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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/INSPECTION/OPERATING PROCEDURES
MONTHYEARML17313B0081999-07-14014 July 1999 Rev 2 to Inservice Insp Program Summary Manual for PVNGS Unit 1. ML17313A7511998-12-16016 December 1998 Rev 2 to ISI Program Summary Manual, for PVNGS Unit 3 ML17312A9451996-05-14014 May 1996 Rev 3 to Significant Condition Investigation. ML17312A5691996-03-0505 March 1996 Revised Pages to ISI Program Summary Manual ML17311B3181995-12-20020 December 1995 Revised Pages to ISI Program Summary Manual ML17312A9381995-02-0303 February 1995 Corrective Action Program. ML17310B0911994-03-0202 March 1994 SG Tube Insp Plan. ML17310B0251994-01-27027 January 1994 Unit 2 Steam Generator Tube Insp Plan Addendum. ML17310A7421993-10-27027 October 1993 Revised Unit 1 SG Tube Insp Plan. ML17310A6501993-09-17017 September 1993 Unit 1 SG Tube Insp Plan. ML20056D3951993-08-0909 August 1993 Rev 04.01 to Procedure 41AO-1ZZ08, SG Tube Leak ML20056D3961993-06-16016 June 1993 Rev 00.07 to Procedure 41EP-1R004, Excess Steam Demand, Consisting of CRS Actions & Details on Emergency Notification & Support ML20056G0111993-03-21021 March 1993 Rev 7 to Odcm ML17306A9831992-09-0303 September 1992 Window 2B08B, Rc LO Temp Over Press of Rev 5 to Procedure 40AL-9RK2B ML17306A9841992-09-0303 September 1992 Window 2B08B, SDC Ln Isol VLV Not Fully Closed of Rev 5 to Procedure 40AL-9RK2B ML17306A9851992-09-0303 September 1992 Window 2B09A, SDC Ln Isol Vlvs UV-653/654 Inverter Trbl of Procedure 40AL-9RK2B ML17306A9871992-09-0303 September 1992 Window ES2A01B, LO Press Safety Inj of Rev 2 to Procedure 41AL-1ES2A ML17306A4741991-10-30030 October 1991 Rev 2 to Nuclear Administrative & Technical Manual 76PR-9RW01, Solid Radwaste Process Control Program. ML20085L3671991-10-28028 October 1991 Emergency Response Data Sys (ERDS) Implementation Program Plan for Palo Verde Nuclear Generating Station ML17305B5521991-01-31031 January 1991 Rev 6 to Salt Deposition & Impact Monitoring Plan for Palo Verde Nuclear Generation Stations,Units 1,2 & 3. ML17305B2731990-07-31031 July 1990 PVNGS 1991 Business Plan. ML17306A5181989-10-22022 October 1989 Rev 0 to Nuclear Administrative & Technical Manual 01PR-0QQ02, Employee Concerns Program Policy. ML17306A5161989-09-28028 September 1989 DOL000483, Employee Concerns Program. ML20127J4161989-03-0808 March 1989 Procedure 2-3-89-001, Safety Equipment Status Sys ML20082D9681989-01-18018 January 1989 Rev 1 to Nuclear Administrative & Technical Manual 81AC-OCC07, Cable & Raceway Control & Tracking Sys ML20082D9721988-08-19019 August 1988 Rev 0 to Administrative Change Notice 03 to ES03.03, Cable & Raceway Control & Tracking Sys ML20082E6001988-07-11011 July 1988 Rev 0 to Administrative Change Notice 02 to ES03.03, Cable & Raceway Control & Tracking Sys ML20082D9801988-06-21021 June 1988 Rev 2 to QA02.02, QC Insps ML20082D9871988-06-0202 June 1988 Rev 0 to ES10.00, Sys Engineer Program ML20082D9901988-05-26026 May 1988 Rev 7 to 73AC-OZZ29, Engineering Evaluation Request ML20082E6221988-05-19019 May 1988 Rev 0 to Administrative Change Notice 01 to ES03.03, Cable & Raceway Control & Tracking Sys ML17304A1651988-05-10010 May 1988 Loose Part Monitoring Sys Loose Part Detection Program Rept. W/Eleven Oversize Drawings ML20082E6291987-09-0202 September 1987 Rev 0 to ES03.03A, Cable & Raceway Control & Tracking Sys ML20237H5571987-08-0303 August 1987 Public Version of Revs to Emergency Plan Implementing Procedures,Including Temporary Procedure Change Notice (Tpc) 3 to Rev 5 to EPIP-02, Emergency Classification & Tpc Notice 2 to Rev 11 to EPIP-03.W/870820 Release Memo ML20235X0961987-07-0202 July 1987 Public Version of Revised Emergency Plan Implementing Procedures,Including Rev 3 to EPIP-56, UHS Emergency Water Supply, Rev 4 to EPIP-33, Offsite Assistance & Rev 5 to EPIP-27, Post-Accident Sampling Analysis ML17300A7801987-04-16016 April 1987 Procedure Change Notice 1 to Rev 0 to Procedure 41AO-1ZZ54, Monitoring Reactor Vessel Inventory W/Reactor Vessel Level Monitoring Sys Inoperable. W/870416 Ltr ML17303A3611987-03-20020 March 1987 Test/Retest Recovery Program Diesel Generator B & Associated Support Equipment. ML17333A1801987-03-13013 March 1987 Diesel Generator B Test Insps. ML20206N4501987-03-0606 March 1987 Public Version of Revised Emergency Plan Implementing Procedures,Including Procedure Change Notice 02 to Rev 5 to EPIP-02, Emergency Classification, Closing Out Open Item Noted by NRC ML20212M8121987-01-28028 January 1987 Public Version of Revised Emergency Plan Implementing Procedures,Including Rev 11 to EPIP-04 Re Alert,Site Area & General Emergency Implementing Action,Consisting of Temporary Change Notice 02T ML20214U1761986-09-11011 September 1986 Public Version of Procedure Change Notice 3 to Rev 10 to Emergency Plan Implementing Procedure EPIP-3, Notification of Unusual Event Implementing Actions. W/860925 Release Memo ML20205E5391986-07-29029 July 1986 Public Version of Revised Emergency Plan Implementing Procedures,Including Rev 4 to EPIP-23, Fire Fighting, Rev 5 to EPIP-02, Emergency Classification & Rev 11 to EPIP-04, Alert,Site Area.. ML20211Q5951986-07-10010 July 1986 Public Version of Rev 10 to EPIP-03, Notification of Unusual Event Implementing Actions & Rev 4 to EPIP-15, Protective Action Guidelines. W/Procedure Change Notices 1 & 2 to EPIP-03 ML20212N2671986-07-0303 July 1986 Public Version of Revised Emergency Plan Implementing Procedures,Including Rev 5 to EPIP-02, Emergency Classification & Rev 10 to EPIP-03, Notification of Unusual Event Implementing Actions ML17300A3731986-06-25025 June 1986 Rev 0 to Pump & Valve Inservice Testing Program, for Units 1,2 & 3 ML17300A2611986-05-29029 May 1986 Rev 0 to Inservice Insp Program Summary Manual. ML20155K1011986-04-17017 April 1986 Public Version of Revised Emergency Plan Implementing Procedures,Including Rev 10 to EPIP-03 Re Notification of Unusual Event Implementing Actions & Rev 9 to EPIP-04 Re Alert Implementing Actions.W/Grimsley 860521 Release Memo ML20206E5991986-04-0808 April 1986 Public Version of Revised Emergency Plan Implementing Procedures,Including Procedures Index,Cancellation of Rev 2 to EPIP-28, Personnel Monitoring & Decontamination & Cancellation of Rev 2 to EPIP-29 ML17299B1791986-03-11011 March 1986 Public Version of Revised Emergency Plan Implememting Procedures EPIP 11,EPIP 19 & EPIP 20 & Revs 1 to Administrative Procedures 7N409.08.00 & 7N409.09.00, respectively.W/860409 Release Memo ML17299B0501986-02-21021 February 1986 Rev 2 to Operations Procedure 42AO-2ZZ50, Venting Charging Pumps. 1999-07-14
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ENCLOSURE UNIT 1 STEAM GENERATOR TUBE INSPECTION PLAN
,9309240009 930917 PDR ADOCK'.05000528, 8 PDR
UNIT 1 STEAM GENERATOR TUBE INSPECTION PLAN The Unit 1 steam generator will be inspected for tube defects using Eddy Current Testing (ECT) technology as opposed to ultrasonic or other NDE methods. The inspection scope and criteria for scope expansion are described below:
INITIALSCOPE:
~ 100% Full Length Bobbin Coil Eddy Current Inspection.
~ 20% hot leg tube sheet and 01H support with Motorized Rotating Pancake Coil (MRPC) ~
MRPC the 08H support to the first vertical support in highest risk arc of approximately 1800 tubes (highest risk arc is based on the Unit 2 pattern of defects). See Figure 1.
MRPC the 08H support to the first vertical support, approximately 570 tubes outside the arc of 1800 tubes.
Bases: 100% full length bobbin coil ECT provides assurance that a widespread pattern of flaws does not exist. The MRPC sample at the tubesheet and 01H support assures circumferential cracks are not forming, and the previously noted cracking at 01H is not progressing. The 1800 tube arc was empirically determined to be the highest risk area from Unit 2 eddy current test data, and if cracks are developing due to the same phenomenon seen in Unit 2 this is where they are expected to be found. The sample of 570 tubes outside the highest risk area provides confidence that cracks are not developing outside the highest risk area.
CRITERIA FOR EDDY CURRENT EXPANSION MRPC:
~ For each tube with a hot leg "I" bobbin indication (NQI, DSI, DTI, BLI, and PLI)', conduct MRPC of the indication area and from the 08H support to the first vertical support.
NQI - Non-Quantifiable Indication; DSI - Distorted Support Signal with Indication; DTI- Distorted Top of Tubesheet with Indication; BLI - Baseline Indication; PLI - Possible Loose Part with Indication.
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Bases: MRPC is required to resolve what "I" code indications are.
In the interest of increasing the data base each time an "I" code indication is examined with MRPC, the 08H support to the first vertical support will also be examined to increase the data base at this elevation.
~ Treat the arc of 3800 tubes as the area of interest.
o If less than 1% (1-17 tubes) of the MRPC sample has NBI axial midspan flaw(s) conduct a 6% (228 tubes) expansion with MRPC from the 08H support to the first vertical support.
In all cases a five tube buffer will be maintained, from the NBI
~
tube.
o If 1% (18 tubes) or more of the sample has NBI axial midspan flaws MRPC the entire area of interest from the 08H support to the first vertical support.
Bases: The Unit 2 ECT data has shown the Unit 2 failure mechanism to be limited to an analytically determined arc of approximately 3800 tubes where thermal-hydraulic conditions can create an aggressive chemical environment. By treating the susceptible area separately, we can apply Technical Specification methodology to MRPC and establish expansion criteria that zeroes in on the area at risk.
~ The area outside the arc of 3800 tubes is treated independently.
o If one or more tubes are discovered to have an NBI axial indication, MRPC the 08H support to the first vertical support in a 6% sample of the area outside the arc (433 tubes) including surrounding tubes until a buffer zone of five tubes is established. Use the results from this sample to define an area of interest and determine what if any further expansions should be done.
o Define areas of interest if a pattern of NBI flaws develops.
Bases: The selection of a 6% sample expansion is analogous to Technical Specifications Table 4.4-2. The results of the 6% sample will be used to identify if a pattern exists so that the area at risk will be examined.
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Any circumferential crack at the tubesheet triggers a 100% MRPC of the tubesheet area.
SECONDARY SIDE INSPECTION:
A visual examination of one steam generator secondary side will be conducted by looking through the manway to determine whether resin has entered the generators, with further actions being based on the results of that inspection.
During the current outage, APS will be installing handholes in the secondary side of the Unit 1 steam generators. An inspection will be conducted of the accessible areas of the tubesheet in each steam generator, in conjunction with the handhole installation.
STEAIVI GENERATOR TUBE PULLING:
Preparations will be made for tube pulling as a contingency. However, the decision to pull tubes from Unit 1 steam generator(s) will depend on the eddy current test results.
The plans regarding this contingency are presented below.
~ Tube pulls will only be done to det'ermine the root cause of failure for significant failure mechanisms not consistent with known phenomenon.
~ If tube pulls occur, up to two tubes will be selected that satisfy as many of the following objectives as possible:
o Tubes which appear to show failure to comply with Regulatory Guide 1.121 o Confirm burst test correlation o Gather ECT detectability data o Gather growth rate data o Support MRPC flaw sizing effort 3of4
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ADVANCED INSPECTION TECHNOLOGY:
Conam will be the vendor used to conduct ECT in the Unit 1 outage. Various technical advances will be used to explore methods to increase the resolution and speed of ECT inspection. These include:
~ Multiple MRPC probes will be used to allow simultaneous testing of up to four tubes.
Rotating field MRPC probe may be tested, but not used for primary data collection.
~ High speed MRPC probes will be tested, and may be used for primary data collection.
~ Bobbin inspection from the cold leg side will be conducted simultaneously with MRPC inspection from the hot leg side.
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09/93, ARIZONA PUBLIC SERVICE CO., PALO VERDE, UNIT i DATE: O7/13/O3 .
STEAM GENERATOR:
PROC: 73TI-9RCO1 11 Rev.8 i Q~'C ~ TIME: 17: 48: 51 CRITERIA: PROJECTED MPRC OSH 1ST VERTICAL STRAP STAYS PLUGGED Group1 2370 X E 0 Tc4& 45 X'50 gp ~ oF X MA~~Sl (8~~6 r iSk /}rc) 150 140 140 130 3 /etc% T~~
120 gdva N 110 100 100 90 90 80 80 70 60 50
= 60 50 40 40 30 30 20 20 10 10 10 20 30 40 50 60 70 80 90 100 110 120 130 140 150 160 170 180 CONAN NUCLEAR. INC. BN
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