ML20203G112
From kanterella
| ML20203G112 | |
| Person / Time | |
|---|---|
| Site: | Perry  |
| Issue date: | 07/24/1986 |
| From: | Kuty J NUCLEAR CONSULTING SERVICES, INC. |
| To: | |
| Shared Package | |
| ML20203G077 | List:
|
| References | |
| R-5293-65, S-101347, NUDOCS 8607310328 | |
| Download: ML20203G112 (5) | |
Similar Documents at Perry | |
|---|---|
Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML20216E4791999-09-0909 September 1999
[Table view]Proposed Tech Specs Revising Allowable Values for CST Low Water Level Limits from Greater than or Equal to 59,700 Gallons to Greater than or Equal to 90,300 Gallons ML20216E4631999-09-0909 September 1999 Proposed Tech Specs Change Eliminating Requirement in EPP to Sample Lake Erie Sediment in Perry & Eastlake Plant Area for Corbicula,Since Corbicula & Zebra Mussels Have Already Been Identified & Control & Treatment Plans Are Implemented ML20211P2871999-09-0909 September 1999 Proposed Tech Specs Pages,Increasing Present 100% Authorized Rated Thermal Power Level of 3579 Megawatts Thermal to 3758 Megawatts Thermal ML20210M7851999-08-0404 August 1999 Proposed Tech Specs 3.9.1,incorporating Addl Option Into Required Actions When Refueling Interlocks Are Inoperable ML20209B3391999-06-28028 June 1999 Simulator Four Yr Test Rept ML20196A2021999-06-17017 June 1999 Proposed Tech Specs SRs Implementing 24-month Operating Cycle at Pnpp ML20205C6351999-03-16016 March 1999 Preliminary Rev 0 to Wps 01-43-T-801, Preliminary Weld Procedure for Perry Nuclear Power Plant Feedwater Nozzle Repair ML20204E4971999-03-15015 March 1999 Proposed Tech Specs,Correcting Typos Found in Table 3.3.6.1-1 ML20207K1041999-03-0404 March 1999 Proposed Tech Specs Improving Licensing & Design Basis for Isolation of FW Penetrations ML20206Q3571999-01-0606 January 1999 Proposed Tech Specs Improving Licensing & Design Basis for Isolation of Feedwater Penetrations ML20195H5381998-11-18018 November 1998 Rev 4 to Pump & Valve Inservice Testing Program Plan ML20155D9431998-10-27027 October 1998 Proposed Tech Specs 2.1.1.2,applying Addl Conservatism by Modifying MCPR Safety Limit Values,As Calculated by GE ML20155D8241998-10-27027 October 1998 Proposed Tech Specs Adding Two Paragraphs to TS 5.2.2.e, Organization - Unit Staff ML20196H5131998-10-0808 October 1998 Rev 4,Vol 1 to Inservice Exam Program for Perry Nuclear Power Plant ML20151V4831998-09-0909 September 1998 Proposed Tech Specs Stipulating That Water Leakage from Feedwater motor-operated CIVs Will Be Added Into Primary Coolant Sources Outside of Containment Program & Check Valves Do Not Need to Be Included in Hydrostatic Program ML20151V1111998-09-0303 September 1998 Proposed Tech Specs Permitting EDG TS Action Completion Time of Up to 14 Days for Div 1 or 2 EDG & Allowing Performance of EDG 24-hour TS SR Test in Modes 1 & 2 ML20151V6861998-09-0303 September 1998 Proposed Tech Specs Increasing Present Div 3 DG Fuel Oil Level Requirements to Account for Rounding Error in Calculation & Unusable Volume Due to Vortex Formation at Eductor Nozzles Located in Fuel Oil Storage Tank PY-CEI-NRR-2395, Rev 5 to Perry NPP Odcm. with1998-09-0202 September 1998 Rev 5 to Perry NPP Odcm. with ML20151S9561998-08-31031 August 1998 Proposed Tech Specs,Allowing Blind Flange in Inclined Fuel Transfer Sys (Ifts) Containment Penetration to Be Removed While Primary Containment Is Required to Be Operable ML20236T7911998-07-22022 July 1998 Proposed Tech Specs Revising MSL Leakage Requirements & Eliminating Msli Valve Leakage Control Sys ML20151P1921998-07-13013 July 1998 Proposed Tech Specs,Increasing Present +/- 1% Tolerance on Safety Mode Lift Setpoint for SRVs to +/- 3% ML20236H8411998-06-30030 June 1998 Proposed Tech Specs,Increasing Boron Concentration in Standby Liquid Control Sys for Pnpp Cycle 8 Fuel Design & Providing Margin for Future Cycles as Required ML20236T8451998-06-24024 June 1998 Rev 3,Change 3 to Vol 1 of Inservice Examination Program, for Pnpp ML20216H9361998-04-14014 April 1998 Rev 1 to Proposed TS Bases,Reflecting Changes Made Since Original Implementation of TS in Improved Format in June 1996 ML20203G4781998-02-23023 February 1998 Maint Progress Review for Perry Nuclear Power Plant ML20197F7871997-12-23023 December 1997 Proposed Tech Specs,Revising 3.8.1 Re AC Sources to Be Consistent W/Recommendations in GL 94-01, Removal of Accelerated Testing & Special Reporting Requirements for Edgs ML20217K6501997-10-22022 October 1997 Proposed Tech Specs Incorporating Temp Control Valves & Associated Bypass Lines Around Emergency Closed Cooling Sys Heat Exchanger ML20217F5911997-10-0202 October 1997 Proposed Tech Specs,Adding Note to TS 2.1.1.2 Re MCPR SL Values & Adding Footnote to TS 5.6.5.b to Reference NRC SER That Approved MCPR SL Values for Cycle 7 ML20210T9631997-09-0808 September 1997 Proposed Tech Specs 5.2.2.e,removing Reference to NRC Policy Statement on Working Hours.Rev Allows Changes to Specific Overtime Limits & Working Hours to Be Evaluated IAW 10CFR50.59, Changes,Tests & Experiments ML20210U8701997-09-0808 September 1997 Rev 3,change 2 to Vol 1 of Inservice Exam Program, for Pnpp ML20217Q4591997-08-28028 August 1997 Proposed Tech Specs 3.4.11,revising Pressure-Temp Limits,Per Reactor Vessel Matl Surveillance Program Requirements Contained in App H of 10CFR50.90 ML20148A6871997-05-0202 May 1997 Proposed Tech Specs Re Surveillance Requirement for MSIV Leakage Rate Acceptance Criteria ML20148A6591997-05-0202 May 1997 Proposed Tech Specs,Revising Existing Exception to LCO 3.0.4 as Applies to LCO 3.6.1.9 for MSIV Leakage Control Sys ML20137S7761997-04-0909 April 1997 Proposed TS Requirements 3.9.1.1 & 3.9.2.2 Re Frequency on Refueling Equipment & one-rod-out Interlocks ML20134D8251997-01-31031 January 1997 Proposed Tech Specs 1.1 Re definitions,3.6.1.1 Re Primary Containment - operating,3.6.1.2 Re Primary Containment Air locks,3.6.1.3 Re PCIVs,3.6.5.1 Re Drywell & 5.5 Re Programs & Manuals ML20147B8271997-01-24024 January 1997 Rev 3 to Vol 1 of Inservice Exam Program ML20134D8751996-10-24024 October 1996 Proposed Tech Specs 2.1.1.2,safety Limits Applying Conservatism by Increasing MCPR Safety Limit Values ML20117E7891996-08-27027 August 1996 Proposed Tech Specs,Revising Mls Leakage Requirements & Eliminating MSIV Control Sys ML20108A2581996-04-26026 April 1996 Proposed Improved Tech Specs ML20100N9501996-03-0101 March 1996 Proposed TS Pages Re Drywell Leak Rate Testing Requirements ML20100L3331996-02-27027 February 1996 Proposed Tech Specs Re Drywell Personnel Air Lock Shield Door Analyses ML20100J5971996-02-24024 February 1996 Proposed Tech Specs,Revising Definition of Core Alteration ML20149K2221996-02-17017 February 1996 Proposed Tech Specs,Reflecting Mod of Leakage Rate Requirements for Main Steam Lines Until End of Operating Cycle 6 ML20100G0161996-02-0101 February 1996 Draft Rev 0 to Pnpp NUMARC/NESP-007 Plant-Specific EAL Guidelines ML20096D4651996-01-16016 January 1996 Proposed TS Requirements for Drywell Leak Rate Testing ML20096C0591996-01-10010 January 1996 Proposed Tech Specs,Requesting one-time Surveillance Interval Extension to Support Current Schedule for Refueling Outage 5,scheduled to Begin 960127 ML20095H4721995-12-20020 December 1995 Proposed Tech Specs Re Replacement of Selected Analog Leak Detection Sys Instruments W/Ge Numac Leak Detection Monitor ML20108B2851995-11-22022 November 1995 Rev 5 to Offsite Dose Calculation Manual ML20094F2051995-11-0202 November 1995 Proposed Tech Specs for Handling Irradiated Fuel in Containment or Fuel Handling Bldg & Performing Core Alterations ML20094E6751995-11-0202 November 1995 Proposed Tech Spec,Requesting Rev to TS for Onsite Power Distribution Sys:Ts 3/4.8.3.1, Distribution - Operation 1999-09-09 Category:TEST REPORT MONTHYEARML20209B3391999-06-28028 June 1999
[Table view]Simulator Four Yr Test Rept ML20086B5471995-06-30030 June 1995 Pnpp Simulator Four Yr Test Rept ML20073H3571994-07-31031 July 1994 Clei Pnpp Primary Containment 1994 ILRT Final Rept ML20045H2121993-03-0101 March 1993 Primary Reactor Containment ILRT Rept, Conducted 930222- 0304 ML20116B4481992-10-20020 October 1992 Results of Acute Toxicity Test W/Daphnia Magna & Pimephales Promelas on Samples from Calgon Corp ML19324B7531989-11-0303 November 1989 Post-Refueling Startup Test Summary Rept,Cycle 2. ML19324B6611989-10-27027 October 1989 Summary Rept of Type B & C Test Failures. ML19327A7531989-07-31031 July 1989 Reactor Containment Bldg Integrated Leak Rate Test. ML20148H5941988-01-13013 January 1988 Reactor Internals Vibration Testing at Perry Unit 1, Preliminary Rept ML20234F2151988-01-0404 January 1988 Startup Test Results Final Summary Rept PY-CEI-NRR-0746, Startup Rept,Supplemental- 31987-11-16016 November 1987 Startup Rept,Supplemental- 3 ML20235K7421987-07-0808 July 1987 Page 55 to Startup Rept,Suppl - 1, Omitted from Rept Previously Submitted PY-CEI-NRR-0706, Startup Rept,Supplemental - 21987-06-27027 June 1987 Startup Rept,Supplemental - 2 PY-CEI-NRR-0661, Startup Rept,Supplemental - 11987-06-0303 June 1987 Startup Rept,Supplemental - 1 ML20212H5101987-03-0303 March 1987 Startup Rept ML20203G1271986-07-29029 July 1986 Adsorber Bed Thermocouple Testing Results ML20203G1121986-07-24024 July 1986 Carbon Sample Test Rept of Replacement Carbon Supplied by Nuclear Consulting Svcs,Inc ML20203G1061986-07-15015 July 1986 Carbon Sample Test Rept of Original Barneby Cheney Co Carbon ML20195C7791986-02-20020 February 1986 Rev 2 to Triaxial Peak Accelerograph Channel Calibr for D51-R120 (Reactor Recirculation Pump) ML20195C7601986-02-20020 February 1986 Rev 1 to Seismic Instruments Channel Check ML20126M4381985-05-31031 May 1985 Torsiograph Tests of Emergency Diesel Generators,Divs 1 & 2,at Perry Nuclear Power Plant-Unit 1 ML20126M4501985-05-31031 May 1985 Addendum to Torsiograph Tests of Emergency Diesel Generators,Divs 1 & 2,at Perry Nuclear Power Plant-Unit 1 on Cylinder Imbalance ML20087C5601984-02-0606 February 1984 Rev 0 to Sys Component Evaluation Worksheet for Class IE Equipment in Harsh Environ ML20087C6811984-02-0606 February 1984 Rev B to Sys Component Evaluation Workshop for Class IE Equipment in Harsh Environ ML20087C6381984-02-0606 February 1984 Rev a to Sys Component Evaluation Worksheet for Class IE Equipment in Harsh Environ ML20087C6001984-02-0606 February 1984 Rev B to Sys Component Evaluation Worksheet for Class IE Equipment in Harsh Environ ML20071P5271983-05-31031 May 1983 Analysis of Inaccessible & Potentially Rejectable Defects in Perry Nuclear Power Plant ML20043B7101981-11-18018 November 1981 Qualification Tests of Electrical Cables W/Extended Exposure to LOCA Environ. ML20043B7031975-05-31031 May 1975 Qualification Tests of Electric Cables for Class 1E Svc in Nuclear Power Plants. 1999-06-28 |
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