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Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML20217C0521999-10-0505 October 1999 Proposed Tech Specs 15.3.1.A,15.3.3.A & 15.3.3.C,eliminating Inconsistencies & Conflict Between TSs ML20210M6171999-08-0404 August 1999 Proposed Tech Specs 15.3.5,removing Word Plasma from Discussion of Type of Display Monitor for sub-cooling Info in CR & TS 15.3.7,removing Discussion That Allowed Delay in Declaring EDG Inoperable Due to OOS Fuel Oil Transfer Sys ML20210B5121999-07-15015 July 1999 Pbnp Simulator Four-Yr Rept ML20209C1831999-07-0101 July 1999 Proposed Tech Specs Page Re Amend to Licenses DPR-24 & DPR-27,removing Ifba Enrichment Curve Methodology from TS ML20205R6741999-04-12012 April 1999 Proposed Tech Specs Updating References to Reflect Relocation of Referenced Info in UFSAR ML20203A2261999-02-0202 February 1999 Proposed Tech Specs Bases Page 15.4.4,correcting References to Pbnp FSAR Re Reactor Containment Design ML20202F6521999-01-29029 January 1999 Proposed Tech Specs 15.6 & 15.7,reflecting Administrative Control Changes ML20154G5601998-10-0707 October 1998 Proposed Tech Specs Ensuring That 4 Kv Bus Undervoltage Input to Reactor Trip Is Controlled IAW Design & Licensing Basis for Facility ML20154H4231998-10-0505 October 1998 Proposed Tech Specs Section 15.4.1,removing Requirement to Check Environ Monitors on Monthly Basis ML20154C0561998-09-30030 September 1998 Rev 5 to Pbnp Units 1 & 2 IST Program Third 10-Yr Interval ML20154C1941998-09-28028 September 1998 Proposed Tech Specs Table 15.4.1-1 Re Min Frequencies for Checks,Calibrations & Tests of Instrument Channels ML20153G7361998-09-23023 September 1998 Proposed Tech Specs Removing Explicit Testing Requirements of TS Section 15.4.13, Shock Suppressors (Snubbers) ML20206E2731998-08-26026 August 1998 Rev 11 to Pbnps Odcm ML20206E2681998-08-26026 August 1998 Rev 12 to EM Environ Manual for Wepc ML20236W7861998-07-30030 July 1998 Proposed Tech Specs Change 206,revising to Incorporate Changes to TS to More Clearly Define Requirements for Service Water Sys Operability ML20249C3811998-06-22022 June 1998 Proposed Corrected Tech Specs Pages Re Radiological Effluents ML20248C6651998-05-28028 May 1998 Proposed Tech Specs Providing Specific Numerical Setting for Rt,Rcp Trip & AFW Initiation on Loss of Power to 4 Kv Buses ML20248G1671998-05-27027 May 1998 Proposed Edited Tech Specs Pages Adding CR & Condenser Air Ejector Radiation Monitor SR & Correcting Errors in Notes of Table 15.4.1-1 ML20203K9571998-02-26026 February 1998 Proposed Tech Specs,Revising Sections 15.3.6, Containment Sys bases,15.3.12 CREFS Including bases,15.4.4 Containment Tests bases,15.4.11 CREFS Including Bases, 15.6.8 Plant Operating Procedures & 15.6.12 ML20203K2981997-12-15015 December 1997 Proposed Tech Specs Re Administrative Controls ML20203K3081997-12-0808 December 1997 Rev 0 to Draft Radiological Effluent & Matls Control & Accountability Program ML20203K3231997-12-0202 December 1997 Rev 11 to Draft Odcm ML20203K3121997-12-0101 December 1997 Rev 12 to Draft Environ Manual Wisconsin Electric ML20203K3201997-11-25025 November 1997 Rev 0 to Draft Radiological Effluent Control Manual Wisconsin Electric ML20247P2681997-09-23023 September 1997 Proposed Tech Specs Implementing Boron Concentration Changes Re Planned Conversion of Unit 2 to 18-month Fuel Cycles ML20210M5151997-08-14014 August 1997 Proposed Tech Specs,Removing Requirement in Plant TS to Perform Pbnp Unit 2 Containment Integrated Leak Rate 60-months from Previous Test ML20210J0331997-08-0707 August 1997 Proposed Tech Specs,Replacing Wording & Double Underlining of Revised Wording ML20140C9111997-06-0303 June 1997 Proposed Tech Specs,Modifying TS Section 15.3.3, Eccs,Acs, Air Recirculation Fan Coolers & Containment Spray, to Incorporate AOT Similar to Ones Contained in NUREG-1431,Rev 1 ML20141C5931997-05-0909 May 1997 Proposed Tech Specs Section 15.3.3, Eccs,Acs,Air Recirculation Fan Coolers & Containment Spray to Incorporate Allowed Outage Times Similar to Those Contained in NUREG-1431,Rev 1 ML20140H0321997-05-0101 May 1997 Rev 5 to Training Programs Trpr 33.0, Licensed Operator Requalification Training Program ML20140H0171997-05-0101 May 1997 Rev 12 to Training Courses Trcr 86.0, Administrative ML20140G9811997-04-29029 April 1997 Assessment of Corrective Action Program Pbnp ML20140D7251997-04-14014 April 1997 Proposed Tech Specs,Changing Title of Corporate Officer Responsible for Nuclear Operations from Vice President- Nuclear Power, to Chief Nuclear Officer Per TS Section 15.6.2.1.c ML20140D7091997-04-14014 April 1997 Proposed Tech Specs,Eliminating Provisions for Operation of Units at Below 3.5% Rated Power W/Only One RCP ML20140G9241997-04-11011 April 1997 Rev 6 to ISTs IT 536, Containment Sump B Suction Line Leak Test (Refueling Shutdown) ML20140G9071997-04-0707 April 1997 Rev 8 to ISTs IT 525B, Leakage Reduction & Preventive Maint Program Test of 2SI-896A&B,SI Pump Suction Valves (Refueling) ML20140G8741997-04-0707 April 1997 Rev 35 to ISTs IT 04, Low Head Safety Injection Pumps & Valves (Quarterly) ML20217P2851997-04-0303 April 1997 Rev 10 to Point Beach Nuclear Plant,Units 1 & 2 Odcm ML20137N6451997-04-0202 April 1997 Proposed Tech Specs 14.2.4, Steam Generator Tube Rupture ML20140G9031997-03-21021 March 1997 Rev 8 to ISTs IT 325, CVCS Valves (Cold Shutdown) ML20140G9741997-03-21021 March 1997 Rev 0 to Operations Refueling Tests Ort 10A, Recovery from Integrated Lrt W/Core Off-Loaded ML20137C8331997-03-20020 March 1997 Proposed Tech Specs 15.2.2, Safety Limit,Reactor Coolant Sys Pressure ML20140G9621997-03-19019 March 1997 Rev 0 to Operations Refueling Tests Ort 9A, Preparation for Integrated Lrt W/Core Off-Loaded ML20140G9131997-03-17017 March 1997 Rev 4 to ISTs IT 535B, Leakage Reduction & Preventive Maint Program Test of Train B HHSI & RHR Sys (Refueling) ML20140G9521997-03-17017 March 1997 Rev 16 to Operations Refueling Tests Ort 6, Containment Spray Sequence Test ML20140G8821997-03-0404 March 1997 Rev 9 to ISTs IT 115, Instrument Air Valves (Quarterly) ML20140H3401997-02-28028 February 1997 WO Work Plan WO 9612073, Removal/Replacement of Breakers 1Y-06-11 ML20140H3011997-02-28028 February 1997 WO Work Plan WO 9612056, Removal/Replacement of Breakers 1Y-06-05 ML20140H3331997-02-28028 February 1997 WO Work Plan WO 9612072, Removal/Replacement of Breakers 1Y-06-01 ML20140H3241997-02-27027 February 1997 WO Work Plan WO 9612057, Removal/Replacement of Breakers 1Y-06-03 1999-08-04
[Table view] Category:TEST REPORT
MONTHYEARML20210B5121999-07-15015 July 1999 Pbnp Simulator Four-Yr Rept ML20086N3171995-07-19019 July 1995 Four-YR Performance Test Rept ML20045D6521993-12-31031 December 1993 Summary Rept,Reactor Containment Bldg Ilrt,Point Beach Nuclear Plant,Unit 1,1993. ML20059H4361993-12-14014 December 1993 Rev 1 to Third Interval of Pbnp ASME Section XI Periodic Pressure Test Program ML20126A1011992-12-14014 December 1992 Reactor Containment Bldg Integrated Leak Rate Test,Point Beach Unit 2 ML20077R9931991-08-16016 August 1991 Cycle 19 Startup Rept ML20006A3511990-01-0909 January 1990 Cycle 16 Startup. W/900118 Ltr ML20005E2351989-12-31031 December 1989 Reactor Containment Bldg Integrated Leak Rate Test,Point Beach Nuclear Plant Unit 2, Summary Rept ML20245J1091989-07-25025 July 1989 Wisconsin Electric Power Co Point Beach Nuclear Plant Unit 1 Cycle 17 Startup May 1989 ML20153G3481987-11-25025 November 1987 Rev 1 to Irradiation Study of Boraflex Neutron Absorber Interim Test Data, Interim Technical Rept ML20207E5321986-12-29029 December 1986 Summary Rept:1986 Unit 2 Integrated Leakage Rate Test ML20197H5651986-05-13013 May 1986 Reanalysis of Main Steam Line Outside Containment W/Energy Absorbers as Replacements for Hydraulic Snubbers for Point Beach Nuclear Plant ML20204F1671985-12-31031 December 1985 Test Rept on Static Load Tests on Liner Plate Leak Chase Channel Assemblies. Supporting Data Rept Encl ML20107D6841985-01-31031 January 1985 Cycle 11 Startup ML20093D2651984-03-30030 March 1984 Type B & C Leakage Testing Summary for Period Between Oct 1981 Type a Containment Integrated Leak Rate Test (Cilrt) & Mar 1984 Type a Cilrt ML20062K1691982-07-31031 July 1982 Rept of Reactor Containment Bldg Integrated Leakage Rate Test for Point Beach Unit 2 ML20011A4691981-09-30030 September 1981 Compressive Strength of Prisms & Concrete Blocks. ML20011A4661981-09-30030 September 1981 Evaluation of Allowable Tensile Stresses Normal to Bed Joint. ML20011A4761981-09-30030 September 1981 Evaluation of Single Wythe Assumption to Represent Multiple Wythe Walls. ML20011A4631981-09-30030 September 1981 Evaluation of Allowable In-Plane Shear Stresses & Strains. ML19312F0181981-09-15015 September 1981 Concrete Block & Prism Testing. ML19247D5421981-01-15015 January 1981 Steam Generator Crevice Flow Test for Wi Electric Power Co. ML19330C0581980-08-0505 August 1980 Steam Generator Insp Results W/Comparison to Previous Insps. ML20126D7061980-04-25025 April 1980 Microscopic & Other Examinations of Nuclear Steam Generator Tubing Removed in Mar 1980 ML19320D5111979-12-28028 December 1979 Seventy-Two Hour Test of Turbine-Driven Auxiliary Feed Pump. ML19320D5231979-12-26026 December 1979 Seventy-Two Hour Test of Electrically-Driven Auxiliary Feed Pump. ML19320D5261979-12-23023 December 1979 Seventy-Two Hour Test of Electrically-Driven Auxiliary Feed Pumps. ML19320D5181979-12-0707 December 1979 Seventy-Two Hour Test of Turbine-Driven Auxiliary Feed Pump. ML20104A3871979-02-28028 February 1979 Inservice Test Plan,Feb 1979. W/Drawings of Reactor Coolant Sys Process,Safety Injection Sys & Chemical & Volume Control Sys ML20236X6381978-09-15015 September 1978 Rev 0 to Summary Rept of Equipment Qualification Analyses 1999-07-15
[Table view] |
Text
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~ WHTP 11.22 Date /3.-d3~)7 MAJOR DSS ' 'f_JK Revision 0
( ;;.; , P38 A _ 6br B g
, I2-05-79 I
72 HOUR TEST OF ELECTRICALLY-DRIVE!! AUXILIARY FEED PUMPS CAUTIOli IF THERE IS ANY PROBLEM IN PERFOR!!ING THIS OPERATION, OPERA-I}21EDIATELY !!OTIFY THE DUTY SHIFT SUPERVISOR.
BILITY OF TilIS EQUIPMENT IS A TECHNIC'.L STECIFICATICN
' REQUIREMENT.
1.0 PURPOSE Demonstrate continuous operation of the pump for 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> while in recirculation rnode.
2.0 INITIAL CONDITIONS Auxiliary feed system lined up for critical operation as per CL-13E.
Initials
,p)
.- 3.0 PROCEDURE
<u b[O .
.- 3.1... . Check oil levels on auxiliary feed pump, hM 3.2 Shut discharge valves MOV-4094 and -WG-3-(4020 and 4021). :
3.3 Start auxiliary feed pump. //b Time
- ) 2 f 1 9 /</ e n 3.4 Check mini-recirculation valve-4003-(4014).
D Check packing glands for excessive leakage or overheating. )TYi
- 3.5
$M
, ; 3.6 Check pump and motor for unusual noise or overheating.
- 3.7 Take an initial set of readings and record on the data sheet. Continue pump operation for 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />. Record a
readings hourly except vibration readings which are recorded each eight hours.
y)vi1g
.- NOTE: CUT IN PI-4914A (4017A) ONLY TO OBTAIN READING.
3.8 Secure auxiliary feed pump. / .2 - 9. C -79 /pcCs
- c. 3.9 After one-half hour, start the pump and observe for any unusual operations. _
{'] ,
a.
'8007210//6() .
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MITP 11.22 Page 2
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Initiale 3.10 Continue operation for one hour. Record data on the data sheet, po3 c 3.11. Secure the pump.
p Open MOV-4922-and M (4021 and 4020)T h
3.12 3.13 Return system to normal lineup.
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