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
. _.....oo.... ......o........, . . . . . . .
DIESEL GEt4ERAf0R kULL OlL IR<GSEER PUMP
, SURVEILLANCE PROCEDURE 6.3.12.8 FLOW TEST
, s a
I. PURPOSE
- A. To provide a detailed instruction for station personnel to perform a flow test of the diesel generator fuel oil transfer pumps.
l II. DISCUSSION 4
A. Diesel fuel oil is stored in two underground tanks. Diesel generator fuel oil transfer pumps A and B transfer fuel to day tanks in the Diesel Rooms. Either pump can feed the day tank in DG-1 Room, or DG-2 Room, or both.
III. REFERENCES
~
! A. USAR.
- 1. Volume IV,Section VIII, Subsection 5.
B. Flow Diagrams.
~
- 1. B & R Drawing 2011. Sheet 1.
- 2. B & R Drawing 2077.
) C. Electrical Diagrams.
- 1. B & R Drawing 3045.
D. Vendor Manuals.
! 1. Gould Pumps Model 3171 E71-5.
IV. PREREQUISITES A. Obtain permission and signature from the Shift Supervisor before starting the test.
B. Schedule this test to follow a monthly diesel operability test. This will provide a means for lowering the day tank to a level necessary to assure full transfer pump flow. ,
C. Coordinate testing with the Control Room Operator.
V. LIMITATIONS A. Surveillance Requirements - Technical Specifications.
- 1. None.
hp D CK O 8 P
A .
Rsvised By/Date Reviewed By/ Data s prot d By/Date Rev Procedure Page 1 Of T. Smith 5/8/86 R. Brungardt 6/4/86 6.3.12.8 Pages 1
n 0---4/%6 3 3 ,
m____ . . _ . _ . _ _ _ . - _ _ _ _ . _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . __ . _ _ _ _ _ . - _ _ . _ . _ _ _ . . _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ . _ _ . _ _ _ _ _ _ _ _ _ _ . _ _ _ _ . _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ . _
- '. 4
?
1 k
}' B. Administrative Limits.
I' 1. Attachment "A" shall be used to record the test and filed as part l
4 of the station records.
- 2. All testing shall be coordinated with the Control Room Operator.
- 3. Test is to be run once per cycle.
VI. PRECAUTIONS (t
A.
No smoking or open flame in the Day Tank Room. -
}. B. Clean up any spilled fuel.
! VII. TEST EQUIPMENT I
A. Stopwatch.
B. Flow meter (stored in the tool crib).
j i
i VII
I. PROCEDURE
4 A. Diesel Generator Fuel Oil Transfer Pu'ap Flow Test.
I
- 1. Obtain the Shif t Supervisor's signature.
l
- 2. Record the levels in diesel oil storage tanks A and B.
- 3. Place the switches for both fuel oil transfer pumps A and B in off l , prior to starting the diesel generators for the monthly operability ;
test when this procedure is to be performed.
} Note: Both switches must be in the OFF position since either pump
- j. will start on a low level in either day tank. .
)
) 4. Close valve DCDO-11 (DGDO-15) and return the broken seal to -the
! Shift Supervisor.
i [
! 5. Close valve DGDO-19 (DGDO-19) and return the broken seal to the
[ Shift Supervisor.
- 6. Install the flow meter in the fill line near the top of the day
! tank.
t I 7. To assure maximum transfer pump flow rates can be measured, verify t
that the day tank levels are < 40" prior to starting and record the
- level in day tank 1 (2).
i l 8. Record the flow meter indication.
) 9.' Open valve DGDO-ll (DCDo-15).
1 1
, i i
i j Procedure Number 6.3.12.8 Date 4. CSIf Revision 3 Page. 2 Of 3 Pages ,
i.
l
- 10. Start fuel oil transfer pump A (B) and operate it for 5 minutes.
During operation record transfer pump A (B) discharge pressures as indicated on DGDO-PI-634A (DGDO-PI-634B) and DGDO-PI-636A (DGDO-PI-636B).
- 11. Stop transfer pump A (B) and record the flow meter indicatibn.
r
- 12. Close valve DGDO-11 (DGDO-15).
- 13. Remove the flow meter and return the fill line back to normal.
- 14. Open valve DGDO-11 (DGDO-15) and install the new seal as issued by
, the Shift Supervisor.
- 15. Open valve DGDO-19 (DGDO-19) and install the new seal as issued by the Shift Supervisor.
~
- 16. Perform independent (Licensed Operator) verification that the valves closed in Steps 4. and 5. have been reopened and sealed.,
i 17. Place one transfer pump control switch in AUTO and the other in AUTO ALTERNATE.
i 1 18. Return the flow meter to the tool c' rib.
- 19. Notify the Shift Supervisor thnt the test is completed.
IX. ATTACHMENTS A. Diesel Generator Fuel Oil Transfer Pump Flow Test Data Sheets.
L 4
.i 4
a 4
IProcedure Number 6.3.12.8 Date A . 6 9b Revision 3 Page _ 3 Of 3 Pages
s~m un .. v u o , .. .,an. ua urr.nnituna nanunu
. DIESEL GENERMOR FUEL oil 'IRANSI ER PUMP -
ATTACHMENT "A" SURVEILLANCE PROCEDURE 6.3.12.8 FLOW TEST DIESEL CENERATOR FUEL OIL TRANSFER PUMP. FLOW TEST DG-1 DG-2
- 1. Obtained Shift Supervisor's signature.
- 2. Recorded levels in diesel oil storage tanks A and B; - HH XXH Tank A: ; Tank B: . - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -
- 3. Placed both fuel oil transfer pumps A and B switches in XXXX XXXX off prior to starting diesel operability test.
4 Closed valve DCD0-11 (DGD0-15) and returned broken seal -------------- XXXX XX,U to Shift Supervisor.
- 5. Closed valve DGD0-19 (DGD0-19) and returned broken seal XXXX XXXX c d S h i f t S u p e rv i s o r . ----------------------------- - - - - - - - - -
- 6. Installed flow meter in fill line near top of day tank.
. 7. Verified day tank levels are < 40" prior to starting XXXX XXXX and recorded levels; Tank 1: ; Tank 2: . - - - - - - - - - - - ---
- 8. Recorded flow meter indication.
- 9. Opened valve DGDO-11 (DGDO-15). *
- 10. Started fuel oil transfer pump A (B) , operated it f or ---------------- XXXX XXXX 5 minutes, and recorded discharge pressures below. "
- 11. Stopped transfer pump A (B) and recorded flow n.eter XXXX XXXX 4 indication. ---- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -
- 12. Closed valve DGDO-11 (DGDO-15).
- 13. Removed flow meter and returned fill line back to normal.
- 14. Opened valve DGDO-11 (DGD0-15) and installed new seal as ----- --
XXXX XXXX issued by Shif t Supervisor.
- 15. Opened valve DCDO-19 (DGDO-19) and installed new seal as XXXX XXXX is s u e d b y S hi f t S u p e rvis o r . ------------------ ------ - - - - -
- 16. Performed independent (Licensed Operator) verification XXXX XXXX that valves closed in Steps 4. and 5 have been reo and se a led . ------------------------pe ne d --- -----
XXXX XXXX
- 17. Placed one transfer pump control switch in AUTO and the XXXX XXXX other in AUTO ALTERNATE.
- 18. Returned flow meter to tool crib. -------------- --- ---
- 19. Notified Shift Supervisor that test is completed.
FLOW METER DATA DAY TANK 1 DAY TANK 2 Final Initial Calculated
- DISCHARGE PRESSURE DATA TRANSFER PUMP A TRANSFER PUMP B PI-634A psig PI-634B psig PI-636A psig PI-636B psis
- Minimum flow is 5 gallons / minute; diesel consumption at full low is 270 gallons /
hour or 4.5 gallons / minute.
Test Instrument Number:
Prec: dure Number 6.3.12.8 Date 4. CM Revision 3 Page 1 Of 2 Pages
ooo. u ..o o o . .. .. . n . au.. o r r.nn t tuns nnnenu f
DIESEL GENERATOR FUEL OLL TRAESFER PLHP ;
'ATTACllMENT "A" SURVEILLANCE PROCEDURE '6.3.12.8 FLOW TEST '
DIESEL GENERATOR FUEL OIL TRANSFER PUMP FLOW TEST Discrepancies: .
4 e
l G
Operator /
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 R; viewed By /
Date Pr:c: dure Number 6.1.12.8 Date r' .' // - Revision 3 Fage 1 Of 2 Pages
_ _ _ _ - _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ . _. - . _ _ _ - _ _ . - - _ _ _ . _ _ _
