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Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML17300B3791999-10-0808 October 1999 Proposed Tech Specs,Waiving Requirement to Perform SR 3.8.4.8 for Unit 1 Channels A,B & C on One Time Basis ML17300B3521999-09-29029 September 1999 Revised Bases Pages,Providing Addl Discussion of Options Available to Exit Required Action G of TS 3.8.1 & Revised Page for TS 3.3.7 ML17300B3321999-09-14014 September 1999 Marked-up Tech Specs Pages to TS 5.5.2 & 5.6.2,making Noted Administrative Changes ML17313B0601999-08-31031 August 1999 Rev 1 to PVNGS TS Bases Implemented Between Aug 1998 & Jul 1999 ML17313B0081999-07-14014 July 1999 Rev 2 to Inservice Insp Program Summary Manual for PVNGS Unit 1. ML17313A9571999-05-26026 May 1999 Proposed Tech Specs,Reducing Spurious Reactor Trip Hazards Associated with Setpoints While Maintaining Plant Protection ML17313A7511998-12-16016 December 1998 Rev 2 to ISI Program Summary Manual, for PVNGS Unit 3 ML17313A4181998-06-0909 June 1998 Proposed Improved Tech Specs Sections 3.5.1 & 3.5.2,revising Safety Injection tanks-operating & Safety Injection Tanks Shutdown ML17313A1141997-11-0707 November 1997 Improved TS Pages for Section 3.0, LCO & SR Applicability, Section 3.1, Reactivity Control & Section 3.2, Power Distribution Limits. Generic Change to NUREG-1432,Rev 1 Incorporated Into Section 3.0 & 3.1 ML17312B6411997-08-28028 August 1997 Proposed Tech Specs,Allowing one-time Extension of Required Surveillance Interval for Msi Sys Portion Only of ESFAS Logic ML20217Q6801997-08-22022 August 1997 Proposed Tech Specs,Clarifying Wording in TS Bases 3/4.6.1.4, Internal Pressure ML20141H7831997-07-18018 July 1997 Proposed Improved Tech Specs Section 3.8, Electrical Power Sys ML20141H7461997-07-18018 July 1997 Proposed Tech Specs,Providing Addl Info Re Improved TS Section 3.4, Rcs ML17312B0311996-11-0606 November 1996 Proposed Tech Specs 3/4.8.1.1 Re A.C. Sources - Operating ML17300B2651996-06-17017 June 1996 Proposed Tech Specs,Changing Section 1.10 & 3.2.8 & Associated Bases for Obtaining Thyroid Dcfs Used in Definition of Dose Equivalent I-131 ML17312A9451996-05-14014 May 1996 Rev 3 to Significant Condition Investigation. ML17312A6491996-04-0101 April 1996 Proposed Tech Specs,Revising TS 3/4.9.6 to Temporarily Allow Use of Hoist Instead of Refueling Machine for Movement of Fuel Assembly at Core Location A-07 ML17312A6401996-03-26026 March 1996 Proposed Tech Specs 3/4.9.6,increasing Refueling Machine Overload Cut Off Limit to 2,000 Lb,In 50 Lb Increments,For Removal of Stuck Fuel Assembly from Core Location A-06 ML17312A6321996-03-26026 March 1996 Proposed Tech Specs,Revising TS 3/4.9.6 to Relocate Refueling Machine Overload Cut Off Limit from TS 3/4.9.6 to Plant UFSAR Per Criteria in 10CFR50.36 & Rev 1 of NUREG-1432 STS for C-E Plants. ML17312A6371996-03-23023 March 1996 Proposed Tech Specs,Revising TS SR 4.8.2.1.e, DC Sources, to Suspend Provision of TS 4.0.1 & 4.0.4 for Battery Capacity Testing Requirements Until Entry Into Mode 4 Following Sixth Refueling Outage ML17312A5691996-03-0505 March 1996 Revised Pages to ISI Program Summary Manual ML17312A5011996-01-17017 January 1996 Revised Page 5-1 Changing Section 5.2.2 to Include Description of Material Used for Control Element Assemblies ML17311B3221995-12-20020 December 1995 Proposed Tech Specs,Reducing Setpoint for MSIS & Rt on Low SG Pressure ML17311B3181995-12-20020 December 1995 Revised Pages to ISI Program Summary Manual ML17311B0301995-07-0303 July 1995 Proposed Tech Specs Re Temp Method to Respond to Sustained Degraded Switchyard Voltage ML17311A9771995-06-21021 June 1995 Proposed Tech Specs,Modifying Tables 3.3-4 & 3.3-5 of Section 3/4.3.2 of Esfa Sys Instrumentation ML17311A8651995-05-0202 May 1995 Proposed TS 3.1.2.6,Figure 3.1-1, Min Borated Water Vols, Relocating Elevations That Correspond to Min Required Water Vols for Spent Fuel Pool Into Site Procedures ML17311A8231995-04-18018 April 1995 Proposed Tech Specs Section 3/4.4.4 Re Sleeving Process for SG Tube Repair ML17312A9381995-02-0303 February 1995 Corrective Action Program. ML17311A5631994-12-28028 December 1994 Proposed TS Sections 3.9.6 & 4.9.6.1 Re Refueling Machine ML17311A5021994-12-0707 December 1994 Proposed Tech Specs,Changing Note 5 to Table 4.3-1 of TS 3/4.3.1 to Allow Verification of Shape Annealing Matrix Elements Used in Core Protection Calculators ML17311A4341994-11-30030 November 1994 Proposed TS 3/4.4.2,changing Pressurizer Code Safety Valve Lift Setting from 2,500 Psia to 2,475 Psia in LCOs 3.4.2.1 & 3.4.2.2 ML17311A3851994-10-31031 October 1994 Proposed Tech Spec Sections 3.9.6 & 4.9.6.1, Refueling Machine. ML17311A3341994-10-0909 October 1994 Proposed Tech Specs Suspending TS 4.0.1 & 4.0.4 for Battery Capacity Testing Requirements Until Mode 4 Following Fifth Refueling Outage ML17311A2171994-08-18018 August 1994 Proposed Tech Specs Adding Analytical Method Suppl Entitled, Calculative Methods for CE Large Break LOCA Evaluation Model for Analysis of CE & W Designed Nsss. ML17310B4511994-07-12012 July 1994 Proposed Tech Specs Amend to Add One Action Statement to Table 3.3-3,entry 8 ML17310B4151994-07-0101 July 1994 Proposed Tech Specs Re Reactor Coolant Cold Leg Temperature Vs Core Power Level of TS 3.2.6 ML17310B4331994-06-20020 June 1994 Proposed Tech Specs Sections 5.3.1 & 5.6.1, & New TS Section 3/4.9.13 & Bases 3/4.9.13 ML17310B4091994-06-17017 June 1994 Proposed Tech Specs Removing Five Tables of Component Lists Per GL-91-08 ML17310B1661994-03-28028 March 1994 Proposed Tech Specs Re Min Condensate Storage Tank Indicated Level ML17310B0911994-03-0202 March 1994 SG Tube Insp Plan. ML17310B0771994-02-24024 February 1994 PVNGS Unit 1 Cycle 5 Startup Rept. ML17310B0611994-02-18018 February 1994 Proposed Tech Specs Figure 3.2-1,Section 3/4.1.1.4 & Bases 3/4.1.1.4,establishing Min Temp for Criticality at 545 F for Facilities ML17310B0251994-01-27027 January 1994 Unit 2 Steam Generator Tube Insp Plan Addendum. ML17310B0001994-01-19019 January 1994 Proposed Tech Specs of AF Automatic Actuation Logic Surveillance Frequency Extension ML17310A8361993-11-16016 November 1993 Proposed Tech Specs Table 4.2-4, Min Staffing Requirements for PVNGS Emergencies, in Support of Proposed Rev to Emergency Plan ML17310A7421993-10-27027 October 1993 Revised Unit 1 SG Tube Insp Plan. ML17310A7351993-10-26026 October 1993 Proposed Tech Specs Changing Maximum Nominal Enrichment of Fuel Allowed to Be Used in Reactor Core ML17310A6501993-09-17017 September 1993 Unit 1 SG Tube Insp Plan. ML17310A6161993-09-0808 September 1993 Proposed Tech Specs Section 6.9.1.10 Re Sys 80 Inletflow Distribution to List of Methods Used to Determine Core Operating Limits 1999-09-29
[Table view] Category:TEST REPORT
MONTHYEARML17310B0771994-02-24024 February 1994 PVNGS Unit 1 Cycle 5 Startup Rept. ML17306A5911991-12-31031 December 1991 Reactor Containment Bldg 1991 Integrated Leak Rate Test Final rept.W/920319 Ltr ML17305B1921990-11-13013 November 1990 Piping Verification Test Summary. W/901113 Ltr ML17305A8411990-02-28028 February 1990 1990 Reactor Containment Bldg Integrated Leak Rate Test Final Rept. ML17304A6291988-10-31031 October 1988 Startup Rept,Suppl 1. ML17304A2551988-07-31031 July 1988 Suppl 1 to Palo Verde Nuclear Generating Station Unit 3 Startup Rept. ML20150E6711988-02-29029 February 1988 Vols I-III of Reciprocating Charging Pump Test Rept ML20155A9331987-12-24024 December 1987 Analysis of Reactor Coolant Pump Shaft W/Modified Key Region ML17303A4551987-07-0101 July 1987 Piping Verification Program,Test Summary. W/870701 Ltr ML17300A9181987-06-30030 June 1987 Suppl 2 to Palo Verde Generating Station Unit 2 Startup Rept. ML20207R9931987-03-31031 March 1987 Suppl 1 to Palo Verde Nuclear Generating Station Unit 2 Startup Rept ML20207N0531986-12-31031 December 1986 Rev 0 to Palo Verde Nuclear Generating Station,Unit 2 Startup Rept ML17303A1811986-12-0101 December 1986 Reactor Containment Bldg Integrated Leak Rate Test Summary Technical Rept. W/861208 Ltr ML20214T8891986-11-30030 November 1986 Suppl 3 to Startup Rept ML20214L8401986-08-31031 August 1986 Suppl 2 to Palo Verde Nuclear Generating Station Unit 1 Startup Rept ML17300A2821986-07-15015 July 1986 Reactor Containment Bldg Integrated Leak Rate Test Summary Technical Rept. ML20210U6791986-05-31031 May 1986 Rev 1 to Palo Verde Nuclear Generating Station Unit 1 Startup Rept ML20154D4671986-02-28028 February 1986 Startup Rept ML17299B0511986-02-24024 February 1986 Startup Experience Rept:Mgt Overview. ML20127J4031986-01-20020 January 1986 Safety Equipment Status Sys (Sess) Commissioning Test ML17299A9021985-12-24024 December 1985 Auxiliary Feedwater Pump 48 H Endurance Test Results, Per Sser (NUREG-0857).W/851224 Ltr ML17299A3471985-05-0707 May 1985 Reactor Containment Bldg Integrated Leak Rate Test Summary Technical Rept. ML17298B5721984-10-24024 October 1984 Preliminary Prompt Notification Siren Sys Test Rept for 841024 Test. ML20080C5391983-10-15015 October 1983 Preliminary Rev 0 to Pre-Core Emergency & Auxiliary Feedwater Sys Test, Test Results Rept for 830503-0703 ML20080C5601983-10-0505 October 1983 Preliminary Rev 0 to Pre-Core Instrumentation Correlation, Test Results Rept for 830516-0701 ML20080C4511983-09-19019 September 1983 Preliminary Rev 0 to Pre-Core Chemical & Vol Control Sys Integrated Test, Test Results Rept for 830604-0704 ML20080C4341983-09-17017 September 1983 Draft 7 of Preliminary Rev 0 to Pre-Core Turbine Bypass Control Sys Test, Test Results Rept for 830601-0705 ML20080C4211983-09-14014 September 1983 Preliminary Rev 0 to Pre-Core Safety Injection Check Valve Test, Test Results Rept for 830602 ML20080C4781983-09-0707 September 1983 Preliminary Rev 0 to Main Steam Traps & Drain Valves Hot Functional Test, Test Results Rept for 830606-15 ML20080C4671983-08-25025 August 1983 Preliminary Rev 0 to MSIV & Bypass Valves Hot Functional Test, Test Results Rept for 830602-0703 ML20080C4091983-08-25025 August 1983 Preliminary Rev 0 to Atmospheric Dump Valve Hot Functional Test, Test Results Rept for 830603-0822 ML20080C4851983-08-20020 August 1983 Preliminary Rev 0 to Pressurized Performance, Test Results Rept for 830603-17 ML20080C3951983-08-0101 August 1983 Preliminary Rev 1 to Steam Generator Blowdown Sys Test, Test Results Rept for 830611-15 ML20080C5201983-07-27027 July 1983 Preliminary Rev 0 to RCS Expansion Measurements, Test Results Rept for 830411-0715 ML20080C5061983-07-21021 July 1983 Preliminary Rev 0 to Main & Auxiliary Transformer Backfeed, Test Results Rept for 830420-0515 ML20077F4261983-06-30030 June 1983 Rev 0 to Nonproprietary Cycle 1 CPC & Control Element Assembly Calculator Data Base Listing ML20077F4141983-06-30030 June 1983 Rev 1 to Nonproprietary Cpc/Control Element Assembly Calculator Sys Phase II Software Verification Test Rept ML20077F4071983-06-30030 June 1983 Rev 1 to Nonproprietary Cpc/Control Element Assembly Calculator Sys Phase I Software Verification Test Rept ML20080C4931983-06-14014 June 1983 Preliminary Rev 0 to Loose Parts & Vibration Monitoring Sys Hot Functional, Test Results Rept for 830506-0607 ML20080P6441983-02-0909 February 1983 Soil Thermal Property Measurements for Palo Verde Nuclear Plant ML20071E7081983-01-31031 January 1983 Core Protection Calculation & Control Element Assembly Calculator Sys Phase II Software Verification Test Rept. Proprietary Info Deleted ML20071E7001983-01-31031 January 1983 Core Protection Calculation & Control Element Assembly Calculator Sys Phase I Software Verification Test Rept. Proprietary Info Deleted ML17298A5431982-10-22022 October 1982 Failure Analysis of 54-26-1770 Steel Rotor Returned on NPR-97152 from Palo Verde Nuclear Station. ML17300A5321982-09-30030 September 1982 Test Rept on Slender Walls. ML20028G2191981-10-0909 October 1981 Az Nuclear Power Project 150-Inch Reed Switch Position Transmitter & Litton Electrical Connector Seismic Qualification Test (Sine Sweep Testing). Age Considerations for Seismic Design & Surveillance in Mild Environs Encl ML20063A5801981-05-18018 May 1981 Flow Interruption Test for Part 77910,Supplied to C-E ML20009C6991981-05-0808 May 1981 Flow Interruption Test on Gate Valve Assembly. ML20063A6021981-05-0808 May 1981 Corrected Flow Interruption Test on Gate Valve Assembly ML20009C6951981-03-25025 March 1981 Revision a to Flow Interruption Test for Part 77910 Supplied to C-E. ML17300A8201978-08-28028 August 1978 Torsiograph Test Rept of KSV-20-T. 1994-02-24
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1-8736: 36 AH: CCIT 3 + 9445662 l f11 XEROX tELECOP IKR 295 3 Mar 12,87 07:34 GC-RECIF GENERAL Grove City 412-458-8000 eat. 4129 P.ll TORSIOGRAPH TEST REPORT C8 KSV-20-T BECHTPj FOR ARIZONA PUBLIC SERVICE CO-PALO VERDE NUCLEAR QENERATINQ STATION SO 0391 SN-7183 This unit, completely assembled with its flywheel and generator, was torsiogxaphed in, Grove City, Pa., on 8-17-78, to confirm the results of the torsiona1 analysis.
The torsiogxaph instrumetation consisted of two Statham ASXTC 350 accelerometers mounted, at a 13" radius on a bar bolted to the free end of the generator shaft, Mi~higan Scientific 8-4 slip xing, Ellis BAN>>l amplifier, EMR-1510 analyser, and Hewlett-Packard 7035B plotter. The enqine was torsiographed at loads, of 5000, 5500, aKd 5900 kw 600 rom; at 5500 kw, 570 to 610 rpm; and at zero load, 540 to 600 rpm.
The predicted and measured torsional natural frequencies for this unit are!
Mode Natural Frequency - cpm Predicted Measurecl 127 1459 1430 4097 4010 4525 5969 6060 The first and fourth modes are associated with the forward end auxiliary drive assembly and are not, measurable at the generator shaft. These modes have no significant affect on the stresses in the engine shaft system. All of the measured natural frequencies are within 2% of the predicted values.'he predicted and measured shaft stresses (- ksi) at 600 rpm are:
Q7QQQ g0270 ADOCK 05000530 87050'DR p PDR A T~A ~N Sf'= m y"
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" 1-87: 5: 36 AM; CC l 7 3 + 9445662: 512 XEROX TELECOP E'ER 295 3
\
City 412-458-8000 eat. 4129 P.12 Mar 12,87 07:35 GC-RECIP GENERAL Grove Page 2 C~)
Predicted Measured 0 00 kw 00 W Crank- ,Qen. Crank- Gen. Crank- Gea. Crank- Ge~
Order shaft Shaft. shaft Shaft shaft Shaft shaft Shc 1-1/2 .31 .08 ~ 20 ~
~ 05 .22 -06 ~ 23 2 ~ 17 ~ 05 ~ 18 +05 .14 .04 2-1/2 2-26 .61 1.67 .45 .48 1. 92 3 -07 .02 -06 .02 ,07 .02 ,07 .C 3-1/2 ~ 89 -26 -57 ~ 17 .62 .18 ~ 67 4 .02 .Gl .02 ~ Ol .02 4-1/2 -90 ~ 29 .60 .65 ~ 21 .68 5 -08 '03 .07 ~ 02 -08 .03 ~ 09 op S>>l/2 ~ 64 ~ 49 ~ 18 .52 .19 .54 4 2
-03 .01 .03 .01 .03 .Ql -03 .0 6
6 1/2 ~ 33 -15 '48 ~ 21 .51 ~ 23 -51 4 2 7 ~ 72 36 .40 .20 ~ 41 ~ 21 7-1/2 F 01 .OL iQL F 01 .01 ~ 0:
8 .18 .13 >>13 -10 .13 .09 Pl s-l/2 .Ol .01 -03. .01 -Ol ~ 0:
9 ~ 01 .01 -OL .02 .01 .02 F 01 9-1/2 -01 .02 .02 .06 .02 .06 -02 .Qt 10 F 01 .08 -02 -01 ~ 03 All of the significant stress levels are less than the predicted values except for the 6-1/2 order, which is slightly higher due ta the change in the third mode natural frequency.
The measured maximum resonant. stresses at 5500 kw are:
Order Stress - ksi
'93 Made Crankshaft Gen. Shaf t 2-1/2 670 3.75 7 570 .98 .45.
10 605 .09
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't.KVx. IKLr,t ur'It.K 4oo 3 -i >-or ~ Q.or 44 I I I VD '7 o t'tvooc e rIo 07:35 GC-. CIP GENERAL
~M'ar'12,87 Grove City 412- 58-8000 eat. 4129 p. 1, Page 3
+/i)
The measured stresses at resonant stresses within 00 rpm axe
$-10% all quite small, and all of 600 @pm are well within the normal limit of ~5.0 ksi. Thus these results indicate the torsional vibration characteristics of this unit are completely satis2actory.
John M. Horne August 28, 1978 Distribution:
M. J. Helmich J. N. Roeder-L. S. Ulrey R. A. Kiklos
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