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Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML20217C7961999-10-0606 October 1999 Marked-up & Type Written Proposed TS Pages,Revising TSs 1.0, 3.6,Bases 3.0,Bases 3.6 & 5.5,to Adopt Implementation Requirements of 10CFR50,App J,Option B for Performance of Type A,B & C Containment Leakage Rate Testing ML20209A7351999-06-23023 June 1999 Proposed Tech Specs Pages 3.3-4 & 3.3-6,replacing Page 3.3-6 Re Recirculation Loop Flow Transmitters & Applicable SRs Associated with Function 2.b ML20196B4741999-06-17017 June 1999 Proposed Tech Specs Bases Changes Made at Plant Subsequent to Receipt of License Amend 178,dtd 980731,for Conversion to Its,Through 990610 ML20195E9101999-06-0808 June 1999 Proposed Tech Specs,Correcting Described Method by Which SGTS Heaters Are to Be Tested ML20207A0761999-05-14014 May 1999 Rev 3 to CNS Strategy for Achieving Engineering Excellence ML20206J2661999-04-22022 April 1999 CNS Offsite Dose Assessment Manual (Odam) ML20205H2891999-03-31031 March 1999 Proposed Tech Specs Modifying ACs for Unit Staff Qualifications for Shift Supervisor,Senior Operator,Licensed Operator,Shift Technical Advisor & Radiation Manager Positions ML20151Q0621998-07-28028 July 1998 Final Version of Improved TS & Bases Re Proposed Change to Conversion to Improved Standard TS ML20236W1141998-07-28028 July 1998 Proposed Tech Specs Re Implementation of BWR Thermal Hydraulic Stability Solution ML20236R9821998-07-16016 July 1998 Proposed Tech Specs Section 6.5.1,re Implementation of BWR Thermal Hydraulic Stability Solution ML20236Q0641998-07-13013 July 1998 Proposed Tech Specs Re Rev B to Conversion to Improved STS ML20206P9051998-07-0707 July 1998 Rev 2, Strategy for Achieving Engineering Excellence, for Cooper Nuclear Station ML20216H0571998-04-15015 April 1998 Proposed Tech Specs 4.2.C,exempting Neutron Detectors from Channel Calibr Requirements ML20216H0801998-04-15015 April 1998 Proposed Tech Specs Sections 2.1.A.1.d & 3.2.C,deleting Max Rated Power for APRM Rod Block Trip Setting ML20216D8971998-04-0808 April 1998 Rev 1 to Strategy for Achieving Engineering Excellence ML20216B4481998-04-0202 April 1998 Proposed Tech Specs 4.2.C,exempting Neutron Detectors from Channel Calibr Requirements ML20203G4271998-02-24024 February 1998 Rev 0 to First Ten-Year Interval Containment Insp Program for Cns ML20202H5311998-02-11011 February 1998 Strategy for Achieving Engineering Excellence ML20216G1571997-09-0505 September 1997 Rev 2.1 to Third 10-Yr Interval Inservice Insp Program ML20210H5641997-08-0707 August 1997 Rev 2 to NPPD CNS Third Interval Inservice Testing Program ML20148G3481997-05-30030 May 1997 Proposed Tech Specs,Changing Frequency of Testing RHR Cross Tie valve,RHR-MOV-MO20,position Indication from Once Per Month to Once Per Operating Cycle ML20148G8531997-05-0909 May 1997 Nebraska Public Power District Nuclear Power Group Phase 3 Performance Improvement Plan, Closure Rept ML20138J0751997-05-0505 May 1997 Proposed Tech Specs,Relocating Control of Standby Liquid Control Relief Valve Setpoint in TS 4.4.A.2.a & Associated Bases ML20148B0041997-05-0202 May 1997 Proposed Tech Specs,Deleting SLC Relief Valve Testing Described in TS Section 4.4.A.2.a & Associated Bases in Bases Section 3.4.A Since Testing Is Already Performed Under ISI Program ML20138H3861997-04-29029 April 1997 Rev 1.2 to CNS Third Interval IST Program ML20134K3771997-02-10010 February 1997 Proposed Tech Specs Re Requirements for Avoidance & Protection from Thermal Hydraulic Instabilities to Be Consistent w/NEDO-31960 & NEDO-31960,Suppl 1, BWR Owners Group Long-Term Stability Solutions.. ML20134E1091996-10-25025 October 1996 NPPD Cooper Nuclear Station Third Interval IST Program, Rev 1 ML20117K3291996-06-0606 June 1996 Proposed Tech Specs Revising Safety Limit MCPR from 1.06 to 1.07 for Dual Recirculation Loop Operation & from 1.07 to 1.08 for Single Recirculation Loop Operation ML20100R4431996-03-0505 March 1996 Proposed Tech Specs,Consisting of Change Request 142, Revising TS, DG Enhancements ML20101L8381995-12-31031 December 1995 Reactor Containment Bldg Integrated Leak Rate Test. W/ ML20113B0531995-12-29029 December 1995 Rev 4.1 to NPPD CNS Second Ten Yr Interval ISI Program for ASME Class 1,2 & 3 Components ML20093L1901995-10-18018 October 1995 Rev 0 to Third Ten-Yr Interval ISI Program for Cns ML20086K4421995-07-14014 July 1995 Revised Proposed Tech Specs Re DG Enhancements Reflecting More Conservative Approach to Enhancing DGs ML20086H7341995-07-14014 July 1995 Rev 7 to CNS Second Ten Yr Interval IST Program ML20086H7601995-06-30030 June 1995 Rev 4 to CNS Second Ten Yr Interval ISI Program for ASME Class 1,2 & 3 Components ML20086B7061995-06-28028 June 1995 Proposed Tech Specs Re Increasing Required RPV Boron Concentration & Modifying Surveillance Frequency for SLC Pump Operability Testing ML20085J2631995-06-15015 June 1995 Proposed Tech Specs Re Extension of Surveillance Intervals for Logic Sys Functional Testing for ECCS ML20083A7241995-05-0505 May 1995 Proposed Tech Specs Reflecting Changes to TSs & Associated Bases for License DPR-46 ML20083A1341995-05-0202 May 1995 Proposed Tech Specs Re Temporary Rev to SR to Extend Two Year LLRT Interval Requirement ML20083M0401995-01-20020 January 1995 Rev 1 to Restart Readiness Program ML20083M0901995-01-13013 January 1995 Rev 2 to Startup & Power Ascension Plan ML20149H8821994-12-27027 December 1994 Proposed Tech Specs Re Control Room Emergency Filter Sys ML20078S5711994-12-22022 December 1994 Proposed Tech Specs Re Definition of Lco,Per GL 87-09 ML20083M0141994-11-0909 November 1994 Rev 3 to Phase 1 Plan, ML20083M0321994-11-0808 November 1994 Rev 0 to Restart Readiness Program ML20073J2371994-09-26026 September 1994 Proposed TS LCOs 3.5.C.1 & 3.5.C.4,increasing Min Pressure at Which HPCI Sys Required to Be Operable from Greater than 113 Psig to Greater than 150 Psig ML20149F9921994-09-15015 September 1994 Rev 1 to CNS Startup Plan ML20071K9311994-07-27027 July 1994 Diagnostic Self Assessment (DSA) Implementation Plan ML20071K1541994-07-26026 July 1994 Proposed Tech Specs to Increase Flow Capacity of Control Room Emergency Filter System ML20070M6671994-04-26026 April 1994 Proposed Tech Specs Re Intermittent Operation of Hydrogen/ Oxygen Analyzers 1999-06-08
[Table view] Category:TEST/INSPECTION/OPERATING PROCEDURES
MONTHYEARML20207A0761999-05-14014 May 1999 Rev 3 to CNS Strategy for Achieving Engineering Excellence ML20206J2661999-04-22022 April 1999 CNS Offsite Dose Assessment Manual (Odam) ML20206P9051998-07-0707 July 1998 Rev 2, Strategy for Achieving Engineering Excellence, for Cooper Nuclear Station ML20216D8971998-04-0808 April 1998 Rev 1 to Strategy for Achieving Engineering Excellence ML20203G4271998-02-24024 February 1998 Rev 0 to First Ten-Year Interval Containment Insp Program for Cns ML20202H5311998-02-11011 February 1998 Strategy for Achieving Engineering Excellence ML20216G1571997-09-0505 September 1997 Rev 2.1 to Third 10-Yr Interval Inservice Insp Program ML20210H5641997-08-0707 August 1997 Rev 2 to NPPD CNS Third Interval Inservice Testing Program ML20148G8531997-05-0909 May 1997 Nebraska Public Power District Nuclear Power Group Phase 3 Performance Improvement Plan, Closure Rept ML20138H3861997-04-29029 April 1997 Rev 1.2 to CNS Third Interval IST Program ML20134E1091996-10-25025 October 1996 NPPD Cooper Nuclear Station Third Interval IST Program, Rev 1 ML20113B0531995-12-29029 December 1995 Rev 4.1 to NPPD CNS Second Ten Yr Interval ISI Program for ASME Class 1,2 & 3 Components ML20093L1901995-10-18018 October 1995 Rev 0 to Third Ten-Yr Interval ISI Program for Cns ML20086H7341995-07-14014 July 1995 Rev 7 to CNS Second Ten Yr Interval IST Program ML20086H7601995-06-30030 June 1995 Rev 4 to CNS Second Ten Yr Interval ISI Program for ASME Class 1,2 & 3 Components ML20083M0401995-01-20020 January 1995 Rev 1 to Restart Readiness Program ML20083M0901995-01-13013 January 1995 Rev 2 to Startup & Power Ascension Plan ML20083M0141994-11-0909 November 1994 Rev 3 to Phase 1 Plan, ML20083M0321994-11-0808 November 1994 Rev 0 to Restart Readiness Program ML20149F9921994-09-15015 September 1994 Rev 1 to CNS Startup Plan ML20071K9311994-07-27027 July 1994 Diagnostic Self Assessment (DSA) Implementation Plan ML20065H7481994-03-31031 March 1994 Near Term Integrated Enhancement Program, 940331 ML20063L2391994-01-31031 January 1994 Jan 1994 Addenda Cooper Nuclear Station IST Program for ASME Class 1,2 & 3 Components, Rev 6 ML20058C3331993-11-17017 November 1993 Rev 1 to Procedure MIUB-W812, Ultrasonic Insp of Pressure Retaining Bolting Two Inches or Greater in Diameter ML20058C3501993-11-15015 November 1993 Rev 0 to Procedure GE-UT-307, Procedure for Ultrasonic Exam of Reactor Pressure Vessel Closure Studs ML20128P0451992-12-21021 December 1992 Dec 1992 Addenda to Rev 6 to Cooper Nuclear Station Inservice Testing Program for ASME Class 1,2 & 3 Components ML20118A6151992-07-31031 July 1992 Jul 1992 Addenda to Rev 6 to Inservice Testing Program for ASME Class 1,2, & 3 Components ML20091K1831991-12-17017 December 1991 Dec 1991 Addenda to Rev 3 to Cooper Nuclear Station Inservice Insp Program for ASME Class 1,2 & 3 Components ML20086E6161991-11-0808 November 1991 Revised Pages to Cooper Nuclear Station Inservice Insp Program ML20085G1841991-08-31031 August 1991 Aug 1991 Addenda to Cooper Nuclear Station Inservice Testing Program for ASME Class 1,2 & 3 Components (Rev 6) ML20082H6371991-08-0101 August 1991 Aug 1991 Addenda to Rev 3 to Cooper Nuclear Station, Inservice Insp Program for ASME Class 1,2 & 3 Components ML20043C7951990-05-25025 May 1990 Rev 6 to Inservice Testing Program for ASME Class 1,2 & 3 Components. ML19332C8181989-10-31031 October 1989 October 1989 Addenda to Rev 3 to Inservice Insp Program for ASME Class 1,2 & 3 Components. ML20246J4271989-07-31031 July 1989 Jul 1989 Addenda to Inservice Insp Program for ASME Class 1,2 & 3 Components, Rev 3 ML20247K7591989-02-28028 February 1989 Addenda to Rev 3 to, Inservice Insp Program for ASME Class 1,2 & 3 Components ML20151U1551988-08-12012 August 1988 Long-Term Plan for Code Qualification of Seismic Class 1S Pipe Supports Cooper Nuclear Station ML20235U4221987-09-21021 September 1987 Reportability Analysis for 10CFR50.50 to Rev 5 to Engineering Procedure 3.3, Station Safety Evaluations. Related Info Encl ML20235U4091987-09-21021 September 1987 Temporary Mod Sheet to Rev 2 to Conduct of Operations Procedure 2.0.7, Plant Temporary Mod Control ML20235T2711987-08-20020 August 1987 1987 Annual Emergency Preparedness Exercise ML20153F0491987-06-0101 June 1987 Addenda to Rev 3 to Inservice Insp Program for ASME Class 1 2 & 3 Components ML20212D6301986-12-18018 December 1986 Fitness for Duty Policy ML20064A6961986-12-0202 December 1986 App I to PEI-TR-870200-01 Test Procedure for Steam Accident Test of Limitorque Control & Power Wiring & Okonite Tape Splices ML20211B4971986-09-30030 September 1986 Rev 5 to Offsite Emergency Plan Prompt Alert & Notification Sys Addendum for Cooper Nuclear Station ML20211B4891986-09-30030 September 1986 Rev 4 to Offsite Emergency Plan Prompt Alert & Notification Sys Addendum for Cooper Nuclear Station ML20214W0111986-08-22022 August 1986 Rev 2 to Procedures Generation Package ML20211B4851986-07-31031 July 1986 Draft Rev 3 to Offsite Emergency Plan Prompt Alert & Notification Sys Addendum for Cooper Nuclear Station ML20212B9141986-07-31031 July 1986 Vols I & II of Rev 5 to Inservice Testing Program for ASME Class 1,2 & 3 Components, for Second 10-yr Testing Program ML20211B4751986-06-30030 June 1986 Rev 2 to Offsite Emergency Plan Prompt Alert & Notification Sys Addendum for Cooper Nuclear Station ML20206T6551986-06-12012 June 1986 Rev 13 to Surveillance Procedure 6.3.2.1, Automatic Depressurization Sys Manual Valve Actuation ML20206T6791986-06-12012 June 1986 Rev 23 to Surveillance Procedure 6.3.3.1, HPCI Test Mode Surveillance Operation 1999-05-14
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' SURVEILLANCE PROCEDURE 6.3.9.I !!SIV ACCUMULATO!! FUNCTIONAL TEST 1
I. PURPOSE A. To provide a detailed instruction for station personnel to p' rform e a functional test of the main steam isolation valve (MSIV) accumulators.
II. DISCUSSION A. The MSIV accumulators are designed to provide pneumatic pressure and volume to actuate the valves through 1/2 cycle (open to close) in the event of failure of the normal air supply. Check valves are installed in the accumulator system to prevent back leakage if the air supply is lost. j B. The accumulator test is performed by isolating and ableeding the sir '
supply to the accumulators, then attaching a pressure test gauge to the system. Accumulator pressure is adjusted to 95 psig. After i hopr the gauge pressure is observed and recorded. The minimum acceptable pressure is 70 psig to actuate the MSIV 1/2 cycle (open to closed).
III. REFERENCE MATERIAL .
A. USAR. .
- 1. Volume III,Section VII, Subsection 3.4.6.
- 2. Volu=e IV,Section X, Subsection 12.3.2.5.
B. Flow Diagrams.
- 1. B & R Drawing 2010; Reactor Building Instrument Air, Sheet 2. '
- 2. B & R Drawing 2041; Reactor Building Main Steam System.
C. Mechanical Drawings.
- 1. Jelco Drawing 92200-1; Air Accumulators. J IV. PREREQUISITES A. Obtain permission and signature from the Shift Supervisor before starting the test. .
B. Coordinate testing with the Control Room Operator.
C. The test shall be performed with the reactor in a cold shutdown condi-tion and with the drywell vented.
D. The MSIVs must be closed.
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R1 vised By/Date Reviewed By/Date prov d By/Date Rev Procedure Page 1 Of T. Smith 5/8/86 R. Brungardt 6/5/86 g" 1 6.3.9.1 3 Pages
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'V. LIMITATIONS I
A. Surveillance Requirements - Technical Specifications.
.1, None.
+
- B. Administrative Limits.
i
- 1. Functional Test frequency is once per operating cycle.
- 2. Attachment "B" shall be used to record the test and filed as part of the station records.
t l
.VI. PRECAUTIONS
, A. Comply with the appropriate Special Work Permit.
4 B. Return the accumulator system to operational status after completion of the test. ,
- VII. TEST EQUIPMENT I A. Test gauge - O to 200 psi Ashcroft or. equivalent with 1/4" tube fitting.
B. Soap bubble leak detector.
. PROCEDURE I A. MSIV Accumulator Functional Test.
4 l 1. Obtain permission and signature from . the Shif t Supervisor before
- starting the test.
, 2. Inform the Control Room Operator of intent to test the MSIV accumu-lators.
?
- 3. Close the applicable instrument air supply . shutof f valve (for inboard MSIVs inside the northeast - drywell equipment hatch; for outboard MSIVs on the north wall, 916' level of the steam tunnel).
4 Install the test gauge'on.the MSIV accumulator test connection.
- 5. Adjust pressure in the accumulator to 95 psig ;by bleeding through-the test connection vent valve.
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- 6. -Uncap the tee on the pilot air supply line upstream of the'instru--
ment air _ supply check valve (to provide a' leak path).
- 7. Record the test gauge pressure on Attachment "B".
- 8. After-1 hour, again record the test pressure on Attachment "B".
i i
i Procsdure Number 6.3.9.1 Date /-etMb Revision 1 Pige 2 Of 3 Pages
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I Note: The minimum acceptable pressure is 70 psig. If the pressure is below this value, repressurize, check for leaks, and retest.
- 9. -After completion of the test, close the test connection- valve and remove the test gauge.
- 10. Recap the tee on the pilot air supply line upstream of the instru-ment air supply check valve.
- 11. Open the MSIV instrument air supply shutoff valve.
- 12. Perform independent (Licensed Operator or Instrument Technician)
- verification that the valve closed in Step 3. has been reopened.and the cap is replaced on the tee.
- 13. Leak test (soap bubble) all fittings that have been disconnected for this test.
- 14. Inform the Control Room Operator that,the test is complete.
IX. ATTACHMENTS A. Not Applicable.
B. MSIV Accumulator Functional Test Data Sheets.
I C. MSIV Accumulator Instrument Air Supply Drawing. ,
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, Prccedure Number 6.3.9.1 Date d- f JP (k;,,, Revision- 1 Page 3- 10f 3 Pages
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j ATTACID!ENT "B" SURVEILLANCE PROCEDURE 6.3.9.1 MSIV ACCUMULATOR FUNCTIONAL TEST
!1
{ FUNCTIONAL TEST i
1.
PROCEDURE i DATA CHECK
- l. Obtained permission and signature from Shift -
XXXXXXXXXXXXX Supervisor before starting test. ,
- 2. Informed Control Room Operator of intent to - - - - - - - - - ----- XXXXXXXXXXXXX perform test.
i 80A 80B 80C 80D 86A 86B 86C 86D
! 3. Closed instrument air supply shutoff valve. -
- 4. Installed test gauge on MSIV accumulator test X X X X X X X X connection.
[ 5. Bled pressure in accumulator to 95 psig. -----
- 6. Uncapped tee on pilot air supply line upstream X X X X X X X X of instrument air suoply check valve.
- 7. Recorded starting test gauge pressure. -- --
l 8. Recorded ending test pressure after I hour.
- 9. Closed test connection valve and removed test X X X X X X X X gauge. - ~~-- -- ---
- 10. Recapped tee on pilot air supply line upstream X X X X X X X X of instrument air supply check valve.
- 11. Opened MSIV instrument air supply shutoff valve. -
j 12. Performed independent (Licensed Operator or X X X X X X X X
- Instrument Technician) verification that valve X X X X X X X X is open. ---- ----------
- 13. Leak tested all fittings previously disconnected.
- 14. Informed Control Room Operator test is complete.
. START PRESSURE END PRESSURE ACCUMULATOR (t = 0 Hr) (t = 1 Hr) INITIALS ,,,
80A
. 80B 80C SOD
. 86A 1
86B 86C 86D Note: The initial pressure should be the normal minimum supply pressure (95 psig). The minimum required to operate the MSIV 1/2 cycle is 70 psig.
Test Instrument Number:
Prcesdure Number 6.3.9.1 Date A- c Pfr Revision 1 Page 1 Of 2 Pages
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-ATTACIB!ENT "B" SURVEILLANCE PROCEDURE 6.3'.9.1 MSIV ACCUMULATOR FUNCTIONAL TEST FUNCTIONAL TEST Discrepancies: '
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Date
- Shift Supervisor / Permission To Start Date Shif t Supervisor /' ~ Test Complete And Reviewed Date l Shift Supervisor / 'NCR Written If Required Date 1 Work Item (s) Initiated If Required
- Rsviewed By /
Date h
Precedure Number 6.3.9.1 Date d". . .-C #d- . Revision 1 Page 2 .0f 2 Pages.
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== w u s uvuouan a uu ivn vrcanttuno unovna ATTACIRIENT "C" SURVEILLANCE PROCEDUitE 6.3.9.1 MSIV ACCintULATOP FUNCTIONAL TEST MSIV ACCUMULATOR INSTRUMENT AIR SUPPLY DRAWING ITEM DESCRIPTION MANUFACTURER SIZE MATERIAL MODEL QUANTITY i
1 Valve, Globe Jenkins I/2" Bronze 106A 1 2 Tee, Female Branch Swagelok 1/2" Brass B-810-3TTF -2 i
3 Tee, Union Swagelok 1/2" Brass B-810-3 1 4 Valve, Check Nupro 1/2" 316 SS' SS-8C4-1 1 5 Connector, Male Swagelok 1/2" x 1/4" 316 SS SS-400-1U8 1 1
6 Valve, Globe Whitey 1/4" 316 SS SS-IVS4 2 7 Tee, Union Swagelok 1/4'I 316 SS SS-400-3 1 i
j Procsdure Number 6.3.9.1 Date 4 '~.8.h Revision 1 Page 2 Of 2 Pages