Rev 0 to PE-9778-1, Test Rept-Grinnell Hydraulic Snubber Freedom of Motion Test Under Duke Powers McGuire Nuclear Station MSLB Accident Temp ConditionML20216B817 |
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Site: |
Mcguire, McGuire ![Duke Energy icon.png](/w/images/7/75/Duke_Energy_icon.png) |
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Issue date: |
08/25/1997 |
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From: |
AFFILIATION NOT ASSIGNED |
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To: |
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Shared Package |
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ML20216B822 |
List: |
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References |
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PE-9778-1, PE-9778-1-R, PE-9778-1-R00, NUDOCS 9709080155 |
Download: ML20216B817 (4) |
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Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML20217F3481999-10-15015 October 1999 Marked-up & Reprinted TS Pages,Changing TS Requirements for Insp of RCP Flywheels ML20217J6401999-10-0606 October 1999 Revised Pages to McGuire Nuclear Station Selected Licensee Commitments Manual ML20216E6601999-09-13013 September 1999 Marked-up & Revised TS Pages,Making Permanent One Time Only Changes Incorporated Into TS 3.7.9 Allowing Up to 24 Hours to Restore Control Room Pressure Boundary to Operable Status When Two Cravs Trains Inoperable ML20211G6711999-08-27027 August 1999 Proposed Tech Specs 3.1.4 Re Rod Group Alignment Limits ML20211A9881999-08-18018 August 1999 Rev 5 to DPC Nuclear Security Training & Qualification Plan ML20210R0131999-08-10010 August 1999 Revised Tech Specs Bases Pages B 3.4.14-2 & B 3.4.14-6, RCS PIV Leakage ML20196H7551999-06-24024 June 1999 Proposed Tech Specs 2.0, Safety Limits, TS 3.3.1, Reactor Trip Sys Instrumentation & TS 3.4.1, RCS Pressure,Temp & Flow Departure from Nucleate Boiling (DNB) Limits ML20195F2941999-06-10010 June 1999 Proposed Tech Specs,Facilitating one-time Addition of Condition G & Administrative Controls Note to TS 3.7.9, Cravs ML20212A2701999-05-28028 May 1999 Rev 25 to McGuire Nuclear Station,Units 1 & 2 Pump & Valves Inservice Testing Program ML20206M9391999-05-0606 May 1999 Proposed Tech Specs,Revising List of Referenced Documents in TS 5.6.5b Re COLR Requirements ML20206Q9311999-05-0404 May 1999 Rev 29 to List of Effective Pages for Chapter 16 & Page 16.11-66 to McGuire Selected Licensee Commitment Manual. with ML20206S9401999-04-30030 April 1999 Rev 29 to McGuire Nuclear Station Selected Licensee Commitments. with List of Effective Pages ML20206K3621999-04-30030 April 1999 Revised McGuire Nuclear Station Selected Licensee Commitments (SLC) Manual ML20206B0761999-04-0606 April 1999 Proposed Tech Specs Expanding Allowable Values for Interlocks P-6 (Intermediate Range Neutron Flux) & P-10 (Power Range Neutron Flux) in TS 3.3.1,Table 3.3.1-1, Function 16 ML20205L2251999-04-0505 April 1999 Proposed Tech Specs,Providing Revised SFP Storage Configuration,Revised SFP Storage Criteria & Revised Fuel Enrichment & Burnup Requirements ML20205L2431999-04-0505 April 1999 SFP Soluble Boron Credit Dilution Analysis (Summary of Applicable Portions) ML20205L2531999-04-0505 April 1999 Boraflex Degradation Analysis ML20205B6231999-03-23023 March 1999 Proposed Tech Specs Pages Mark Ups for Unit 1,changing Record for FOL NPF-9 Amend Submittal ML20204F6761999-03-18018 March 1999 Marked-up Tech Spec Pages Re License Bases Record Change to License Amend Submittals ML20207C6921999-02-22022 February 1999 Proposed Tech Specs Bases,Reflecting Removal of SI Signal on Low Steamline Pressure on Page B 3.3.2-16 & Adding Clarification for Increasing Hydrogen Recombiner Power During Testing on Page B 3.6.7-4 ML20198B9671998-12-0909 December 1998 Revised TS 3.7.11 LCO Bases to Specify That AB Filtered Ventilation Exhaust Sys Is Considered Operable When Associated Two Fans,Filters,Ductwork,Valves & Dampers Are Operable ML20198A4691998-12-0909 December 1998 Rev 14 to DPC McGuire Nuclear Station Process Control Program ML20196G6891998-11-23023 November 1998 Rev 26 to Selected Licensee Commitments (SLC) Manual ML20196C9211998-11-14014 November 1998 Rev 26 to Selected Licensee Commitments Manual. with Update Instructions ML20155B2111998-10-22022 October 1998 Proposed Revs to Improved Tech Specs,Implementing W Fuel as Described in TRs DPC-NE-2009 & DPC-NE-2009P ML20154L7191998-10-0505 October 1998 Rev 8 to DPC Nuclear Security & Contingency Plan, for Oconee,Mcguire & Catawba Nuclear Stations ML20151Y2461998-09-15015 September 1998 Proposed Improved Tss,Resolving Items Identified by Util During Review ML20151U3521998-09-0808 September 1998 Proposed Tech Specs & Bases Converting to Improved Tech Specs ML20151Z7751998-09-0808 September 1998 Rev 25 to McGuire Selected Licensee Commitment Manual, Consisting of Revised Pages 16.7-9 & 16.7-10 ML20237B6241998-08-14014 August 1998 Proposed Tech Specs 4.6.5.1.b.2 & 4.6.5.1b.3 Relating to Ice Condenser Ice Bed Changing Portion of Surveillances Pertaining to Lower Inlet Plenum Support Structures & Turning Vanes from 9-month Frequency to 18-month Frequency ML20237B5721998-08-12012 August 1998 Proposed Tech Specs 4.6.5.1b.3 Re Ice Condenser Sys Components W/Respect to Accumulation of Frost or Ice ML20237A0411998-08-0505 August 1998 Suppl 8 to Improved TS Noting Differences Between Two Units. Proposed Changes Require That Specs & Surveillances Apply to Each Unit Individually,Unless Otherwise Noted,Consistent W/Version of Current TS Prior to Amends 166 & 148 ML20236U1531998-07-22022 July 1998 Proposed Revised Improved Tech Specs,Implementing W Fuel as Described in TRs DPC-NE-2009P & DPC-NE-2009 ML20236G5301998-06-29029 June 1998 Rev to Bases of TS 3/4.6/3,correcting Editorial Errors ML20249C2081998-06-0909 June 1998 Rev 24 to Selected License Commitments (SLC) Manual & SLC 16.10.1,dtd June 1998 ML20247E3891998-05-0808 May 1998 Proposed Tech Specs,Revising Power Range Neutron Flux High Trip Setpoints in Event of Inoperable MSSVs & Deleting References to 3-loop Operation in Current TS Section 3.7.1.1(b) & Table 3.7-2 ML20217F2841998-04-20020 April 1998 Rev 7 to DPC Nuclear Security & Contingency Plan, for Oconee,Mcguire & Catawba Nuclear Stations ML20217E6531998-04-20020 April 1998 Proposed Improved Tech Specs Re Section 1.0,2.0,3.0 & 4.0 ML20217B7871998-03-20020 March 1998 Marked-up Proposed Improved TS 3.6 & 5.5.2 ML20217N9311998-03-0303 March 1998 Proposed Tech Specs 5.5 Re Meteorological Tower Location ML20216B9851998-03-0202 March 1998 Proposed Tech Specs Responding to 980116 RAI Re Improved TS Sections 3.1 & 3.2.Suppl Changes to Improved TS Encl ML20203J9391998-02-19019 February 1998 Revised McGuire Nuclear Station Selected Licensee Commitments, List of Effective Pages ML20198H5361997-12-17017 December 1997 Tech Spec Pages for TS 3/4.7.8 for Use in Lieu of ASME Section XI Requirements ML20197G4391997-12-17017 December 1997 Proposed Tech Specs Referencing Updated or Recently Approved Methodologies Used to Calculate cycle-specific Limits Contained in COLR ML20203E1911997-12-0101 December 1997 Revised McGuire Nuclear Station Selected Licensee Commitments, List of Effective Pages ML20217H5541997-10-13013 October 1997 Proposed Tech Specs Supporting Replacement of Three Safety Related Narrow Range Refueling Water Storage Tank Level Instruments W/Three Safety Related Wide Range Level Instruments ML20212A2511997-10-0606 October 1997 Proposed Tech Specs Deleting All References to Steam Line Low Pressure Safety Injection Function ML20216A8691997-09-0101 September 1997 Rev 0 to QAM-2.0, Order Entry ML20210K9281997-08-31031 August 1997 Cycle 12 Startup Rept ML20216B8171997-08-25025 August 1997 Rev 0 to PE-9778-1, Test Rept-Grinnell Hydraulic Snubber Freedom of Motion Test Under Duke Powers McGuire Nuclear Station MSLB Accident Temp Condition 1999-09-13
[Table view] Category:TEST REPORT
MONTHYEARML20205L2431999-04-0505 April 1999 SFP Soluble Boron Credit Dilution Analysis (Summary of Applicable Portions) ML20205L2531999-04-0505 April 1999 Boraflex Degradation Analysis ML20210K9281997-08-31031 August 1997 Cycle 12 Startup Rept ML20216B8171997-08-25025 August 1997 Rev 0 to PE-9778-1, Test Rept-Grinnell Hydraulic Snubber Freedom of Motion Test Under Duke Powers McGuire Nuclear Station MSLB Accident Temp Condition ML20046D3831993-08-0303 August 1993 Cycle 9 Startup Rept. ML20059L7721993-05-31031 May 1993 Reactor Containment Building Integrated Leakage Rate Test Rept ML20100Q1391992-01-31031 January 1992 Cycle 8 Startup Rept ML20076N0241991-02-28028 February 1991 Cycle 7 Startup Testing Rept ML20196F0141988-02-0909 February 1988 Cycle 5 Startup Rept ML20203N8101986-10-0909 October 1986 ECCS Pump Room Pressure Verification ML20214J9591986-08-17017 August 1986 Reactor Containment Bldg Integrated Leak Rate Test Conducted 860814-17 ML20099E6561985-02-18018 February 1985 Rev 1 to Reactor Vessel Cavity Seal Test Results,Catawba Nuclear Station,Units 1 & 2,McGuire Nuclear Station,Units 1 & 2 ML20104A9601985-01-18018 January 1985 Reactor Vessel Cavity Seal Test Results ML20024E6511983-08-0505 August 1983 Duke Power Co McGuire Nuclear Station,Unit 1,Reactor Containment Bldg Integrated Leak Rate Test Conducted 830415-18. W/830805 Ltr ML20028B5361982-11-18018 November 1982 Reactor Containment Bldg Integrated Leak Rate Test,Suppl 2. ML20081F5081982-11-15015 November 1982 Suppl 3 to Startup Rept ML20066K7831982-09-10010 September 1982 Analysis of Cables & Connectors Following Accident Test Conducted on 820331 & Extended Accident Test Conducted 820510-18 on Electrical Penetration Assembly,Type B-M, Vol 2 ML20066K7561982-07-21021 July 1982 Environ Qualification Test Rept on Electrical Penetration Assembly,Type B-M, Vol 1 ML20049J3331982-02-15015 February 1982 Startup Rept. ML19341C5491981-02-27027 February 1981 Reactor Containment Bldg Integrated Leak Rate Test Suppl 1. ML19341A1141981-01-0505 January 1981 Analysis of Hydrogen Control Measures at McGuire Nuclear Station, Vol 3 ML19257A9111980-01-0303 January 1980 Reactor Containment Bldg Integrated Leak Rate Test. ML20064E9891978-11-20020 November 1978 Test Procedure for Qual of Joy Manufacturing Co Axial Fan/Motor Units for Class I Svc in Nuc Pwr Stations of Both BWR & PWR Types.Test Conducted to Document & Qual Fan Motor Unit ML19305D3101978-07-0606 July 1978 Qualification Test Rept on Three Model 386A Differential Pressure Transmitters & Remote Sensors, Vol 1,Revision B ML19305D3131978-07-0606 July 1978 Qualification Test Rept on Three Model 386A Differential Pressure Transmitters & Remote Sensors, Vol 2,Revision C 1999-04-05
[Table view] |
Text
. Al0-28-97 THU 0316 Pli GRINNELLCORPORAT10E rax th Aut eso suiu r. uNr PREP.BY g R N O. PE-9778-1 GRINN ELL CORPORATION APP.
PAGE 1 OF 4 O
REV.
DATE 8-25-97 QAg/
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TITLE: TEST REPORT GRINNEl.L HYDRAUUC SNUBBER FR MOTION TEST UNDER DUKE POWERS MCGUIRE NUCl. EAR STATION MSLB ACCIDENTTEMPERATURE CONDITION.
- 1. PURPOSE This test report evnlantes thefreedom of motion of Grinnell hydraulic snitbbers during Duke Power Company - McGulrc Station's MSLB ntcident (cmperntarc condition. This testing was performed under Grinnell shop order No. 4128923 in accordance with the requirements of Duke Power Company P.O. No. MN31233, Rev.1 "QA Condition 1".
1
- 2. T_f5T SPECIMENS Two (2) Grinnell figure 200 N hydraulic smtbbers were supplied by Duke Power Company. Both Werc 1 1/2" bore with 5" strokes and contained polycarbonate reservolts. The serial numbers were 20598 and 20725. Both smtbbers were manufactured in 1978 and subsequently reballt by Duke Power Company using Grinnell supplied seals, fluid and procedurcs.
- 3. TEST REOUIREMENTS 3.1. Snttbber setting at midstroke 3.2. Snnbber reservoirftlled to > 50% capacity 3.3. Inlllal5nubber temperature 120' F in moisture environment 3.4. Quickly increase air temperature to 350'F 3.5. Hold temperature at 350'Ffor 10 minutes 3.6. Performfreedom of motion test by hand on snubber tofnis extension andfull retraction 9709080155 97oggg DR ADOCK 05000369
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. AUG-28-97 THU 03:17 Pil GRINNELt. CORPORATION FAX NO. 401 666 3010 y, ugfuf PREP.BY NO. PE-9778-1 GRINN ELL CORPORATION PAGE 2 OF 4 REV. O DATE 8-75-97 TITLE: TEST REPORT-GRINNEll. HYDPAUUC SNUBBER FREEDOM OF MOTION TEST UNDER DUKE POWERS MCGUIRE NUCLEAR STATION MSLB ACCIDENT TEMPERATURE CONDITION.
- 4. TEST EQUlPM EN_l 550' F oven- Grinnell No. GC 0361 l 550' F oven- Grinnell No. GP 1054 l Thermocouplc Dl0 ltalThermometer Grinnell No, GC 0005 calibrated August l
13,1997.
(3) Type K OMEGA T hermocottples
- 5. TEST SEQUENCE 5.1 Installed (1) thermocottple on cach rod bushht0 5.2 Verifted both sntthbers set at midstroke 5.3 Verifted both sanbber reservoirs to be approximately 3/4fttll 5.4 Removed reservoir vent pitu3s 5.5 Placed both sunbbers in a 120' F moist oven and left overnite to stabilize 5.6 Serial number 20725 5.6.1 Mcasttrcit rod bitshing temperatttre of126.0"F 5.6.2 Rapidly trangferred to adjacent oven which had been preheated to 360'F 5.6.3 Monitored oven alt temperatare by means of a thermoccuplc 5.6.4 When oven rtir temperatttre retttrned to 350'F the ten (10) minate testWas started 5.6.5 Every thirty (30) seconds the oven air and rect bashin0 temperatures Were mensttrett. The air temperature rangedfrom 350 to 355' F nnd the rod bashing reached a maximttm of 226' F.
5.6.6 At the enct of the ten (10) minutes. the oven was opened and the snitbber Was immediately hand strokett Whlte still in the oven to thefully extended anc( thcJttlly retracted positions two (2) times.
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nw- & ur niu usu , en unmnm warunnnua rna nu. u. ovo so.. r. oe u, PREP.BY NO. PE-97781 GRINN ELL CORPORATION PAGE 3OF4 REV. O DATE 8-25 97 TITLE: TEST REPORT-GRINNELL HYDRAULIC SNUBBER FREEDOM OF MOTION TEST UNDER DUKE POWERS MCGUIRE NUCLEAR STATION MSI.B ACCIDENTTEMPERATURE CONDITION.
5.7 Scrint Nt4ntber 20598 5.7.1 Mcasttred rod bitshin0 temperature of122.9'F 5.7.2 Rapittly transferred to adjacent oven which hcut been prehented -
to 355'F 5.7.3 Monitored oven air temperature by means of a thermoccuptc.
5.7.4 When oven air tentpcrnture relltrned to 350'F the tett (10) minute test was started 5.7.5 Every thirty (30) seconds the oven air anst rod bitshing temperatures were measured. The air temperntitre ran0cdfrom 350 to as6* F ruut the rod busking rear.ited a maximitm of 224' F 5.7.6 At the end of the ten (10) minutes, the oven was opened nnd the sunbber was immediately hand stroked while still in the oven to thefully extended and thefally retracted positions two (2) times.
- 6. T._EST RESULTS No restriction of motion was encottntered with eith er snnbber,
- 7. ANALYTlCAL RESULTS An analysis was performed on 1 1/2 to 6" bore Gr.miell hydraallt snitbber cylinders. The efects of eqttllibrium temperatures up to 350'F on the slidin0 components of the cylinders Werc evalttated. Of ttg worst case tolerances, materials and material properties; no interfer:.nce resulted. This analysis is onftlefor revicW at Grinnell Corporation.
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. aus-ze-st m u 03:18 en oxinsat uuxeuxanus m nu. aui een ouiu r. u3,u, PREP.BY GRINN ELL CORPORATION N O. PE-9778-1 PAGE 4 OF 4 REV. O DATF R-7 5-47 TITLE: TEST REPORT-GRINNELL HYDPAULIC SNUBBER FREEDOM OF MOTION TEST UNDER DUKE POWERS MCGUlRE NUCLEAR STATION MSLB ACCIDENTTEMPERATURE CONDITION.
- 8. CONCLllSIONS Tlte Grlitncilltydrattlic snitbbets allowed titermal movement ditring post ,
MSL.B accident condillottsfor Ditke Po Ner's McGirlre Nt(clear Station, Based on tlic analytical restttts, sizes 1 1/2 to 6" bore cylinders Will allow titis titermal Movement.
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