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
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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
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SUhVEILLANCE PROCEDURE 6.3.6.1 RCIC TEST MODE SURVEILLANCE OPERATION i
- 1. PURPOSE A. To provide a detailed instruction for station personnel to check the reactor core isolation cooling (RCIC) pump flow rate and pressure.
II. DISCUSSION A. The RCIC pump flow controller, flow rate, and discharge pressure are verified during this test by using the RCIC system test flow path.
Pump suction is from the emergency condensate storage tanks, through the RCIC pump, through the test flow line, and back to the emergency condensate storage tanks. If during this test low reactor water level
(> -37") occurs, system initiation signal, the system will return to auto initiation lineup. ,
B. Surveillance Procedure 6.3.6.4, RCIC Turbine Test Potentiometer And Pump Operability, can be performed to check the operation of the test potentiometer if so desired.
III. REFERENCE MATERIAL A. USAR.
- 1. Volume II, Section IV, Subsection 7.0.
B. Flow Diagrams.
- 1. B & R Drawing 2040; Flow Diagram, RHR System.
- 2. B & R Drawing 2041; Flow Diagram, Reactor Building Main Steam System.
- 3. B & R Drawing 2043; Flow Diagram, RCIC System.
- 4. B & R Drawing 2044; Flow Diagram, HPCI System.
C. Vendor Manuals.
- 1. G.E. Operations and Maintenance Instruction Volume V, Subgroup RCIC. ,
- 2. RCIC Turbine Instruction Manual E-66-31-12,
- 3. RCIC Pump Drive Manual E-66-31-83.
D. Electrical Diagrams.
- 1. B & R Drawing 3007; Auxiliary One Line Diagram, Sheet 6.
8607080218 860630 ~7 PDR ADOCK 05000298 P PDR Ravised By/Date Reviewed By/Date J ppr ed By/Date Rev Procedure Page 1 Of 4:rf M . wmmO T. Florence 11/11/85 R. Brungardt 11/20/85. gf,y f _gg- 15 6.3.6.1 ~6 Pages e _ x- 5
- 2. B & R Drawing 3058; DC One Line Diagram.
- 3. B & R Drawing 3139; Reactor Building Lighting Panel Schedules.
- 4. G.E. Drawing 729E517BC; Functional Control Diagram. ,
- 5. G.E. Drawing 791E264; Elementary Control Diagram, Sheets 1 Through 9.
E. Miscellaneous.
- 1. CNS Inservice Testing Program.
IV. PREREOUISITES A. Instrument and service air system in operation.
B. Emergency condensate storage tank level normal.
C. Suppression pool level normal.
D. RCIC area FCU available and in service (preferred).
V. LIMITATIONS A. Surveillance Requirements - Technical Specification Sections 4.5.D.1.b.,
-4.5.D.1.d., 4.5.D.1.e., 4.5.G.1., 4.5.H., and 4.6.G. (IST).
- 1. RCIC subsystem testing shall be performed as follows:
- a. Pump operability is once/ month,
- b. Flow rate at
- 1000 psig steam pressure is once/3 months (will be done monthly).
- c. Flow rate at
- 150 psig steam pressure is once/ operating cycle.
- d. Discharge piping filled is once/ month,
- e. Unit coolers. operability checked during testing of the associ-ated pumps.
- 2. With the surveillance requirements of Technical Specifications Section 4.5.D. not performed at the required intervals due to reactor shutdown, a reactor startup may be conducted provided the appropriate surveillance is performed within 48 hours of achieving 150 psig reactor steam pressure.
B. Administrative Limits.
- 1. All discrepancies shall be recorded in the Shif t Supervisor's log.
'rocedure Number 6.3.6.1 Date n.4/ E5 Revision 15 Page 2 Of 6- Pages
- 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.
VI. PRECAUTIONS -
A. Assure positive suction is available to the RCIC pump from the emergency condensate storage tank.
B. During periods of standby status, the flow control transfer switch shall remain in the AUTO position and the flow controller shall remain set for 100% flow.
C. During any controlled operation of the pump, monitor closely for unusual vibration, oil pressure, oil temperature, or other abnormal conditions.
D. The turbine should not be started or operated with oil temperature <
60*F or > 160*F.
E. The pump, turbine, and associated equipment must be free of all obstruc-tions and foreign material at all times.
F. Do not over-pressurize the RCIC low pressure pipe in the test return line to the emergency condensate storage tanks. The manual return valve must be open before the RCIC system is placed in operation.
G. Warm the RCIC steam supply line slowly when placing the system in service.
H. During operation of the RCIC system, closely monitor the suppression pool temperatures and place the Suppression Pool Cooling Mode of the RHR system in operation, as necessary, to maintain the pool temperature
< 95'F (can go to 105'F during testing but must be returned to < 95*F within 24 hours).
I. Obse rve that the gland seal condenser condensate pump always' has a discharge path valved into operation or that the pump ' breaker is deenergized.
J. Do not exceed the manufacturers recommended startup suction strainer differential pressure. .
K. During the 150 lbs. reactor steam pressure pump test, insure that the rea-tor heatup/cooldown rates are not exceeded.
VII. TEST EOUIPMENT A. Stopwatch.
?roccdure Number 6.3.6.1 Date //. 2/. 66 Revision 15 Page 3 Of 6 Pages
'II. PROCEDURE Note: For Inservice Testing, the following check valves shall have been exercised upon a successful surveillance test. A successful test is one which has no discrepancies; RCIC-CV-10, RCIC-CV-12, RCIC-CV-13, RCIC-CV-15, RCIC-CV-18, RCIC-CV-19, RCIC-CV-20, and RCIC-CV-21.
Note: Recording of the exercised check valves (IST Review) shall be recorded at least once every 3 months (Engineer).
Note: Those valves followed by (IST) shall be timed on a quarterly basis.
A. RCIC Test Mode Surveillance Operation.
- 1. Obtain permission and signature from the Shift. Supervisor _before starting the test. -
- 2. Assure the proper indication for the test condition is displayed on the safety system status panel.
- 3. Open RCIC-189 and RCIC-190 (high point vent valves).
4 Observe water flows freely. ,
- 5. Close RCIC-189 and RCIC-190 (high point vent valves).
- 6. Open RCIC-M0-33.
- 7. Start the barometric condenser vacuum pump on panel 9-4 by placing the control switch to the START position.
- 8. Open RCIC-MO-30.
- 9. Assure that RCIC-MO-18 is open.
Note: The RCIC turbine should not be operated at speeds less than the minimum design speed of 2200 rpm.
- 10. Open RCIC-MO-132 by placing the control switch on panel 9-4 to the OPEN position.
- 11. Start the RCIC turbine by placing the control switch for RCIC-MO-131 to the OPEN position (IST). ,
- a. Check that RCIC-AO-34 and RCIC-AO-35 close.
- b. Check that RCIC-AO-12 and RCIC-AO-13 close.
- 12. CS Room FCU 1-FC-R-1F.
- a. Verify locally that FCU 1-FC-R-1F starts.
?rocsdure Number 6.3.6.1- Date //. O/.RS Revision- 15 Page 4 Of: '6- Pages-
- b. Observe REC-TCV-864 opens to control temperature.
- 13. Check that RCIC-MO-27 opeos and closes, as necessary, to main.ain a minimum flow of 80 gpm increasing and 40 gpm decreasing (+125 psig permissive).
- 14. For the 1000 psig reactor pressure test performed monthly, assure that either 400 gpm is reached or the data is on or to the right of the dotted line on Attachment "C" for reactor conditions and record the data. The pressure should be within 10% of 1170 psig and the flow should be at least 395 gpm to satisfy the Technical Specifi-cation requirements.
Note: Ensure the controller output signal does not indicate > 100.
- 15. For the.150 psig reactor pressure test performed once each cycle, assure that either the flow of 400 gpm is reached or the data is on or to the right of the dotted line on Attachment "C" for reactor conditions and record the data. 'The pressure should be within 10%
of 430 psig and the flow sho'ild be a't least 245 gpm to satisfy the Technical Specification requirements.
- 16. Record the temperature on Attachment "B".
- 17. Trip the turbine manually.
- 18. Close RCIC-M0-30 by placing the control switch to the CLOSED position.
- 19. Close RCIC-MO-33 by placing the control switch to the CLOSED position. '
- 20. Assure that RCIC-MO-27 (minimum flow) closes.
- 21. Close RCIC-MO-131 by placing the control switch to the CLOSED position (IST).
- a. Check that RCIC-AO-34 and RCIC-AO-35 open.
- b. Check that RCIC-AO-12 and RCIC-AO-13 open.
- 22. Verify that RCIC-FIC-91 is in AUTO and set at 400 gpm.
- 23. Stop the barometer condenser vacuum pump by placing the control switch to the STOP position.
24 Close RCIC-M0-132 by placing the control switch to the CLOSED position.
- 25. Verify that the RCIC turbine trip and throttle valve is automatic-ally reset.
I
'rocsdure Number 6.3.6.1 //. ? > 9,5 Revision 15 Page 5 Of- 6 Pages lDate
. _ m .
- 26. Assure that the RCIC system is returned to the standby status as per System Operating Procedure 2.2.67.
- 27. Check the suppression pool temperature and place the RHR system in the Suppression Pool Cooling . Mode if necessary (105'F maximum during testing, must be < 95*F within 24 hours). -
- 28. Place the safety system status panel to normal operation.
- 29. Notify the Shift Supervisor that the' test has been completed.
IX. ATTACHMENTS A. Not Applicable.
B. RCIC Test Mode Surveillance Operation Data Sheets.
C. RCIC Discharge Pressure Vs. RCIC Discharge Flow Curve.
1 J
k
- - 'rocadure - Number 6.3.6.1 Date // - O / 9,5 = Revision Page 6 Of. 6' Pages o.
. .- - +- ,
m.... ......u.... ..........,.m..uno ATTACHMENT "B" SURVEILLANCE PROCEDURE 6.3.6.1 RCIC TEST MODE SURVEILLANCE OPERATION 4
FUNCTIONAL TEST Mote: For Inservice Testing, the following check valves shall have been exerci. sed upon a successful surveillance test. A successful test is one which has no discrepancies; RCIC-CV-10, RCIC-CV-12, RCIC-CV-13, RCIC-CV-15, RCIC-CV-18, RCIC-CV-19, RCIC-CV-20, and RCIC-CV-21.
Note: Recording of the exercised check valves (IST Review) thall be recorded at least once every 3 months (Engineer).
Nota: Those valves followed by (IST) shall be timed on a quarterly basis.
IST TIME IN PROCEDURE TIME LIMIT SECONDS DATA CHECK A. RCIC Test Mode Surveillance Operation.. XXXXXXXX
, 1. Obtained permission te start test.
- I 2. Assured proper indication for test condition is -- --- - -- XXXXXXXX displayed on safety system status panel. "
- 3. Opened RCIC-189 and RCIC-190.
4 Observed water flows freely. ----- -- ----------- --
- 5. Closed RCIC-189 and RCIC-190.
; 6. Opened RCIC-M0-33. '
j
- 7. Started barometric condenser vacuum pump. ------- - -
- 8. Opened RCIC-M0-30.
] 9. Assured that RCIC-M0-18 is open.
- 10. Opened RCIC-MO-132. ------- - ------ ------ -
- 11. Started RCIC turbine by placing control switch
- for RCIC-MO-131 to OPEN position (IST). l1.25See l
, a. Checked that RCIC-AO-34 and RCIC-AO-35 close. -- ----
i b. Checked that RCIC-AO-12 and RCIC-AO-13 close.
- 12. CS Room FCU 1-FC-R-1F. XXXXXXE
- a. Verified FCU 1-FC-R-1F starts. ---- ---- -------
i b. Observed REC-TCV-864 opens.
I 13. Checked that RCIC-MO-27 maintains minimum flow.
- 14. Assured that either 400 gpm is reached or data ----
XXXXXXXX
, is on or to right of dotted line on Attachment XXXXXXXX "C" for reactor conditions and reccrded data XXXXXXXX (1000 psig test). -- -- ---- --------- '
- 15. Assured that either 400 gpm is reached or data XXXXXXXX is on or to right of dotted line on Attachment XXXXXXXX ,
"C" for reactor conditions and recorded data ------- -
XXXXXXn 1 (150 psig test). '
l
- 16. Recorded temperature.
- 17. . Tripped turbine manually. - --
- 18. Closed RCIC-MO-30.
19.
Closed RCIC-MO-33.. '
- 20. Assured that'RCIC-M0-27 (minimum flow)' closes. -----
- 21. Closed RCIC-MO-131 (IST).
- a. Checked that RCIC-AO-34 and RCIC-A0-35'open.
l5.25Sec l
- b. Checked that RCIC-AO-12' and RCIC-AO-13 open. -------- ------ -
i .
. t
. Procedure Number 6.3.6.1 Date //. O f - 253 Revision '15 Page 1 Of 3- Pages
uvv i.a ..uu na o i n i tv.. v u.uuavoo nnaunu l
AI'TACHMENT "B" SURVEILLAI'CE PROCEDURE 6.3.6.1' RCIC TEST MODE SURVEILLANCE OPERATION i
I FUNCTIONAL TEST IST TIME IN PROCEDURE TIME LIMIT SECONDS DATA CHECK
- 22. Verified RCIC-FIC-91 is in AUTO and set at 400 gpm.
- 23. Stopped barometer condenser vacuum pump.
24 Closed RCIC-M0-132. -------- ---- --------
- 25. Verified RCIC turbine trip and throttle valve is XJCCCGXX
, au'tomatically reset.
- 26. Assured RCIC system is returned to standby status. --- - - - - -
- 27. Checked suppression pool temperature.
- 28. Placed safety system status panel to normal operation.
- 29. Notified Shift Supervisor test has been completed. -- ,
TEST
SUMMARY
i TURBINE AND OBSERVED PUMP TEMPERATURES DATA MAXIMUM PERFORMED BY Oil Temperature *F 160*F tust Bearing *F 180*F FLOW PUMP PUMP REQUIRED DISCllARGE REACTOR TECH. SPEC.
FREQUENCY FLOW FROM CURVE C PRESSURE PRESSURE LIMIT INITIALS Once/ Month And 400 gpm Rx Once/3 Months 150-1000 psi Once/ Operating 400 gpm Rx Cycle ~150 psi WATER FLOW OBSERVED FROM TECH. SPEC. LIMIT INITIALS Discharge-Piping Vented At High Valves RCIC-189 And RCIC-190 Point And Water Flow Observed l ..
FAN COOLING UNIT TECH. SPEC. LIMIT IhtTIALS
- FC-R-1F Operates Normally Unit Cooler Checked For Operability Test Instrument Number
i i
l Procedure Number 6.3.6.1 Date / /. ! l ?$ Revision 15 Page 2 Of 3- Pages l
ov o . ., .. .. . . n u v. . u . . u o.. s . .ac. o n o ATTACHMENT "B" SURVEILLANCE PROCEDURE 6.3.6.1 RCIC TEST MODE SURVEILLANCE OPERATION d
FUNCTIONAL TEST t Discrepancies: -
!. I 4
I r
Operator /
Date-Shift Supervisor / Permission To Scart Date ,
Shift Supervisor / Test Complete'And Reviewed Date-Shift Supervisor / NCR Written If Required Date .
Work Item (s) Initiated If. Required Raviewed By /
Date IST Review / Record Status.On Valve Summary Date. Listing
[Proctdure Number 6.3.6.1 'Date- /'-2/-P.5 ' Revision -15 Page 3 -Of 3 Pages
. ATTACllMENT "C" - RE"ISION 15 SURVEILLANCE PROCEDURE 6.3.6.1
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