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
|
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
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
,
touren'autLeak diattua urendtiund narvoat SURVEILLANCE PFOCEDURE 6.3.2.1 ADS MANUAL VALVE ACTUATION
/
I. PURPOSE A. To provide a detailed instruction for station personnel to manually open each relief valve with the reactor at pressure, to confirm the operability of each automatic depressurization system (ADS) relief valve.
II. DISCUSSION A. The ADS utilizes six pressure relief valves to relieve the high pres-sure steam to the suppression pool. This procedure will consist of testing all eight of the nuclear steam system relief valves. Testing of the relief valves will be normally performed at a low power level.
III.
- REFERENCE MATERIAL A. USAR. - -
- 1. Volume II,Section IV, Subsection 4.
- 2. Volume II,Section VI, Subsectich'5.2.3.
- 3. Volume III,Section VII, Subsection 4.3.3.
- 4. Volume VII, Appendix H, Page H.4.9.
B. Flow Diagrams.
~
- 1. B & R Draving 2027; Reactor Recirculation and Suppression Chamber Vent Systems and Connections.
- 2. B & R Drawing 2028; Reactor Building and Drywell Equipment Drain System.
- 3. B & R Drawing 2026; Reactor Vessel Instrumentation.
C. Vendor Manuals.
- 1. G.E. Operations and Maintenance Instruction Volume II, Subgroup Nuclear Boiler System, Sections 3 and 5. , ,
D. Electrical Diagrams.
- 1. G.E. Drawing 791E253; Elementary Automatic Blowdown System.
- 2. G.E. Drawing 730E149; FCD Automatic Blowdown System.
- 3. G.E. Drawing 944E689; Low-Low Set. -
8607080202 860630 PDR ADOCK 05000298 p PDR Rsvised By/Date Reviewed By/Date AhproedBy/Date J Rev Procedure Page 1 0:
R. Gardner 1/6/86 R. Brungarde 6/10/86 /% 13 6.3.2.1 4 Paget
.- _ ,v . ~ .
- 4. B & R Drawing 3010; Vital One Line Diagram.
- 5. B & R Drawing 3059; DC Panel Schedules.
IV. PREREQUISITES A. Control air system in service and supplying reliable air to the relief i
' valve accumulators.
B. Reactor pressure
V. LIMITATIONS A. Surveillance Requirements - Technical Specifications Section 4.6.D.5.
- 1. Once per operating cycle, with the reactor pressure > 100 psig, each relief valve shall .be manually opened until the main turbine i
, bypass valves have closed, to compensate for relief valve opening.
, B. Administrative Limits. - -
- 1. Attachment "B" shall be used to record the test and filed as . part .
of the station records.
! 2. All testing shall be coordinated with the Control Room Operator.
i VI. PRECAUTIONS
. A. Suppression pool water temperature must be monitored during relief valve operation.
- B. When manually operating main steam relief valves attempt to alternate
. the use of the valves and avoid prolonged usage (> 5 minutes) of j individual valves to avoid overheating any localized areas.
C. In the event that a relief valve fails:to function as designed, except for pressure setpoint requirements, and the cause of the malfunction is not clearly determined, understood, and therefore corrected, the entire valve shall be removed from service, disassembled, inspected, adjusted, and pressure setpoint tested with steam for proper operation prior to q returning the valve to service.
VII. TEST EQUIPMENT
1 VII
I. PROCEDURE
A. ADS Manual Valve Actuation.
- 1. Obtain permission and signature from the Shif t. Supervisor before starting the test.
i I
l l
l i
Procsdure Number. 6.3.2.1 Date / 13 2l , Revision 13 Page 2 Of. 4 Pages
. . . -- - . , - , . ~ , , . _ .- . . _ , -, , , ,
- 2. Assure the proper indication for the test condition is displayed on the safety system status panel.
- 3. The blue indicating light for relief valve position indication on panel 9-3 is lit (indicates the valve has downstream pressure < 30 psig which indicates that the valve should be closed).. ,
- 4. The green indicating light for the relief valves on panel 9-3 is-lit (indicates the solenoid pilot valve is deenergized).
- 5. Check that_ annunciators 9-3-4/2-1, SV BLOWDOWN VALVE LEAK, and 9-3-4/3-1, RELIEF VALVE OPEN, are clear. ,,
- 6. Read and record the relief valve downstream temperature on NB-TR-166 with the relief valves closed. .
Note: The following computer points may also be utilized.
I a. T142; MS Relief Valve A Temperature DEGF.
- b. T143; MS Relief Valve B Temperature DEGF.
- c. T144; MS Relief Valve C Temperature DEGF.
- d. T145; MS Relief Valve D Temperature DEGF.
- e. T146; MS Relief Valve E Temperature DEGF. .
- f. T147; MS Relief Valve F Temperature DEGF.
- g. T148; MS Relief Valve G Temperature DEGF.
- h. T149; MS Relief Valve H Temperature DEGF.
- 7. Read and record the bypass valve position with the relief valves closed.
- 8. Place the control switch for the desired relief valve (A, B, C, D, E, F, G, H) to OPEN on panel 9-3.
- 9. Check that the red indicating light comes on and the green and blue indicating lights go out for that relief valve (indicates solenoid pilot valve is energized). ,
- 10. Read and record the bypass valve position with the relief valve open.
Note: Minimum acceptable level of valve movement is > 2%.
- 11. Observe the temperature increase indication on recorder NB-TR-166 and record the temperature or computer point for the appropriate relief valve as listed in Step 6.
i
- Procedure Number 6.3.2.1 ,
Date I,. il- QG Revision 13 Page- 3 Of 4 Pages:
- 12. Verify annunciators 9-3-4/2-1, SV BLOWDOWN VALVE LEAK (only if the temperature is > 300*F), and 9-3-4/3-1, RELIEF VALVE OPEN, alarm.
- 13. Verify computer alarm typer prints MAIN STEAM RELIEF VALVE OPEN for proper valve.
- 14. Place the control switch for the relief valve to AUTO on panel 9-3.
- 15. Verify computer alarm typer prints MAIN STEAM RELIEF VALVE CLOSED for proper valve.
- 16. Check that the red indicating light goes out and the green and blue "'
indicating lights come on for that relief valve.
CAUTION: DO NOT LEAVE THE RELIEF , VALVE OPEN FOR LONGER THAN 5 MINUTES MAXIMUM. MONITOR THE SUPPRESSION POOL TEMPERA-TURE AFTER MANUALLY INITIATING EACH RELIEF VALVE.
- 17. Read and record the bypas's valve position with the relief valve closed. -
- 18. Mark the time and relief valve number (of valve just tested) on the torus level recorder.
- 19. Ensure the ADS system is ready for standby operation as per System Operating Procedure 2.2.1,Section VII.A.
- 20. Restore the safety system status panel to normal.
- 21. Notify the Shift Supervisor that the test is complete.
IX. ATTACHMENTS A. Not Applicable.
B. ADS Manual Valve Actuation Functional Test Data Sheets.
Proctdure Number 6.3.2.1- Date /9 I;, J', Revision 13 Page 4 Of 4 Pages
~
COOPER NUCLEAR STATION OPERATIONS MANUAL ATTACHMENT "B" SURVEILLANCE PROCEDURE 6.3.2.1 ADS MANUAL VALVE ACTUATION FUNCTIONAL TEST f
STEP PERFORMED RELIEF VALVES MS-RV-71 PROCEDURE A B C D E F G H
- 1. Obtained permission to start test.
- 2. Assured status panel indicates test condition.
- 3. Verified blue light lit. -- -- -------
- 4. Verified green light lit.
- 5. Verified annunciators 9-3-4/2-1 and 9-3-4/3-1 elear.
- 6. Recorded temperature. --
- 7. Recorded bypass valve position.
- 8. Placed control switch to OPEN.
- 9. Checked red light on, green and blue, lights out. ---
- 10. Recorded bypass valve position.
- 11. Recorded temperature. ~
- 12. Verified annunciators 9-3-4/2-1 (only if temperature ----- X X X X X X X X is > 300*F) and 9-3-4/3-1 alarm.
- 13. Verified computer prints MAIN STEAM RELIEF VALVE X X X X X X X X OPEN. -
- 14. Placed control switch to AUTO.
- 15. Verified computer prints MAIN STENH RELIEF VALVE X X X X X X X X CLOSED. -' --
- 6. Verified red light out, green and blue lights on.
j
- 17. Recorded bypass valve position.
- 18. Marked time and relief valve number on torus level -
X X X X X X X X recorder.
- 19. Ensured ADS in standby.
- 20. Restored status panel to normal.
- 21. Notified Shift Supervisor test complete.
i-TEMPERATURE RECORDER 166 PANEL 9-21 l Relief Valve Downstream Temperature MS-RV- 71A 71B 71C 71D 71E 71F 71G 71H
- Initial Downstream Temperature Downstream Temperature Following Valve Movement Bypass Valve Position Before Test
,
- Bypass Valve Position During Test Bypass Valve Position After Test
- Minimum acceptable level of bypass valve movement is > 2% during valve lif t.
Procedure Number 6.3.2.1 Date /. . c. . ; f.
-Revision 13 Page 1 Of 2 Pager i
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. , . . , , _ _ ~ ,- - - - - - + --, -- " ' - - ~ ~ " " " " ' " ' ' ~ ~ ' ~~~'
COUPER NUCLEAR tiTAT10N UPhKAT10Nts MANUAL TTACHMENT "B" SURVEILLANCE PROCEDURE 6.3.2.1 ADS MANUAL VALVE ACTUATION 4
FUNCTIONAL TEST Discrepancies: .
N Operator /
Date Shift Supervisor / Permission To Start Date Shift Supervisor / Test Complete And Reviewed Date Shift Supervisor / NCR Written If Required Date I
Work Item (s) Initiated If Required Reviewed By /
Date Proc dure Number 6.3.2.1 Date /.. ! !.
. Revision 13 Page 2 Of 2 Pages
