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Category:ARCHIVE RECORDS
MONTHYEARML17313B0901996-02-13013 February 1996 Rev 0 to Calculation of Bonnet Fluid Temp for MOV SI-604/609. ML17312A7841995-12-0101 December 1995 Rsb 5-1 SD Cooling Analysis for 102% Stretch Power Using Descent Code Pvngs,Units 1,2 & 3. ML17310B2541994-04-12012 April 1994 Risk Impact of Extending TS LCO for EDG B. ML17310A6771993-09-0909 September 1993 Rev 1 to Calculation, Auxiliary Spray Line Thermal Stratification. ML17311A4471993-01-28028 January 1993 Seismic Study of Bldg. ML20079M9531991-11-11011 November 1991 Responds to NUMARC Survey in Support of NRC License Renewal Rulemaking Covering Aquatic Resources,Socioeconomic Questions & Waste Mgt Questions ML17306A1791990-12-0707 December 1990 Calculation 13-NC-SQ-200, Sample Line Plateout. ML17305A7001990-03-0606 March 1990 Package of 4 Preexam Security Agreements Made Prior to Requalification Exam Scheduled for 900320 & 21 ML20114D9641990-02-25025 February 1990 Package Consisting of Plant Lighting Sys Evaluation, Summation of Sys Engineer Walkdown Unit One & Emergency Lighting Action Plan ML17304A7611988-10-11011 October 1988 EC Sys & Control Room Temp Rise Study,Quality Class:Q Safety-Related. ML17304A7631988-09-28028 September 1988 Control Room Heat Load Calculation. ML17304A7621988-09-20020 September 1988 Bearing Temps Calculation for AFA-P01,EWA/B-P01 & SIA/B-P01 Motors Subjected to Elevated Room Temps. ML17304A7741988-06-22022 June 1988 Transient Temp Study for Electrical Penetration Rooms, Quality Class Q:Safety-Related. ML17304A7691988-05-10010 May 1988 Transient Temp Study for Auxiliary Feedwater B Pump Room. ML17304A7701988-04-0404 April 1988 Transient Temp Study for HPSI Pump Room. ML17304A7711988-04-0404 April 1988 Transient Temp Study for Containment Spray Pump Room. ML17303A8201988-03-0202 March 1988 Proposed License Condition for Reactor Coolant Pump Vibration Monitoring Program ML20149H9011987-10-0808 October 1987 Package Consisting of Repts of Licensee Telcons to Region V Re Incidents on 871007 & 1221 ML20151M9601987-07-20020 July 1987 Package of NRC Administered Requalification Exam Results Summary ML20214L1061987-05-22022 May 1987 Package Consisting of Undated LER Sequence & Coding & Search Sys Data Run,Data from NRC ES7 Actuation Data Base & Handwritten Staff Notes Re LER 87-071 ML20210T0571987-02-12012 February 1987 Package of Two Documents,Consisting of Viewgraph Detailing 860514 Disruption of Offsite Power Lines & Map of Palo Verde Region ML20214E2781986-05-16016 May 1986 Partially Withheld Record of 860516 Telcon Re FBI Investigation of Facility Power Lines.Partially Withheld Record of 860519 Telcon Also Encl IA-86-774, Partially Withheld Record of 860516 Telcon Re FBI Investigation of Facility Power Lines.Partially Withheld Record of 860519 Telcon Also Encl1986-05-16016 May 1986 Partially Withheld Record of 860516 Telcon Re FBI Investigation of Facility Power Lines.Partially Withheld Record of 860519 Telcon Also Encl ML17299B0771986-01-21021 January 1986 Record of Telcon W/Nrc on 860121 Re Annual FSAR Update Exemption Request ML20136E5911985-10-30030 October 1985 Viewgraphs Discussing 850912 Reactor Trip,Safety Injection & Loss of Pressurizer Auxiliary Spray Sys & Outlining Agenda for 851008 Pressurizer Auxiliary Spray Design Review & post-trip Review Rept.Related Info Encl ML20129F4831985-05-0909 May 1985 Package of Compilations of Results of Operator Licensing & Requalification Exams ML20112E7801984-11-30030 November 1984 Technical Audit Conducted During Oct-Nov 1984 ML20085M8481983-08-12012 August 1983 Press Release Re Delay in Fuel Loading Due to Defective Reactor Coolant Pumps.Unit 1 Fuel Load Date Extended to Late Dec 1984 ML20080T5521983-07-14014 July 1983 Press Release Discussing Coalition Demands on Independent Investigation Into Safety Problems at Facilities.Local & Natl Organizations Requesting NRC to Order Independent Investigation of Worker Allegations of Faulty Const ML20066F3111982-07-13013 July 1982 News Release Announcing Results of Facility Const Cost & Schedule Analysis ML17297B6141982-07-0202 July 1982 Revised Page 16 to Slide Presentation Entitled, Tentative Feature Selection. ML20101U2081982-06-29029 June 1982 Slide Presentation Entitled Independent QA Evaluation of Palo Verde Nuclear Generating Station Units 1,2 & 3. Related Documents Encl ML20079F0931982-02-17017 February 1982 Newspaper Article Re Higher Const Costs at Arizona Nuclear Project ML17297A9151981-06-18018 June 1981 Vol III of 810617-18 Slide Presentation Re Independent Design Review of Instrumentation & Control Sys Before Instrumentation & Control Sys Review Board ML20065G7251975-06-26026 June 1975 Power Cable Ampacities 1996-02-13
[Table view] Category:PACKAGE OF NONCODED MATERIAL
MONTHYEARML20079M9531991-11-11011 November 1991 Responds to NUMARC Survey in Support of NRC License Renewal Rulemaking Covering Aquatic Resources,Socioeconomic Questions & Waste Mgt Questions ML17305A7001990-03-0606 March 1990 Package of 4 Preexam Security Agreements Made Prior to Requalification Exam Scheduled for 900320 & 21 ML20114D9641990-02-25025 February 1990 Package Consisting of Plant Lighting Sys Evaluation, Summation of Sys Engineer Walkdown Unit One & Emergency Lighting Action Plan ML17303A8201988-03-0202 March 1988 Proposed License Condition for Reactor Coolant Pump Vibration Monitoring Program ML20149H9011987-10-0808 October 1987 Package Consisting of Repts of Licensee Telcons to Region V Re Incidents on 871007 & 1221 ML20151M9601987-07-20020 July 1987 Package of NRC Administered Requalification Exam Results Summary ML20214L1061987-05-22022 May 1987 Package Consisting of Undated LER Sequence & Coding & Search Sys Data Run,Data from NRC ES7 Actuation Data Base & Handwritten Staff Notes Re LER 87-071 ML20210T0571987-02-12012 February 1987 Package of Two Documents,Consisting of Viewgraph Detailing 860514 Disruption of Offsite Power Lines & Map of Palo Verde Region ML20136E5911985-10-30030 October 1985 Viewgraphs Discussing 850912 Reactor Trip,Safety Injection & Loss of Pressurizer Auxiliary Spray Sys & Outlining Agenda for 851008 Pressurizer Auxiliary Spray Design Review & post-trip Review Rept.Related Info Encl ML20129F4831985-05-0909 May 1985 Package of Compilations of Results of Operator Licensing & Requalification Exams 1991-11-11
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)R INFORMATION ONL June 1, 1985 ATTACHMENT 1 PALO VERDE NUCLEAR GENERATING STATION, UNIT 1 OPERATING LICENSE NPF-41 This attachment identifies items which must be completed to the NRC staff's satisfaction in accordance with the schedule identified below.
Surveil ce. Pro ram Prior to entering Mode I for the first time, .APS shall
- a. Have completed a review of the surveillance procedures applicable to the change of mode, and determined that the procedures demonstrate the operability of the required systems with respect to all
. acceptance criteria defined in the Technical Specifications.
- b. Have dispatched written notification to the NRC Regional Administrator, Region V, that the action. defined in (a), above, has been completed for Mode I.
2.
8803090225 880302 PDR ADOCK 05000528 P
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- 2. APS shall implement an augmented vibration monitoring program for each of the four reactor coolant pumps that includes the following elements:
a~ Every four hours, monitor and record vibration data on each of the four reactor coolant pumps.
- b. On a daily basis, perform an evaluation of the pump vibration data obtained in a. above, by using an appropriately qualified engineering individual.
C ~ When any one vibration monitor on the reactor coolant pumps indicates a vibration level of 8 mils or greater, the Nuclear Regulatory Commission shall be notified within four hours via the Emergency Notification System. In addition, when the vibration on any pump exceeds 8 mils due to a shaft crack or unknown cause, within four hours the affected pump shall have its orbit and spectra continuously monitored and evaluated by an appropriately qualified individual.
- d. When any one vibration monitor on the reactor coolant pumps indicates a vibration level of 10 mils or greater, within one hour, initiate action to place the unit in at least HOT STANDBY within the next six hours, and at least COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />. In addition, the affected pump shall be secured after entering HOT STANDBY.
- e. On a daily basis a spectrum analysis shall be performed on the reactor coolant pump shaft vibration data and shall be evaluated for trends by using an individual qualified in that technique. The evaluation shall consist of comparing the running speed (1xRPM) and twice running speed (2xRPM) spectral components to limits computed from the baseline vibration. The limits shall be based on the lowest of: (a) 1.6 times the baseline value, (b) the mean plus three standard deviations, (c) 2 mils for the 2xRPM component, or (d) 6 mils for 1xRPM component. 1/
When the amplitude exceeds any limit, further analysis shall be performed. This analysis shall consist of an inspection of the amplitude versus time plots for a steadily increasing trend, and a review of other plant data which might explain the change in amplitude. If it is confirmed that the trend is not caused by plant or pump conditions unrelated to a shaft crack, the trend shall be extrapolated manually and/or by computer to predict the time at which the vibration is expected to reach 10 mils. If the projected time for reaching 10 mils is one week or less, within one hour, initiate action to place the Unit in at least HOT STANDBY within the next six hours and at least COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />. In addition, the affected pump shall be secured after entering HOT STANDBY.
The Regional Administrator, Region V may relax or rescind, in writing, any of the above vibration monitoring conditions upon a showing by the licensees of good cause.
licensee to assure that the new methods are equal to or better than the above method. The Commission shall be advised within one week, if new methods are chosen.
1 V