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
[Table view] |
Text
,
uuur t.n . . o u i. c.n n si,.aava ve r.nn a tuas ruu.oni-SURYEILLANCE PROCEDURE SLC MANUAL ISLTIATION IEST TANK TO REACTUh 6.3.8.4 VESSEL I. PURFOSE A.
To provide a detailed instruction for station personnel to check the SLC pump flow rate to the reactor vessel.
II. DISCUSSION A.
The SLC pump flow rate is verified during this test by using the SLC test tank.
The flow path during this test is from the SLC test tank, which is filled with demineralized water, through one pump and one squib valve to the reactor vessel. The' system is initiated from the Control Room to fire one squib valve.
III. REFERENCE MATERIAL A. USAR. .
- 1. Volume I,Section III, Subsection 9.0.
B. Flow Diagrams.
1.
B & R Drawing 2045; Core Spray and Standby Liquid Control System.
2.
B & R Drawing 2038; Reactor Building Floor and Roof Drain Systems.
- 3. B & R Drawing 2029; Demineralized Water System.
C. Vendor Manuals.
1.
G.E. Operations and Maintenance Instruction Volume III, Part II, Standby Liquid Control System. *
- 2. G.E.
Operations and Maintenance Instruction Volume IX, Part I, Standby Liquid Control System.
3.
Instruction Manual, Union Pump Company E-66-31-8; Standby Liquid Control Pump and Motor Data Book.
4.
Instruction Manual, Greer Products E-66-31-25; Nitrogen Accumulator.
D. Electrical Diagrams.
1.
B & R Drawing 3006; Auxiliary One Line Diagram.
2.
B & R Drawing 3139; Reactor Building Lighting Panels.
~
8607080224 860630 PDR P ADOCK 05000298' PDR Rsvised By/Date Reviewed by/Date p Rev Procedure gy&yrgyedBy/Date
, tj f w & c= ~ , Page 1 Of J. Ss11sbury 8/7/85 .R. Brungardt 8/18/85 f-//-p f 11 6.3.8.4 7- Pages
- 3. B'& R Drawing 3010; Vital One Line Diagram.
- 4. G.E. Drawing 920D225; Functional Control Diagram.
- 5. G.E. Drawing 791E262; Elementary Control Diagram. ,
D. Miscellaneous.
- 1. CNS Inservice Testing Program.
IV. PREREOUISITES-A. Plant air system in Mervice for the storage tank level indication.
B.
Demineralized water storage and transfer system available for a water supply to the storage tank.
C.
SLC actuation keylock control switch,in the STOP (center) position and-key removed.
D.
Special tools and nitrogen gas charging unit with pressure gauge available for charging the accumulators, as required.
E.
Pump discharge piping nitrogen accumulators charged to greater than 450 psig.
V. LIMITATIONS A.
Surveillance Requirements - Technical Specification Sections 4.4.A.2.c. ,
4.4.A.2.d...and 4.6.G. (IST).
1.
The operability of the SLC system shall be shown by the performance of the following tests:
- a. At least once during each operating cycle, manually initiate one of'the SLC system pumps and pump demineralized water into the reactor vessel from the test tank. These tests check the ~
actuation of the explosive charge of the tested, loop,-proper operation of the valves, and pump operability. The replacement charges to be-installed will be selected from the same manu-factured batch as the tested charge. 'Both systems, including both explosive valves, shall be tested in the' course of two operating cycles. *-
B. Administrative Limits. ;
1.
All discrepancies 'shall be . recorded in the' Shif t Supervisor's log. l
- 2. Attachment "B" shall be' used to record the test and filed as part .
of the station records.
13.
l' All testing shall be coordinated with the Control Room Operator.
w -
Proczdure Number' 6.3.8.4 1
-Date- f,~ l f, 713
_ Revision-11 Page 2 Of- . 7 Pages; i-
_.a.-- - - - . _ . . . . -.u_--_ .... _ - . - - - _ _ - - . - -
- 4. Any valve seals broken must be reported to the Shif t Supervisor who must enter status in the Valve Seals Log as per Conduct of Operations Procedure 2.0.2, Operations Logs And Reports. When the valve is returned to its normal positien, it must be resealed using numbered lead se,a1 and reported to the Shift Supervisor.
VI. PRECAUTIONS A. During pump operation check that piston seal leakoff is sufficient to prevent overheating the packing - glands. If excessive, notify the Maintenance Department to adjust.
B.
The SLC test tank should have a sufficient demineralized water level to prevent the SLC pump from losing suction.
C. Pump suction block valve SLC-10 from the SLC tank must not be' opened until after the fired squib valve has been replaced., Opening the valve before this would allow sodium pentaborate to gravity feed to the reactor when at zero pressure. ,
D.
The electrical leads on one squib have to'be removed to prevent firing both squib valves. -
E. Do not open SLC-23 wide open prior'to'the SLC pump start, during test tank recirculation, due to possible damage to the flow meter. However, SLC-23 must be at least three turns open to prevent chattering and cycling of SLC-RV-10RV and SLC-RV-11RV. Chattering and cycling reducer relief valve performance and reliability.
F. Be aware that the RWCU system will isolate on SLC initiation.
G. Sodium pentaborate concentration, in the SLC system demineralized water, must be less than 5 ppm before inj ecting into the reactor vessel.
VII. TEST EQUIPMENT A. Sufficient number of barrels to hold flush water from piping and to drain the test tank upon completion of the test.
VII
I. PROCEDURE
NOTE: For Inservice Testing, the SLC-CV-12 and SLC-CV-13 check valves shall have been exercised upon a successful surveillance test. A successful test is one which has no discrepancies.
NOTE: Recording of the exercised check valves (IST Review) shall be recorded at least once per cycle.
NOTE: Section A. prepares the system for the injection test and Section B.
completes the injection test and returns the system to ' standby status.
Prcetdure Number 6.3.8.4 Date %. \%.95 Revision __1[, Page 3 Of; Pages 7
A. SLC System Flush.
- 1. Obtain permission and signature from the Shift Supervisor before starting the test.
- a. Obtain the key from the Shift Supervisor for the keylocked local control pump switches (key number 40). *
- 2. Notify the Control Room Operator of the intent to perform the test.
- 3. Establish communications between the Control Room and SLC Pump Area.
- 4. Place the SLC system in TEST cn the safety system status panel.
- 5. Close and tag SLC-10, pump suction' block, from the SLC tank and return the broken seal to the Shift Supervisor.
- 6. Check closed SLC-25, SLC tank recirculation valve.
a.
Verify SLC-23 is three turns open..
Note: It is important to verify SLC-23 is at least three turns open in order to minimize SLC-RV-10RV or SLC-RV-11RV chattering and cycling. Chattering and valve cycling greatly reduces valve performance and reliability.
- 7. Open SLC-28, test tank suction valve.
- 8. Open SLC-26, test tank recirculation valve, and return the broken seal to the Shift Supervisor.
- 9. Verify the test tank level is approximately 6" from the top of the test tank (demineralized water).
- 10. With the key inserted in SLC Pump A (B) local control switch start SLC Pump A (B).
11.
Verify 1215 psig is indicated on the local rack pressure gauge.
Throttle SLC-23 as necessary. The Technical Specifications require greater than or equal to 38.2 gpm at 1215 psig.
- 12. Circulate water approximately 3 minutes and place the' local control switch for SLC Pump A (B) to the OFF position.
- 13. Repeat Steps 6. through 12. for SLC Pump B (A).
14.
Open RW-50, segregated drains to drain piping, test tank, and pumps to 55 gallon barrels located in the Reactor Building, 903'.
Note: -One barrel will not hold all of the drains. Coordination l between levels 903' and 976' may be required to prevent flooding the floor on level 976' while changing the barrels. l 1
-Procxdure Number 6.3.8.4 Date 5t ' 2 5 Revision 11 Page '4 Of 7 Pages- I
- 15. Open SLC-19 and SLC-20, SLC pump discharge piping drains, and SLC-29, test tank drain.
- 16. Close SLC-19, SLC-20, and SLC-29 when drainir.g is complete.
- 17. Close RW-50. -
- 18. Close SLC-28.
- 19. Open DW-199, demineralized water supply to fill SLC pumps, piping, and test tank.
- 20. When the test tank is about 1/2 full, open SLC-28.
- 21. Close DW-199 when the test tank is full.
- 22. With the. key inserted in.SLC Pump A (B) local co,ntrol switch, start SLC Pump A (B).
- 23. Circulate the water approximately 1" minute and place the 16 cal control switch for SLC Pump A (B) . to the OFF position.
- 24. Repeat Steps 22. and 23. for SLC, Pump B (A).
- 25. Have Chemistry sample the test tank for sodium pentaborate concen-tration, must be less than 5 ppm to proceed with test.
Note: If concentration is NOT less than 5 ppm the system will need more recirculation and flushing.
- 26. Close SLC-26.
- 27. Perform independent (Licensed Operator) verification that SLC-26 is closed and install a new seal as issued by the Shif t Supervisor.
- 28. Close SLC-23.
- 29. Return the key to the locked local pump switches to the' Shift Supervisor.'
B. SLC Manual Initiation - Test Tank To Reactor.
- 1. Notify the Electrician to remove the electrical leads from the squib valve not being fired.
- 2. Measure the test tank level and verify the level to be within 6" of the top of the tank.
- 3. Check open SLC-28.
- 4. Check closed SLC-10.
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Proc; dure Number- 6.3.8.4 Date f~s Revision 'll Page 5 Of 7 Pages L
- 5. Check closed SLC-23.
- 6. Check closed SLC-25.
- 7. Notify the Control Room Operator to secure the .RK'CU system. .
- 8. Notify the Control Room to initiate the SLC system that is being tested.
Note: Alternate the systems and squib valves every operating cycle to ensure proper operation of both SLC pumps, i.e. system A pump and squib valve A should be operated together.
- 9. Record data on Attachment "B".
- 10. After the pump has run 1 minute and flow has been verified through the squib valve that was-fired, notify the Control Room to stop the SLC system.
- 11. Measure the level from the top of the test tank and compute the
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pump flow rate for the I minute run. Enter the data on Attachment "B".
- 12. Close SLC-28.
- 13. Perform independent (Licensed Operator) verification that SLC-28 is closed. '
- 14. Notify the Electrician to replace electrical lead to the squib valve that was not fired.
- 15. Replace the fired squib valve as per Maintenance Procedure 7.2.2'5.
Caution: Ensure that the fired squib valve has been replaced before opening SLC-10, see Precaution C.
- 16. Open SLC-10.
- 17. Perform independent (Licensed Operator) verification that SLC-10 is open and install new valve seal as issued by the Shift Supervisor.
- 18. Open SLC-23 three turns.
- 19. Return the system to standby status as per System Operating Proce-dure 2.2.74,Section VII.B.
- 20. _ Notify the Control Room Operator that the test has been completed.
- 21. Return the safety system status panel to normal.
- 22. Notify the Shift Supervisor that,the test has been completed.
Prsecdure Number. 6.3.8.4 Date Q lR 1$ Revision 11 Page 6 Of 7 Pages
IX. ATTACHMEh"IS A. Not applicable.
B. SLC Valve Initiation Test Tank To Reactor Vessel Data. Sheets.
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Percedure-Number 6.3.8.4
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Date Q . \ 9. 9,5 Revision , 1I Page 7 Of -7 Pages
. . . . . . . . . ~ ~ . . -......o.....-..., . - . . . - . . -
i ATTACHMENT "B" SLC MANUAL INITIATION TEST TANK YO REACTORl SURVEILLANCE PROCEDURE 6.3.8.4 UESSEL FUNCTIONAL TEST NOTE: For Inservice Testing, check valves SLC-CV-12 and SLC-CV-13 shall have been exercised upon a successful surveillance test. A successful test is one which has no discrepancies.
Recording of the exercised check valves (IST Review) shall be recorded at least once per cycle.
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PROCEDURE A. SLC System Flush. DATACllECK_l.
XXXXXXXXXX
- 1. Obtained permission and signature from Shift. Supervisor. '
- a. Obtained key number 40 from Shift Supervisor key -
XXXXXXXXXX locker. .
- 2. Notified Control Room Operator of intent to perform test.'
- 3. Established communications between Control Room and SLC - ----
XXXXXXXXXX Pump Area. ~
, 4. Placed SLC system in TEST on safety system status panel.
- 5. Closed and tagged SLC-10; returned broken valve seal to -
_-- XXXXXXXXXX Shif t Supervisor. ,
- 6. Checked closed SLC-25. ~
- a. Verified SLC-23 three turns open. - , - - --
- 7. Opened SLC-28.
- 8. Opened SLC-26; returned broken seal to Shift Supervisor.
- 9. Verified test tank 1,evel S 6" from top of tank. --- -- ------- -
i 10. Started SLC Pump A (B) with local control switch.
- 11. Verified > 38.2 gpm at 1215 psig pump discharge pressure.
- 12. Circulated water
- 3 minutes and stopped Pump A (B). ------------- ---
- 13. Repeated Steps 6. through 12. for SLC Pump B (A).
- 14. Opened RW-50 to 55 gallon barrel.
- 15. Opened SLC-19, SLC-20, and SLC-29. ------ - -----
- 16. Closed SLC-19, SLC-20, and SLC-29 when draining is completed.
- 17. Closed RW-50.
- 18. Closed SLC-28. ---- ----- -- -----------
- 19. Opened DW-199 to test tank.
- 20. Opened SLC-28 when test tank is about 1/2 full.
- 21. Closed DV-199 when test tank is full. -- --------------------- ---
- 22. Started SLC Pump A (B) with local control switch.
- 23. Circulated water about I minute and stopped Pump A (B).
, 24. Repeated Steps 22. and 23. for SLC Pump B (A). -- --------------
- 25. Had Chemistry sample tank tank: ppm.
- 26. Closed SLC-26.
- 27. Performed independent (Licensed Operator) verification that --------------- XXXXXXXXXX SLC-26 is closed and installed,new valve seal as issued by XXXXXXXXXX Shift Supervisor.
- 28. Closed SLC-23. =
- 29. Returned key to Shift Supervisor (key number 40).
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i Procedure Number 6.3.8.4 Date 2-if-1!T Revision Page Of 11 1 3 Pages
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SLC MANUAL INITIATION TEST TANK TO REACTOR ATTACHMENT "5" SURVEILLANCE PROCEDURE 6.3.8.4 VESSEL l
i FUNCTIONAL TEST 4
h PROCEDURE DATA CHECK ;
B. SLC Manual Initiation - Test Tank 'lo Reactor. -
XXXXXXXXXX
- 1. Notified Electrician to remove electrical leads from squib XXXXXXXXXX valve not being fired. - - - ----- - ----
- 2. Measured test tank level and verified level to be within XXXXXXXXXX 6" of top of tank.
- 3. Checked open SLC-28. --- -
= - - - - - - -------------
- 4. Checked closed SLC-10,
- 5. Checked closed SLC-23.
- 6. Checked closed SLC-25. -- - =-- -- -
- 7. Notified Control Room Operator to secure RWCU. system.
i 8. Notified Control Room to initiate SLC system being tested; ,
XXXXXXXXXX System: . -
- 9. Recorded data. *
- 10. Verified SLC system off.
- 11. Measured test tank and computed flow rate. ---- -------------
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- 12. Closed SLC-28.
- 13. Performed independent (Licensed Operator) verification that XXXXXXXXXX SLC-28 is closed. -- - - - - - - - - - - - - - -- -- -----------
- 14. Replaced electrical leads on unfired squib9'alve.
- 15. Replaced fired squib valve.
- 16. Opened SLC-10. --- -
i 17. Performed independent (Licensed Operator) verification that __
XXXXXXXXXX SLC-10 is open and installed new valve seal as issued by X%XXXXXXXX Shift Supervisor. ------- -- ------ -----------------------
! 18. Opened SLC-23 three turns.
- 19. Returned system to standby status.
- 20. Notified Control Room Operator test is completed. --- - ----- ---
- 21. Returned safety system status panel to normal.
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- 22. Notified Shif t Supervisor test has been completed.
l PUMP A DATA PUMP B DATA I
Test Tank Level-Stop Test Tank Level Stop Test Tank Level Start Test Tank Level Start Level Decrease Level Decrease GPM Pump Flow CPM Pump Flow Pump Discharge Pressure Pump Discharge Pressure NOTE: 1" level in SLC Test Tank equals.4.4 gallons. ;
Technical Specifications required 1 38.2 gpm flow rate.at 1 1215 psig pump discharge pressure.
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Procedure Number 6.3.8.4 Date 9- 19 -3!$ Revision 11' Page 2 Of 3 Pages l
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SLC MANUAL INITIATIOS IEST TANK 10 REACTOR ATTACHMENT "B" SURVEILLANCE PROCEDURE 6.3.8.4 VESSEL FUNCTIONAL TEST Discrepancies:
Oparator /
Date 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 IST Review. / Satisfactory Completion Date Raviewed By /
Date Preccdure Number 6.3.8.4 Date C.*I<'~ Revision 11 Page 3 Of' 3 Pages