Similar Documents at Perry |
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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 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
[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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n NUCON~ TECHNOLOGY ADSORPTION PROCESSES, ADSORBENTS, ENGINEERING, INSTRUMENTS, SERVICES IL EJ pe .
Carbon Sample Testing Report performed for Cleveland Electric Illuminating Co.
Perry Nuclear Plant P.O. S-101347 R-5293-65 DISTRIBUTION CEI: (2) Perry Nuclear Power Plant l NUCON: (1) Master File I
(1) Lab File (1) QA 8887MMBt8%o S
O NUCON 50C0069 NUCON INTERNATIONAL. INC TE L E PHONE 614'846-57)7
. _ _ , _ _ _ - - - - . . . - - - ' ' - - ' ' ' ' ' ~
O NUCLEAR CONSULTING $[RYlCES,O INC sto_ 24 July 1986 Q r.c e . nni w.* . o .n" Project __50C0069
( CARDON SAMPLE TESTING Requested By _
(q_)
CLICi:T: CEI Perry DescripticBI-1/First 20,000 lbs Disposition:
Order No.S-101347 R-5293-65 Discard Sample No. Composite of each 1000 lbs Retain 6 mos.
Lot No. CEI-1 ,
12 mos.
Datch No. _
Indefinitely -
_ TEST NO. ,AS IS < 150*C DRIED , HIGH TEMP, REACT. ,
A.D. a/ml ASTM D20S4 X 0.53 '
_CC14 wt % ASTM D3467 '
RET. wt %
P. S. minutes
_ SURFACE AREA m2/a I2 NO.
PORE VOL, MICR0 ml/a PORE VOL, MACR 0 ml/a Aminct H70 wt % ASTM D2867 X 1.5 ASH wt % ASTM D2866 X 3.4 HARDNESS % ASTM D3802 X 98.4 VOLATILE wt %
pH ASTM D3838 IGNITION 'C ASTM D3466 y 373 CAR 8ONATE SOL. opm CHLORIDE Total opm CHLORIDE SOL. ppm
_ NITRATE S01.. ppm AV. PARTICLE SIZE risher
- K Xenon cc/R PROC 30 X 1225113 PARTICLE SIZE DIST. ASTM D2862 MESH SIZE Wat. % Cum. OPE NING _ Wat. % Cum. REMARKS On 6 0.5 0.5 525 C. ,305 SCFM 6 inch On 8 63.6 62.8 test bed, -30*C dewpoint On 12 35.9 35.4 air. average of three DTNS On 16 0.8 0.8
_On 20 0.4 0.4 i
Date 25 July 1986 Thru 20 0.1 0.1 Thru Tested byh d i Total 101.3 100.C Total Certified by M [ /a b l
i
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_ _ . . _ _ _ _ _ . _ _ - - - - - - - - - - - - - - -- ~
N NUCLEAR CONSUtilNG SERVICES, INCp 74 ul ir R6 e o e.. nm waa. om mn project _50C0069
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( CARDON SAMPLE TESTING CLIti;T: m _ Perrv Requested By_ -
"\ Description CEI-2/First 15.000 lbs N Order No, to e e. . . e , t.1 :' 9 52 9 3-K Disposition:
Discard Sample No.
Retain 6 mos.
Lot No. 2 12 mos.
Batch No. , Inde finitely TEST NO. ,AS IS 1500C DRIED ,
HIGH TEMP. REACT. ,
A.D. o/ml ASTn 020S4 X 0.51 E lo ut % ASTM 03467 RET. wt %
P. S. minutes SURFACE AREA m2/a I2 NO.
PORE VOL. MICR0 ml/o PORE VOL. MAERO ml/n Aminct H70 wt % ASTM 02867 X 1.9
, _ ASH wt % ASTM 02866 X 2.2 HARONESS % ASTM 03802 X 98.8 VOLATILE wt %
pH ASTN 03838 IGNITION 'C ASTM 03466 y als
. CARBONATE SOL. ppm CHLORIDE Total opm CHLORIDE SOL. ppm NITRATE SOL. ppm AV. PARTICLC SIZE Fisher
- Kr cc/g PROC 30 X 7412.0 l ,
l
- Xe cc/g PROC 30 X 1230 5.0 PARTICLE SIZE DIST. ASTM 02862
, MESH SIZE Wat. % Cum. OPENING Uqt. % Cum. REMARKS
\
On 6 0.3 0.3 .305 cfm. 25 C On 8 50.3 50.6 -30 C dewooint On 12 45.3 45.5 6 inch bed on 16 3.5 3.5 average of three DTNS i
l On 20 0.0 0.0 Date P- Q #t> /7/5 Thru 20 0.1 0.1 Thru Tested by hMd Total 99.5 100.0 Total Certified by W zew
N NUCLEAR CONSULTING SERVICES, INC D ato 23 July 1986 Q r o u nm <*- w. on en" Project 50C0069
( CARDON SAMPLE TESTING Requested By f'-
O Q CLIEUT: CEI - Perry Description CEl-3 Final 15,000 lbs Disposition:
Order No, f> e 8 s /p / 3 4 7. R - C '13 -/ T Discard Sample No. Retain 6 mos.
Lot No. 3 12 mos.
Batch No. -
Indefinitely TEST NO. AS IS , 150 C DRIED , HIGH TEMP. REACT, ,
A.D. o/ml ASTn 02054 X 0.50 CfC14 wt % ASTn 03467 RET. wt %
P. S. minutes SURFACE AREA m2/a
_I2 NO.
PORE VOL. MICR0 ml/a PORE VOL. MACR 0 ml/o Aminec H70 wt % ASTn 02067 X 1.8 ASH wt % ASTn 02866 X 2.5 HARONESS % ASTn 03802 X 98.7 VOLATILE wt %
pH ASTn 03838 IGNITION oC ASTn 03466 X 380 CARBONATE SOL opm CHLORIDE Totel ppm CHLORIDE SQL, ppm NITRATE S01.. ppm AV. PARTICLE SIZC Fisher
- Kr cc/g PROC 30 X 75 1.3 .
- Xe cc/g PROC 30 X 123515 PARTICLC SIZE DIST. ASTn D2862 MESH SIZE Wat. % Cum. OPENING , Uqt. % Cum. REMARKS On 6 0.2 0.2
- 305 cfm, 25 C on 8 55.1 55.4 -30"C Dewpoint On 12 41.5 41.7 6 inch bed on 16 2.5 2.5 average of three DTNS C') On 20 0.1 0.1 Date J[M #h Li / ,y Thru 20 0.1 0.1 Thru Tested by tr$4 -
Total 00_5 inn n Total Certi fied by //4-