Letter Sequence Other |
---|
|
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
|
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] |
|
---|
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
..~m., m o o o . .. m o uv.. .sn u v.. ., ..
f dSURVEILLANCE FROCEDURE 6.3.4.1 CS TEST MODE SURVEILLANCE OPERATION
.\Q3
.v
- 1. PURPOSE A. To provide detailed instructions for station personnel to assess the operational readiness of the core spray (CS) pumps.
II. DISCUSSION A. The CS pumps operability, flow rate, pressure, and vibration amplitude are verified during this test by using the CS system test flow path.
Pump suction is from the torus, through the CS pump, through the flow test line, and back into the torus. If during this test, either low reactor water level (-145.5") or high drywell pressure (+2 psig) occurs, which are the system initiation signals, the CS system test valve CS-M0-26 will close. When this Surveillance Procedure is run for only the monthly pump operability or to prove operability when another safety system is declared inoperative, Data Sheets for Pump A and Pump B, Pages 2 and 3, need not be completed.
III. REFERENCE MATERIAL j A. USAR.
- 1. Volume II,Section VI. Subsection 4.3.
- 2. Volume II,Section VI, Subsection 5.2.4.
- 3. Volume III,Section VII Subsection 4.3.4.
B. Flow Diagrams.
- 1. B & R Drawing 2045; CS and SLC System.
= -
C. Vendor Manuals.
I
- 1. G.E. Operations and Maintenance Instruction Volume V; CS System.
\
- 2. G.E. Operations and Maintenance Instruction Volume IX, Part I, CS System.
- 3. CS Pump Instruction Manual E-66-31-33, Byron Jackson Pump Company.
D. Electrical Diagrams.
- 1. G.E. Drawing 791E265; Elementary Diagram.
- 2. G.E. Drawing 729E402; Functional Control Diagram.
8607080210 860630
-sh (jg w PDR P
ADOCK 00000298 PDR A
R: vised By/Date Reviewed By/Date prov d By/Date Rev Procedure Page 1 Of L. Jones 12/24/85 R. Brungardt 1/24/86 ,
- - AS-n 18 6.3.4.1 6 Pageu
I .
.~ .
Ah 3. B & R Drawing 3059; DC Panel Schedules.
- y. .3
- 4. B & R Drawing 3002; Auxiliary One Line Diagram.
- 5. B & R Drawing 3007; Auxiliary One Line Diagram.
- 6. B & R Drawing 3010; Vital One Line Diagram. ,
- 7. B & R Drawing 3139; Reactor Bizilding Lighting Panel Schedule.
- 8. B & R Drawing 3024; 4160 V Switchgear Elementary Diagram.
E. Maintenance Procedures.
- 1. Maintenance Procedure 7.2.36.
F. Miscellaneous.
- 1. Inservice Testing Program.
G. CIS Engineering Procedures.
- 1. QIS Engineering Procedure 3.9.
IV. PREREOUISITES L.'- Q A. Support Systems.
9 1.
The condensate storage and transfer system available for keeping the CS system piping full of water.
- 2. The REC system available for area coolers.
- 3. The area FCUs available for service.
B. Power Supplies Energized.
Note: Read Precautions before energizing equipment.
- 1. 4160 V Critical Bus IF'for:
- a. CS Pump 1A, Breaker CSP 1A. .
- 2. 4160 V Critical Bus 1G for:
-a. CS Pump 1B, Breaker CSPIB.
- 3. 460 V Critical MCC-Q for:
- a. CS-MO-7A, Breaker SC.
- b. CS-MO-11A, Breaker SD.
-I Percedure Number 6.3.4.1 Date / dd.8Io Revision 18 Page 2 Of 6 Page.
- c. CS-MO-12A, Breaker 6A.
. i.3/ d. CS-MO-26A, Breaker 10B.
- e. CS-MO-5A, Breaker 6D.
- f. CS-MO-15A, Breaker 3A.
1 4. 460 V Critical MCC-Y for:
- a. CS-MO-7B, Breaker SA. *
- b. CS-MO-11B, Breaker SB. '
I
- c. CS-MO-12B. Breaker'5C. I
- d. CS-MO-26B,. Breaker 10C.
i
- e. CS-MO-5B, Breaker SD.
- f. CS410-15B, Breaker ID.
- 5. 125 V DC Panel AA2, Breaker 6; Feed to Panel 9-32 for Logic Bus A.
- 6. 125 V DC Panel BB2, Breaker 8; Feed to Panel 9-33 for Logic Bus B.
! 7. 125 V DC Panel AA3, Breaker 6; 4160 V Critical Bus IF Control 1 A** Power * -
I Ilh
- 8. 125 V DC Panel BB3, Breaker 6; 4160 V Critical Bus 1G Control Power.
l 9. 120 V AC Panel SPR-1, Breaker 7; CS Pump 1A Motor Space Heater.
4 t
- 10. 120 V AC Panel SPR-1, Breaker 7; CS Pump 1B Motor Space Heater, s
3 11. 120/240 V AC Panel CCPIB, Breaker 1; Feed to Board 9-3.
2
- 12. 120/240 V AC Panel CCP1A, Breaker 3; Feed to Board 9-19.
r V.' LIMITATIONS i
\
A. Surveillance' Requirements - Technical Specification Sections 4.5.a.1.b.,
4.5.a.1.d., 4.5.H., 4.5.G.1., and 4.6.G (IST).
- 1. Once per month check the pump operability.
- 2. Once per 3 months check the pump flow rate, pressure, and vibration. ,
- Each pump shall deliver 4720 gym against system head corresponding '
to a differential pressure > 113 psi between the reactor vessel and the primary containment. ,
- w.
! m'sw i i !
i I
i Prec dure Number 6.3.4.1 Date /-M ~ 2 0$ Revision 18 P, age _ 3 Of 6 Pages <
J e # 2 4
. e e F
F
4
'~
3._ The unit coolers for the CS pumps will be checked for operability
- during surveillance testing of the associated pump.
({..Q. .g - -
- 4. The pump discharge line high points shall~be vented monthly and j - water flow observed.
j .B. Administrative Limits.
- 1. All discrepancies shall be recorded in the Shif t Supervisor's log. .
I s 2. Attachment "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.-
- A. There are no interlocks between a closed pump suction valve and ' the pumps, ensure suction path for the~ pump.
1 2
B. Avoid pump runout. The rated CS pump motor current is'157 amps. Total-discharge pressure should not be < 240 psi.
VII. TEST EOUIPMENT j
j A. Model 306 or 308 hand-held IRD vibration meter.
l .g g
- h. Model 816, data collector and Model 820 vibration analyzer (Engineering
,, Analysis).
J j VII
I. PROCEDURE
J 4 Caution: If the restricting orifice (RO-29A and R0-29B) is not installed
- in the test line, pump runout and resultant damage may occur if 1
test valve CS-MO-26A (CS-MO-26B) is opened' too far. Refer to j Precautions (Section VI.) of this procedure.
Note: For inservice testing, the following check valves shall have been 4 exercised upon a successful surveillance tast. A successful test is l
one which has no discrepancies; _CS-CV-10, CS-CV-11 CS-CV-12, CS-CV-13, CS-CV-14, and CS-CV-15.
! Note: Recording of the exercised check valves (IST Review) shall be recorded at least once every 3 months (Engineer).
i A. CS Test Mode Surveillance Operation.
- 1. Obtain permission and signature from the Shif t Supervisor before
, starting the test.
j
{ 2. Assure the proper indication for the test condition is displayed on i the safety system status panel. ,
i e
.w i
Prec: dure Number 6.3.4.1 Date / -? q .2 (c Revision- 18 Page 4 Of 6 l' ages
. . -t
- 3. Open vent valve CS-136 (high point vent) .
- 4. Observe that water flows freely.
- 5. Close vent valve CS-136.
. 6. Open vent valve CS-138 (high point vent).
- 7. Observe that water flows free,1y.
- 8. Close vent valve CS-138.
. 9. Check valve CS-MO-7A (CS-MO-7B) open.
- 10. Check valve CS-MO-5A (CS-MO-5B) open.
- 11. Close valve CS-MO-llA (CS-MO-11B) (CS system injection) .
Note: Valve CS-MO-llA (CS-MO-ilB) (CS spray injection) will reopen if an auto initiation occurs.
- 12. Record Pump A (Pump B) inlet pressure.
- 13. Position CS Pump A (Pump B) control switch on panci 9-3 to start.
- 14. CS Room FCU HFC-R-lF (HFC-R-lE).
- Qf
- a. Verify locally that FCU HFC-R-lF (HFC-R-lE) for CS Room A (CS Room B). starts.
- b. Observe REC-TCV-864 (REC-TCV-861) cpens to control temperature.
- 15. Open test valve CS-M0-26A (CS-MO-26B) until a system flow approxi-i mately equal to the reference value (> 4720 gpa for monthly pump l operability) is reached as indicated on FI-14-50A (FI-14-50B) on panel 9-3, verify that CS-MO-5A (CS-MO-)B) is closed, and hold for 5 minutes.
4 f Note: It is not necessary to hold for 5 minutes if the test is run for monthly pump operability or to prove operability because (
- another safety system is inoperable.
- 16. Record the required data on Attachment "B" for Pump A (Pump B).
Note: Pump A and Pump B data sheets need to be completed for only the quarterly flow test.
- 17. Close test valve CS-MC-26A (CS-MO-26B). ;
- 18. Verify that CS-MO-5A (CS-MO-5B) opens.
- 19. Position CS Pump A (Pump B) control switch on panel 9-3 to stop.
'Ga .
Prrc dare Number 6.3.4.1 Date / -3/) 8 la Revision 18- Page 5 Of 6 Pages
' ~
i
- 20. Open valve CS-MO-11A (CS-MO-11B) (CS system injection) .
- 21. Ensure the CS system is ready for standby operation as per System Operating Procedure 2.2.9,Section VII.B.
- 22. Restore the safety system status panel to normal.
- 23. Notify the Shift Supervisor that the test is complete.
II. ATTACHMENTS
l B. CS Test Mode Surveillance Operation Data Sheets.
j C. Vibration Data Point Drawing For Pumps A And B.
I
- [A
\
L %.
k, .cc
- fr:c: dure Number -
6.3.4.1 Date /-do-#6 Revision 18 Page
-6 Of 6' Pages 4 o
,- -e- .
e - ,n-_,- ,.-
} v - -
v . . . w .. ., ..n.....-
.,a..-..
m, o . .. ..o-.
6.3.4.1 CS TEST MODE SI'RVEILLANCE OPERATION CHMEKT "B" SURVEILLANCE PROCEDURE FUNCTIONAL TEST JSSYSTEMj j 'j B . .e A w
. s PROCEDURE XXX XXX ..
test. d _
- 1. -----
2.
Obtained permission to startAssured proper indication for test condition isXXX_
displaye *-
on safety system status panel. - - --
' XXX_
XXX .
- 3. Opened CS-136.
^ f
- 4. Observed water flows freely.
XXX
- 5. Closed CS-136. - - _XXX 6 .. Opened CS-138.
- 7. Observed water flows freely. - - -
-- XXX i hW
- 8. Closed CS-138. - _
9 Checked CS-MO-7A (CS-MO-7B) open. -- _
10.
Checked CS-MO-5A (CS-MO-5B) open. Closed CS-MO-11A (CS-MO-11B) . - __
- 11. _
- 12. Recorded Pump A (Pump B) inlet pressure. -
_XX X XXX_
13.
Positioned CS Pump A (Pump B) control switch to start. -
XXX_
- 14. CS Room FCU HFC-R-lF (HFC-R-1E). - _XXX Verified FCU HFC-R-1F starts.
^
- a. -- XXX Verified FCU HFC-R-1E starts. XXX
- b. Observed REC-TCV-864 opens. - XXX XXX Observed REC-TCV-861 opens. ~ -
,]XXX XXX XXX_
9),
- 15. Opened CS-MO-26A (CS-MO-26B) until a system~XXX ,
flowappro XXX XXX_
for monthly pump operability) is reached for Pump -
s.{g/ A (Pump B) , verified CS-MO-5A (CS-MO-5B) is closed, ~
and held for 5 minutes for quarterly flow test. --
- 16. Recorded required data. ~ -
- 17. Closed CS-MO-26A (CS-MO-26B).
- 18. Verified CS-MO-5A (CS-MO-5B) opens. -
19.
Positioned CS Pump A (Pump B) control switch to stop. -
~
- 20. Opened CS-MO-11A (CS-MO-11B) . Ensured CS system is [ready for sta 21.
j
- 22. Reptored safety system status panel to normal. i
- 23. Notified Shif t Supervisor test is complate. !
\
INITIALS _
WATER FLOW TECH. SPEC. LIMIT OBSERVED FROM Discharge Piping At High Point Valve CS-136 xu_xxxxxXXXXXXXXX And Water Flow Observed a Valve CS-138 xxxxxxxx.tttttttd INITIALS __
TECH. SPEC. LIMIT
~
FAN COOLING UNIT Unit Coolet; Checked For.
Operates Normally_
HFC-R-1E Operability a 1 Operates Normally 3 I HFC-R-1F l I
> (~%71 l .Page. .t Of _ - 4 _Pages 6.3.4.1 Date /.20'R Ir _ Revision 1 2racedure Number
_._ _ _'_ -momwres;mpfgygg-gg
m I e
@ @ @ g n
U
= -
n
- $ CS PUMP A ,
'E
- n 4-m Note: This Data Sheet need not be completed when procedure is being performe:1 for monthly pump operability or to N P' s
- prove operability when another safety system is declared inoperable. {
M m
REFERENCE ACCEPTABLE REQUIRED m PARAMETERS ACTUAL VALUES RANCE ALERT RANCE ACTION RANGE INITIALS $ c
.o Pump Inlet Pressure O &
$ (Before Start) Pib 6.5 psig None Required None Required None Required E [
4 10 < Pi < 13 psig $ -
i Pump Inlet Pressure 10" lig Vac < Pi 20" ilg vac < Pi < Pi < 20" Hg Vac E (After Start) Pia 4.4 psig < 10 psig 10" lig Vac Pi > 13 psig r D Pump Discharge Pressure
% Pd 315 psig None Required None Required None Required 3
h Pump Flow Rate Q* 4720 gpm See Note 1 See Note.1 Q < 4720 gpm j Pump Vibration Amplitude .
~
[
Velocity In/Sec** (Pt 1) V C .314 In/See .314 < V < .628 V > .628 c Pump Vibration Amplitude p j* Velocity In/Sec** (Pt 2) V < .314 In/Sec .314 < V < .628 V > .628 n
" [
f Pump Differential 281 < AP < 290 AP < 281 psig ;
g Pressure AP 312 290 < P < 318 318 < AP < 321 AP > 321 psig m C
g Amps < 120 $ ['
Amps 143 XXXXXXXXXXXXXXXX XXXXXXXXXXXXXXXXX Amps > 157 :c g
- E O E m a r
.i' m
- io m 5 ** Maintenance Procedure 7.2.36 outlines the procedure to be used for taking vibration readings. Attachment "C" shows where to take these readings.
" . O Note _1: The Reference Value for flow, Q, must Le duplicated to provide a method to analyze the other parameters. o O m C
e V # y i
..}0 tO .
m._ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ . -,
.o
@ O j
- l l-G.
'n en y e t z CS PUNP B :
N C ,
t E
i . .
This Data Sheet need not be completed when procedure is being performed for monthly pump operability or to C
I i
Note:
prove operability when ano*her safety system is declared inoperable.
{
~
) O REQUIRED m REFERENCE ACCEPTABLE l ALF"T RANGE ACTION RANGE INITIALS $ !
f y PARAMETERS ACTUAL VALUES RANGE O !
Pump Inlet Pressure P
W o
(Hefore Start) Pib 6.1 psig None Required None Required 10 < pi < 13 psig None Required {
en 3 u Pi < 20" lig vac l, 10" lig Vac < Pi 20" lig Vac < Pi <
} Pump Inlet Pressure 10" lig Vac Pi > 13 psig l 3.5 psig < 10 psig J (After Start) Pia .
7 Pump Discharge Pressure None Required None Required
.G Lo Pd 320 psig None Required ,
o -
i 4750 gpm See Note 1 See Note 1 Q < 4720 gpm F l Pump Flow Rate Q* "
1
)
Q Pump Vibration Amplitude
~
l Velocity In/Sec** (Pt 1) V < .314 In/Sec .314 < V < .628 V > .628
$ - l
+ Pump Vibration Amplitude V > .628 n i Velocity In/Sec** (Pt 2) V < .314 In/Sec .314 < V < .628
- f 283 < AP < 293 AP < 283 psig l
- ;i Pumn-Differenttal AP > 324 psig M
Pressure AP 315 293 < AP < 321 321 < AP {.324 '
},. E Amps < 120 $
( @ 142 XXXXXXXXXXXXXXXX XXXXXXXXXXXXXXXXX Amps > 157 :c .
Amps 8
? ~ '"
o2 3
b, E
, , . s Attachment "C" shows
.U **llaintenance Procedure 7.2.36 outlines the procedure to be used for taking vibration readings. F G
.pp%y" where to take these readings.
S
- se o l$ Note 1: The Reference Value for flow, Q, must be duplicated to provide a method to analyze the other parameters, ?
0 5 $
l lM ,
. IRD Vibration Meter Instruinent Number: '
]
e x m
'h .?
M ;S ie w
+
d
wo o. .. .. u u .. ,, . o o v.. v . ,, i . v.. ., . .,.. . o m
. 'ATTACEMENT "B" SURVEILLANCE PROCEDURE 6.3.4.1 CS TEST MODE SURVEII. LANCE OPERATION
.Q h.-> FUNCTIONAL TEST Discrepancies:
4 l'
Operator /
Data Shift Supervisor / '
Permission To Start Date Shift Supervisor / Test Complete And Reviewed Date Shift Supervisor \
/ NCR' Written If Required Date Work Item (s) Initiated If Required Rsviewed By /
b Date IST Review / Analysis Of Test Data Comparing To Date Allowable Ranges 4
IST Review / Summary Of Corrective Actions If Date Required IST Review / Subsequent ST And Confirmation Of Date Operational Adequacy
(.. >*
. , . . .~ - --
Proccdure Number 6.3.4.1 Date / . J0 2 /a Revision IR Page 4 Of a Pages , _
. _ - _ - _ _ _ _ ,I ATTAC10tE'dT "C" SUR','EILLid!CE PROCEDURE I 6. 3 . !+ .1 CS TEST MODE SURVEILLA?'CE OPERATION ._
C PIDf?S 1A AND 1B
/
t i
f 1 i l
o u,' -
,g ' Horizontal *
.gl/l,
- Point 1 Vertical -
e
_ / Vibration Data p 1nt z g
, j , ,f' i x. -
I Discharge -* _
1 I / 4--Suction
[
Vibration Data Point
- All Points Shown Rotated 180* From-Actual s; -
k ,. v< a 3 I
Prscedure Number 6.3.4.1 Date /-30 8b Revision 18 p,g, 1 ,f t ,
i
~
'* f ^ '
+= 7? ' .*"'_J , * ('. # ; ',* ,
l
+ i . ;# .'[' j ,