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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
[Table view] |
Text
ONTROLLED DOCUME Procedure Number 41AL-lES2A Page 151 of 300 Revision 2 Window No.
ES2A01B Window Label LO PRESS SAFETY INJ 'age 1 of 18 ANNUNCIATOR WINDOW INDEX SYST WIND GROUP ID ID COMPONENT WINDOW LABEL POSSIBLE CAUSE j
A SEAS 19K LPSI Pmp A POl Pump A Not Running SEAS 15H LPSI Hdr A to RC Lp lA Vlv UV-635 Valve Not Fully Open SEAS 18H LPSI Hdr A to RC Lp 1B Vlv UV-645 Valve Not Fully Open SEAS 18L LPSI Pmp A Rm Ess ACU Z02 ACU Not Running D SEIS 19K LPSI Pmp A POl Pump A Inoperable E SEIS 15H LPSI Hdr A to RC Lp 1A Vlv UV-635 Valve Inoperable SEIS 18H LPSI Hdr A to RC Lp 1B Vlv UV-645 Valve Inoperable SEIS 18L LPSI Pmp A Rm Ess ACU Z02 ACU Inoperable SEIS 18I SDC Cont Vlvs HV-657/HV-686 Valve Inoperable or HV-685/HV-688 HV-688 Not Fully Closed SEIS 19M SDO Lp I LPSI Suet Vive UV-651/UV-655 Va jve Inoperabl~e SEIS 19I LPSI Suet Warm Up Hx Valve Inoperable, HV-306 Byp HV-306 HV-683/HV-691 Closed or HV-683 Not Fully Open 92092502bi 920903 ADOCKe05000528 PDR P ... PDR
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CONTROLLED DOCUME Page 166 of 300 Window No.
procedure Number 41AL-lES2A Revision 2 ES2A01B Wmdow Label LO PRESS SAFETY INJ Page 16 of 18 SECOND PRIORITY OPERATOR ACTION 1.0 Determine which valves are affected. Inform the Control Room Supervisor and ensure compliance with the following Technical Specifications:
1.1 Valve SIA-UV-651 failure
- a. 3.5.2 Modes 1, 2 and 3 - ECCS Subsystems - T<<~g > 350 F 1.2 Valve SIA-UV-655 failure
- a. 3.5.2 Modes 1, 2 and 3 - ECCS Subsystems - T<<~g 350 F
- b. 3.6.3 Modes 1, 2, 3 and 4- Containment Isolation Valves 2.0 Ifvalve SIA-UV-651 or -655 did not close from B02, direct a Nuclear Operator to manually, fully close the affected valve.
3.0 NOTIFYthe Nuclear Operator of the alarm. DIRECT him to CHECK for possible causes of the alarm and INITIATEaction as necessary to correct the problem. Possible causes of the alarm include:
3.1 Valve motor power supply breaker E-PHA-M3503 or -M3504 for SIA-UV-651 or -655 respectively or backup breaker E-PHA-M3507A for SIA-UV-651 is open.
3.2 Tripped thermal overloads at the valve motor power supply breaker switchgear E-PHA-M3503 or -M3504 for valve SIA-UV-651 or -655 respectively.
3.3 Blown control power fuse or failed control circuit in the valve motor power supply breaker switchgear E-PHA-M3503 or -M3504 for valve SIA-UV-651 or -655 respectively.
4.0 Perform independent verification on all applicable valves, breakers and components that were operated by this alarm response per 02AC-OZZ01, Independent Verification of Valves, Breakers and Components.
CONTROLLED DOCUMENT Procedure Number 4IAL-lES2B Page 138 of 289 Revision Window No.
ES2B01B Window Label LO PRESS S~~ WJ Page 1 of 20 ANIVUNCIATORWINDOW INDEX SYST WIND GROUP ID ID COMPONENT WINDOW LABEL POSSIBLE CAUSE A SEAS 19K LPSI Pmp B POl Pump B Not Rmzoing SEAS 15H LPSI Hdr B To RC Lp 2A Vlv UV-615 Valve Not Fully Open SEAS 18H LPSI Hdr A To RC Lp 2B Vlv UV-625 Valve Not Fully Open SEAS 18L LPSI Pmp B Rm Ess ACU Z02 ACU Not Running D. SEAS 13H Hot Leg Inj A/B Chk Vlv LeatoKVlvs Valve Not FuQy Closed, UV-322/UV-332 SEIS 19K LPSI Pmp B P01 Pump B Inoperable SEIS 15H LPSI Hdr B To RC Lp 2A Vlv UV415 Valve Inoperable SEIS 18H LPSI Hdr B To RC Lp 2B Vlv UV-625 Valve Inoperable G SEIS 18L LPSI Pmp B Rm Ess ACU Z02 ACU Inoperable SEIS 18I SDC Cont Vlvs HV-658/ HV-696 Valve Inoperable or HV-694/HV-693 HV-693 Not Fully Closed
(-I SEIS IBM SDC Lp 2 LPSI Suet Vlys UV-652/UV-656 alve Inoperable J SEIS 19I LPSI Suet Warm Up HX Byp Valve Inoperable, HV-307 HV-692/HV-690 HV-307 Closed or HV-692 Not Fully Open
C4t Q)NTROLLED DOCUME Procedure Number 41AI 1ES2B Page 154 of 289 Revision 2 Window No.
ES2B01B Window Label LO PRESS SAFETY INJ Page 17 of 20 RESPONSE SECTION GROUP I SYST WIND ID ID COMPONENT WINDOW LABEL POSSIBLE CAUSE
~SEIS~9M SDC Lp 2 LPSI Suet Valve-UV=652/UV-656 Valve Inop~eraBle=
AUTO ACTION None NOTE The shutdown cooling line &om loop 2 to LPSI pump B suction isolation valves SIB-UV-652 and -656 are normally shut unless the shutdown cooling system is in operation and act to prevent overpressurization of the shutdown cooling system, along with redundant isolation valve SID-'UV-654, when the RCS pressure is greater than 400 psia.
FIRST PRIORITY'OPERATOR ACTION A. Valve SIB-UV-652 or -656 Not Full Shut 1.0 MAINTAINRCS pressure less than 370 psia as indicated on pressurizer pressure recorder RCN-PR-100 on panel B04 or pressurizer pressure indicators RCA-PI-102A, RCB-PI-102B, RCC-PI-102C and RCD-PI-'102D on panel B05.
2.0 Close/Check Closed Redundant Isolation Valve SID-UV-654 at Switch SID-HS-654 on B02.
B. Valves SIB-UV-652 and -656 Shut None
Procedure Number 41AL-1ES2B Page 155 of 289 Revision 2 Window No.
ES2BOIB Window Label LO PRESS SAFETY INJ Page 18 of 20 SECOND PRIORITY OPERATOR ACTION 1.0 Determine which valves are aQected. Inform the control room Supervisor and ensure Compliance with the following Technical Specifications:
1.1 Valve SIB-UV-652 Failure:
- a. 3.5.2 Modes 1, 2 and 3 - ECCS Subsystems - 'Infold > 350 F 1.2 Valve SIB-UV-656 Failure:
- a. 3.5.2 Modes 1, 2 and 3 - ECCS Subsystems - Tcold) 350 F
- b. 3.6.3 Modes 1, 2, 3 and 4 - Containment Isolation Valves 2.0 IfSIB-UV-652 or -656 did not close &om B02, direct a Nuclear Operator to manually, fully close the affected valve.
3.0 NOTIFY the Nuclear Operator of the alarm and.DIRECT him to check for possible causes of the alarm. Initiate action as necessary to correct the problem. Possible causes of the problem include:
3.1 Open valve motor power supply breaker E-PHB-M3604 or -M3605 for valve SIB-UV-652 or -656 respectively or open backup breaker E-PHB-M3604A for valve SIB-UV-652.
3.2 Tripped thermal overloads at the valve motor power supply breaker switchgear E-PHB-M3604 or -M3605 for valve SIB-UV-652 or -656 respectively.
3.3 Blown control power fuse or failed control circuit at the valve motor power supply breaker switchgear E-PHB-M3604 or -M3605 for valve SIB-UV-652 or -656 respectively.
4.0 Perform independent verification on all applicable valves, breakers and components that were operated by this alarm response per 02AC4ZZOl, Independent Verification of Valves, Breakers and Components.
(
