|
---|
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
,
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
[. _
. , . . , , _ _ ~ ,- - - - - - + --, -- " ' - - ~ ~ " " " " ' " ' ' ~ ~ ' ~~~'
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