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Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML20216E4791999-09-0909 September 1999 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 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 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 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 ML20210U8701997-09-0808 September 1997 Rev 3,change 2 to Vol 1 of Inservice Exam Program, for Pnpp 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 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
[Table view] Category:TEST REPORT
MONTHYEARML20209B3391999-06-28028 June 1999 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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ADSORBER BED THERMOCOUPLE TESTING RESULTS O
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Adsorber Bed Thermocouple Testing Results During the course of the initial event, certain thermocouples appear,ed to _
provide erroneous temperature indications. These thermocouples were tested and replaced as necessary. All 24 thermocouples presently installed in the adsorber vessels were checked for proper calibration prior to their reinstallation in July 1986 following the extinguishment of the second combustion event.
Temperature element 2N64N0023A was tested by PNPP Metrolcgy Lab personnel to verify the quality and reliability of the type of thermocouples installed in the Unit 1 off-Gas System. The temperature element as described on GE drawing #174B9371, dated 11/4/71, with rev. level 6 on 10/11/79, is a type E chromel constantan with the following design specifications.
- 1. Class C pressure integrity 600 lb SS flange (ANSI B16.5) mount
- 2. Process fluid-air
- 3. Pressure - 350 psig l
- 4. Temperature - 150'F
- 5. 18 AWG premium grade wire in ceramic insulation enclosed in 316 series stainless steel sheath 30" x 1/4" O
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- 6. Accuracy-specialcalibrationrehiredfor11.0*F@75'F On June 21, 1986 a functional test was performed on temperature element (2N64N0023A) against a fluke Digital hermoccuple Thermometer with it's married probe, L70-R024P, (accuracy 11 0*F). The data was obtained by using a sand bath which reaches approximately 900*F. We probes were wired together to avoid any temperature gradients. The data indicates that the temperature element had an error of <3'F.
DATA USING SAND BATH
%ermometer 'F TE
69.2 69.2 0.0 O 211.3 y 209.3 2.0 393.5 391.0 2.5 701.2 698.6 2.6 886.0 884.6 1.4 Because of limits of the sand bath, the temperature element (2N64 N0023A) and the thermometer were taken to the CEI 20th St. Lab on June 25, 1986, where they have an ashing furnace. This furnace provides a stable temperature at any point up to approximately 2000*F. The procedure was to place sand within a clay cup that was about 6 inches in diameter into the furnace. %e thermometer and the temperature element undergoing testing were inserted into the sand approximately 6-8 inches. %e furnace was programmed for the various O
temperatures desired until the test was completed. The measurements made June 21, 1986 were consistent with the data taken at 20th St. Lab in the same range. During the checks at the higher temperatures using the furnace, the probes were allowed to equalize in temperature for approx. 45-60 minutes per data point.
DATA USING ASHING EURNACE Thermometer 'F TE 'F Error 'F 508.10 507.60 0.50 698.30 697.60 0.70 888.80 887.10 1.70 1037.48 1034.96 2.52 1186.52 1183.10 3.42 1362.92 1357.70 5.22 1556.42 1548.14 8.28 O
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Upon return to the PNPP Metrology Lab another test was performed to verify repeatability at the lower values. After being exposed to high temperatures for approximately 7 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br /> the following data was found. -
OIL BATH
'Ihermometer 'F TE 'F Error "F 213.2 212.5 0.7 AMBIENT WATER BATH
- Thermometer 'F TE 'F Error 'F O 71.0 0.1 71.1 The upper temperature limits for protected thermocouples can be between 1000 and 1832'F depending on the manufacturer and the gage of wire used. The nominal upper temperature range if a type E thermocouple is 1832'F and 1600*F for the sheath. (ISA, ANSI MC 96.1 " Temperature Measurement Thermocouples" August 1982, pg. a thru 43)
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In conclusion, a thermocouple's characteristics may change after exposure to very high temperatures. But the results obtained from the research in the l l
Metrology Lab provides a high degree of confidence that the thermocouples in question were manufactured well and responded properly, even at very high temperatures. Any uncertainty in the testing would stem from unwanted temperature gradients in the furnace or baths and the long sheath of the temperature element.
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