII, Subsection 5.0.
j B. Flow Diagrams. '
- l. B & E Drawing 2011; Diesel Oil System, Sheet 1. .
- 2. B & R Drawing 2077; Diesel Generator Miscellaneous Diagrams.
- 3. Cooper Bessemer Drawing KSV-46-5.
! 4 Cooper Bessemer Drawing KSV-47-8. =
- 5. Cooper Bessemer Drawing KSV-48-5.
- 6. Cooper Bessemer Drawing KSV-51-6, 1
l C. Vendor Manuals.
- 1. G.E. Operations and Maintenance Instruction Volume.
- 2. 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; 4160 V Switchgear Elementary Diagram.
1 I
8607080246 860630
< PDR ADOCK ODOOO2 8 P .
1 Ravised By/Date Reviewed By/Date Approved By/Date Rev Procedure Page 1 Of R. Cardrer 11/26/84 K. Wire 12/27/84 - *I8- P5 11 '6.3.12.2 4 Pages
l 1
- 4. B & R Drawing 3048; Control Elementary Diagram.
- 5. B & R Drawing 3058; DC One Line Diagram.
- 6. B & R Drawing 3065; Air Compressors control Elementary Diagram.
- 7. Cooper Bessemer Drawing G5-262-743, Sheets 1 through 6.
~
- 8. Cooper Bessemer Drawing KSV-36-7.' -
- 9. G.E. Drawing 791F265, Sheet 3.
IV. PREREQUISITES A. Ensure that the diesel generator to be tested is in the standby condi-tion according to System Operating Procedure 2.2.20.
B. Check the oil levels on air compressors 1 and 2.
C. Check the belt tension on the air compressor belts.
D. Check the crankcase oil level on the diesel driven air compressor.
V. LIMITATIONS A. Surveillance Requirements - Technical Specifications Section 4.9.A.2.a.
- 1. During the monthly generator test the diesel generator starting air compressor shall be checked for operation and its ability to recharge the air receivers monthly.
B. Administrative Limits.
- 1. All discrepancies shall be recorded in the Shif t Supervisor's log.
- 2. Attachment "A" 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. ,
VI. PRECAUTIONS A. Use normal precautions when operating rotating equipment.
B. When running the diesel driven air compressor ensure that the electric air compressor breaker is open.
VII. TEST EQUIPMENT A. None. '
Tocadure Number 6.3.12.2 ,
Date /--23 *f2k _, Revision 11 Page 2 Of 4 Pages
VII
I. PROCEDURE
A. Diesel Generator Starting Air. Compressor Operability.
- 1. Ensure that the diesel generator, 1 or 2, is in the standby condi-tion according to System Operating Procedure 2.2.20.
- 2. Display the proper indication of,the safety system status panel.
- 3. Verify that the air compressor selector switch is in 1.
- 4. Open the drain valve on the north air receiver until the air compressor IA (2A) starts at approximately 220 psig.
- 5. Close the drain valve that was opened in Step 4.
- 6. Let air compressor IA (2A) run until air receivet pressure is up to approximately 245 psig. The air compressor should stop automatic-ally. -
- 7. Place the control switch for air compressor IA (2A) to 0FF.
- 8. Open the drain valvo on the north air receiver until air compressor 1B (2B) starts at approximately 220 psig.
- 9. Close the drain valve that was opened in Step 8.
- 10. Let air compressor IB (28) run until air receiver pressure is up to approximately 245 psig. The air compressor should stop automatic-ally.
- 11. Place the control switch for air compressor IA (2A) to AUTO.
- 12. Place the air compressor selector switch to 2.
- 13. Open the drain valve on the south air receiver until air compressor 1B (2B) starts at approximately 220 psig.
- 14. Close the drain valve that was opened in Step 13.
- 15. Let air compressor 1B (2B) run until air receiver pressure is up to approximately 245 psig. The air compressor,should stop automatic-ally.
- 16. Open the breaker for sir compressor 1A (2A) and turn the control switch for air compressor IB (2B) to 0FF.
- 17. Open the drain valve on either receiver until the pressure is 200 psig. -
- 18. Verify that local alarm STARTING AIR PRESSURE LOW.
incedure Number 6.3,12.2 Date [~i$-]f5 Fevision 11 Pane 3 Of 4 Paces
t-1 .19. Verify' annunciator on Bd-C DC-1 (DG-2) TROUBLE.
- 20. Prime the fuel system manually and place the Start button to START for the diesel driven air compressor. When the air receiver pressure gets to 245 psig, stop the diesel driven air compressor. -
, 21. Return the air compressors back to normal, close air' compressor'1A (2A) breaker, and place air compressor control switch IA (2A).to i AUTO. ~'
- 22. Place air compressor control switch IB (2B) to AUTO. This will be i
the normal compressor lineup.
, 23. Check the diesel driven air compressor fuel oil supply tank level.
l 1
and refill if less than half full.
- 24. Restore the safety system status panel to normal'.
IX. ATTACHMENTS j A. Diesel Generator Starting Air Compressor Operability Data Sheet.
1 1
1 i
't i
I i
i l
1 I
l l
I'
- 4 j recedure Dmber 13,._12.2_ Date [~ h [ Revision 11 Page I. Of I. Paces
COOPER NUCLEAR STATION OPERATIONS tiANUAL DIESEL GENERATOR STARTING AIR COMPRESSOR ATTACllMENT "A" SURUEII LANCE PROCEDURE 6.3.12.2 OPERABILITY PROCEDURE
- DG-1 DG-2 A. Diesel Generator Starting Air Compressor Operability. XXXX XXXX
- 1. Ensured that diesel genetator is in standby condition.
- 2. Displayed proper indication of safety syst,em status ---------------------- XXXX XXXX panel. - *
- 3. Verified that air compressor selector switch is in 1.
- 4. Opened drain valve on north air receiver until air --------------- =
XXXX XXXX compressor LA (2A) starts at approximately 220 psig.
- 5. Closed drain valve that was opened in Step 4.
- 6. Let air compressor I A (2A) run until air receiver - =------------------ XXXX XXXX pressure is up to approximately 245 psig.
- 7. Placed control switch for air compressor IA (2A) to XXXX XXXX OFF. ---- - -== - - - = --------------- -
- 8. Opened drain valve on north air receiver until air XXXX XXXX compressor IB (2B) starts at approximately 220'psig. ~
- 9. C l o se d d ra i n va l v e t h a t wa s o p e n e d i n S t e p 8 . ----------------------------
- 10. Let air compressor IB (28) run until air receiver XXXX XXXX pressure is up to approximately 245 psig; compressor XXXX XXXX stops automatically. ---------------==- ==- - ---- ----= - -----
- 11. Placed control switch for air compressor lA (2A) to XXXX XXXX AUTO.
- 12. Placed air compressor selector switch to 2. ------------------------------
- 13. Opened drain valve on south air receiver until air XXXX XXXX compressor IB (2B) starts at approximately 220 psig.
- 14. Closed drain valve that was opened in Step 13. ------------- -------------
- 15. Let air compressor IB (28) run until air receiver XXXX XXXX pressure is up to approximately 245 psig; compressor XXXX XXXX 16.
stops automatically. ------------------------------------,----------------
Opened breaker for air compressor IA (2A) and turned XXXX XXXX control switch for air compressor 1B (2B) to 0FF.
- 17. Opened d ra in valve on either receiver unt il pres su re --------------------- XXXX XXXX is 200 psig.
18.
Verified that local alarm STARTING AIR PP. ESSURE LOW.
19.
20.
Verified annunc'iator on Bd-G DC-1 (DG-2) TROUBLE. ------------------------
Primed fuel system manually and placed Start button XXXX XXXX to START for diesel driven air compressor and stopped XXXX XXXX diesel driven air compressor at 245 psig. ----- -----------------------
- 21. Returned air compressors back to normal, closed air .
XXXX XXXX compressor IA (2A) breaker, and placed air compressor XXXX XXXX 22.
control switch IA (2A) to AUTO. ------------------------------------------
Placed air compressor control switch IB (28) to AUTO.
- 23. Checked diesel driven air compressor fuel oil supply XXXX XXXX 26.
tank level and refilled if less than half full. --------------------------
Restored safety system status panel to normal.
0 rocedure Mumber 6.3.12.2 Date f~~ ~~ ) Revision 11 Page 1 Of 2 Pages
COOPER NUCLEAR STATION OPERATIONS MANUAL-DIESEL GENERATOR -STARTING AIR COMPRESSOR ATTACIIMENT "A" SURVEILLANCE PROCEDURE 6.3.12.2 OPERABILITY {
Discrepancies:
l .
l en 1
1 Operator /
2 Date
- Shift Supervisor / Permission To Start Date Shift Supervisor / Test Complete And Reviewed
^
Uate Shift Supervisor / NCR Written If Required Date .
Work Item (s) Initiated If Required
- R2 viewed By /
Date 4
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