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Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARB17848, Startup Test Rept Cycle 7. with1999-09-30030 September 1999 Startup Test Rept Cycle 7. with ML20211Q3361999-09-0707 September 1999 Proposed Tech Specs Removing Current Special Exception Which Precludes Applying Eighteen Month Functional Testing Surveillance to SG Hydraulic Snubbers ML20211H6471999-08-25025 August 1999 Proposed Defueled Tech Specs,Revising Sections 5.6.1,5.7.2 & 5.7.3 & Adding Proposed Section 5.6.4 to Reflect ACs Contained in NUREG-1433 ML20210Q5211999-08-0505 August 1999 Proposed Tech Specs Sections 3.8.3.2,4.6.2.1,4.6.2.2, 4.8.1.1,4.9.12 & Bases Section B 3/4.3.2,B 3/4.6.1.2 & B 3/4.8.4,incorporating Editorial Revs ML20210C6091999-07-16016 July 1999 Proposed Tech Specs Relocating Selected TS Related to Refueling Operations & Associated Bases to Plant TRM ML20206U1041999-05-17017 May 1999 Proposed Tech Specs Section 4.4.6.2.2.e,deleting Reference to ASME Code Paragraph IWV-3472(b) Re Frequency of Leakage Rate Testing for Valves Six Inches Nominal Pipe Size & Larger ML20206M8221999-05-10010 May 1999 Restart Assessment Plan Millstone Station ML20206D1761999-04-27027 April 1999 Rev 1 to Millstone Unit 3 ISI Program Manual,Second Ten-Yr Interval ML20205R2411999-04-19019 April 1999 Rev 3 to CP2804L, Unit 2 Rx Coolant & Liquid Waste Pass ML20205R2501999-04-19019 April 1999 Rev 0 to CP2804M, Unit 2 Vent & Containment Air Pass ML20205R2751999-04-19019 April 1999 Proposed Tech Specs,Reflecting Permanently Defueled Condition of Unit ML20205S5611999-04-16016 April 1999 Rev 5 to Epop 4426, On-Site Emergency Radiological Surveys ML20205M0891999-04-0707 April 1999 Proposed Tech Specs Modifying Value for Monthly Surveillance Testing of Tdafwp ML20205E4411999-03-29029 March 1999 Rev 2 to CP 2804L, Unit 2 Rx Coolant & Liquid Waste Pass ML20196K5771999-03-24024 March 1999 Rev 1 to Chemistry Procedure CP2804L, Unit 2 Rx Coolant & Liquid Waste Pass ML20205D5321999-03-22022 March 1999 Rev 3 to RPM 2.3.5, Insp & Inventory of Respiratory Protection Equipment ML20204J1581999-03-19019 March 1999 Proposed Tech Specs Section 6, Administrative Controls, Reflecting Certified Fuel Handler License Amend Changes, Approved on 990305 ML20204J4101999-03-19019 March 1999 Proposed Tech Specs Relocating Instrumentation TSs 3.3.3.2, 3.3.3.3 & 3.3.3.4 to Mnps,Unit 2 TRM ML20204K0971999-03-19019 March 1999 Proposed Tech Specs Supporting Spent Fuel Pool Rerack to Maintain Full Core Reserve Capability Approaching End of OL ML20204F9031999-03-17017 March 1999 Proposed Tech Specs,Revising 3.5.2,3.7.1.7 & 3.7.6.1 Re ECCS Valves,Atmospheric Steam Dump Valves & CR Ventilation Sys. Associated Bases Will Be Modified as Necessary to Address Proposed Changes ML20207H9551999-03-0505 March 1999 Proposed Tech Specs Section 6.0 Re Administrative Controls ML20206K1121999-03-0505 March 1999 Proposed Tech Specs Bases Sections 3/4.7.7, CR Emergency Ventilation Sys & 3/4.7.8 CR Envelope Pressurization Sys. Changes Are Editorial in Nature ML20207F6211999-03-0303 March 1999 Rev 2,change 1 to Communications - Radiopaging & Callback Monthly Operability Test ML20207E0321999-03-0202 March 1999 Proposed Tech Specs 3/4.7.4, SW Sys, Proposing Change by Adding AOT for One SW Pump Using Duration More Line with Significance Associated with Function of Pump ML20207D4821999-02-26026 February 1999 Proposed Tech Specs Re Addl Mods Concerning Compliance Issues Number 4 ML20207J0001999-02-22022 February 1999 Rev 7 to Millstone Unit 2,IST Program for Pumps & Valves ML20206D1991999-02-11011 February 1999 Change 7 to Rev 5 to ISI-3.0, Inservice Testing Program. Pages 2 of 3 & 3 of 3 in Valve Relief Request Section 6.1 of Incoming Submittal Not Included ML20203E4051999-02-11011 February 1999 Proposed Tech Specs Re DG Surveillance Requirements ML20210D2121999-01-21021 January 1999 Proposed Tech Specs Sections 3/4.5.2 & 3/4.5.3, ECCS Subsystems for Info Only ML20199L2841999-01-20020 January 1999 Proposed Tech Specs & Final SAR Proposed Rev to Ms Line Break Analysis & Revised Radiological Consequences of Various Design Basis Accidents ML20199L0801999-01-18018 January 1999 Proposed Tech Specs Change to TS 3/4.2.2 Modifies TS to Be IAW NRC Approved W Methodologies for Heat Flux Hot Channel factor-FQ(Z).Changes to TS Section 6.9.1.6 Are Adminstrative in Nature ML20199L4561999-01-18018 January 1999 Proposed Tech Specs Revising TS Table 3.7-6, Air Temp Monitoring. Proposed FSAR Pages Describing Full Core off- Load Condition as Normal Evolution Under Unit 3 Licensing Basis,Included ML20199L3271999-01-18018 January 1999 Proposed Tech Specs 3.6.1.2, Containment Sys - Containment Leakage ML20199L0431999-01-18018 January 1999 Proposed Tech Specs Removing TS 3/4.6.4.3, Containment Systems,Hydrogen Purge Sys ML20199E0931999-01-13013 January 1999 Rev 2 to Health Physics Support Procedure RPM 2.3.4, Insp & Maint Process for Respiratory Protection Equipment ML20206P5121999-01-0404 January 1999 Proposed Tech Specs 3.5.2,3.6.2.1,3.7.1.2,3.7.3.1 & 3.7.4.1, Incorporating Changes to ESF Pump Testing B17501, 1998 - 2000 Performance Plan - Work Environ Focus Area Update1998-12-31031 December 1998 1998 - 2000 Performance Plan - Work Environ Focus Area Update ML20198K6361998-12-31031 December 1998 Proposed Tech Specs Section 6.0, Administrative Controls ML20199A7531998-12-31031 December 1998 Restart Backlog Mgt Plan Commitments ML20198P9751998-12-28028 December 1998 Proposed Tech Specs Pages Revising Loss of Normal Feedwater (Lonf) Analyses to TS 2.2.1,TS Bases Change to Floor Value for Thermal Margin Low Pressure Reactor Trip & Proposed FSAR Changes ML20196H6301998-12-0404 December 1998 Proposed Tech Specs Re Section 6.0, Administrative Controls ML20197G9831998-12-0404 December 1998 Proposed Tech Specs 4.7.10.e,eliminating Need to Cycle Plant & Components Through SD-startup Cycle by Allowing Next Snubber Surveillance Interval to Be Deferred Until End of RFO6 of 990910,whichever Date Is Earlier ML20196A2181998-11-20020 November 1998 Restart Assessment Plan Millstone Station ML20195D4041998-11-10010 November 1998 Proposed Tech Specs,Modifying Sections 3.3.1.1 & 3.3.2.1 by Restricting Time That Reactor Protection or ESF Actuation Channel Can Be in Bypass Position to 48 H,From Indefinite Period of Time ML20195D8101998-11-10010 November 1998 Revised marked-up Page of Current TS 3.8.1.1 & Revised Retyped Page Re 980717 Request to Change TS ML20195H8681998-11-0404 November 1998 Rev 4 to Millstone Unit 2 Operational Readiness Plan ML20196H5921998-10-29029 October 1998 Rev 0 to TPD-7.088, Millstone 1 Certified Fuel Handler/ Equipment Operator Continuing Training Program ML20196H5861998-10-29029 October 1998 Rev 0 to TPD-7.087, Millstone 1 Certified Fuel Handler Training Program B17548, Rev 0 to TPD-7.089, Millstone 1 Equipment Operator Training Program1998-10-29029 October 1998 Rev 0 to TPD-7.089, Millstone 1 Equipment Operator Training Program ML20155B0331998-10-22022 October 1998 Proposed Tech Specs Changing TS 3.3.2.1, Instrumentation - ESFAS Instrumentation, 3.4.9.3, RCS - Overpressure Protection Sys & ECCS - ECCS Subsystems - Tavg 300 F 1999-09-07
[Table view] Category:TEST REPORT
MONTHYEARB17848, Startup Test Rept Cycle 7. with1999-09-30030 September 1999 Startup Test Rept Cycle 7. with ML20236Y1781998-06-25025 June 1998 Rev 0 to 61138-99N, Test Rept for Addl Testing of Chicago Pneumatic Pumps for Use at Northeast Utils MP-3 ML20236Y1751998-01-19019 January 1998 Rev 0 to Rept 61035-98N, Test Rept for Qualification & Dedication of Chicago Pneumatic Pumps for Use at Northeast Utils MP-3 ML20137G2491997-03-18018 March 1997 Results of Aquatic Toxicity Testing of LCS-1000 in Effluents Discharged to Marine Receiving Waters B15414, Startup Test Rept for Cycle 131995-10-31031 October 1995 Startup Test Rept for Cycle 13 B15368, Startup Test Rept Cycle 61995-09-30030 September 1995 Startup Test Rept Cycle 6 ML20064H0621994-03-0707 March 1994 Startup Test Rept for Cycle 5 B14723, Reactor Containment Bldg ILRT Rept1993-10-31031 October 1993 Reactor Containment Bldg ILRT Rept ML20077N5681991-06-30030 June 1991 Startup Test Rept, Cycle 4 ML20058E1221990-10-29029 October 1990 Vols 3 & 4 to Millstone Unit 3 Simulator Certification Submittal:Performance Test Rept ML19327A7261989-10-31031 October 1989 Startup Test Rept Cycle 3. W/891011 Ltr B13337, Summary Rept,Cycle 13 Start-Up Physics Testing1989-08-15015 August 1989 Summary Rept,Cycle 13 Start-Up Physics Testing B13305, Startup Test Rept Cycle 101989-07-31031 July 1989 Startup Test Rept Cycle 10 B12902, Assessment of Reverse Direction Testing of Containment Isolation Valves1988-05-31031 May 1988 Assessment of Reverse Direction Testing of Containment Isolation Valves B12864, Northeast Nuclear Energy Co Millstone Unit 2 Reactor Containment Bldg Integrated Leak Rate Test1988-05-31031 May 1988 Northeast Nuclear Energy Co Millstone Unit 2 Reactor Containment Bldg Integrated Leak Rate Test B12865, Startup Test Rept,Cycle 91988-04-30030 April 1988 Startup Test Rept,Cycle 9 B12440, Startup Test Rept Cycle 81987-03-31031 March 1987 Startup Test Rept Cycle 8 B12019, Summary Rept,Cycle 11 Startup Physical Testing1986-03-31031 March 1986 Summary Rept,Cycle 11 Startup Physical Testing ML20133N0651985-10-31031 October 1985 Startup Test Rept,Cycle 7 ML20138L2061985-07-31031 July 1985 Reactor Containment Bldg Integrated Leakage Rate Test,Types A,B & C ML20138R7921985-06-16016 June 1985 Reactor Containment Bldg Integrated Leak Rate Test, 850614-16 ML20135E4231985-03-29029 March 1985 Rev 0 to Fire & Hose Stream Test of 8-Inch Thick Specimen of TCO-002 Medium Density Silicone Elastomer Used in Electrical Sleeve Opening Penetrated by Extended Aluminum Conduit ML20135E4341985-03-27027 March 1985 Rev 0 to Fire & Hose Stream Test of 8-Inch Thick Specimen of TCO-002 Medium Density Silicone Elastomer Used in Electrical Sleeve Opening Penetrated by Extended Steel Conduit ML20138K9761984-07-0909 July 1984 Fire Loop Flow Test ML20087P7131984-03-31031 March 1984 Startup Test Rept Cycle 6 ML20091M4041983-12-25025 December 1983 Reactor Containment Bldg Integrated Leak Rate Test, 831223-25 ML20087D3691983-07-31031 July 1983 Development of Long-Term Effluent Toxicity Testing Procedure W/Bay Mysid (Mysidopsis Bahia) & Preliminary Testing Results at Millstone Nuclear Power Station ML20087D3501983-07-31031 July 1983 Effluent Toxicity Testing at Millstone Nuclear Power Station Using Sheepshead Minnow (Cyprinodon Variegatus) During 1981-82 ML20054H6341982-05-31031 May 1982 Startup Test Rept Cycle 5 ML20040A5541982-01-12012 January 1982 Steam Generator Eddy-Current Test Results,Jan 10,1982. ML20058E4371981-11-16016 November 1981 Flame Spread Classification Smoke & Fuel Contribution ML19350A5111981-03-31031 March 1981 Nonproprietary Version of Hydraulic Flow Test of Model C Prototype Fuel Assembly. ML19318A3451980-06-30030 June 1980 Large Break Loca/Eccs Performance Results. ML19323C5951980-05-31031 May 1980 Steam Generator Insp. ML19296B0471980-02-0808 February 1980 RCS Asymmetric Loads Evaluation Program;Interim Rept. ML19254D5991979-09-0707 September 1979 Startup Test Results,Cycle 3. ML20125A9491979-08-10010 August 1979 Reactor Containment Bldg Integrated Leak Rate Test, 790425-0501 ML20058E4401977-10-19019 October 1977 Rept on Flame Test Conducted on Cable Raceway Sys 1999-09-30
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MILLSTONE l' NIT NO. 3 FIRE LOOP FLOW TEST On July 9, 1984, Generation Fire Protection Engineerine conducted a water flow test of the 12 inch underground fire water loop at Millstone Unit No. 3. The purpose of this flow test was to determine the water supply / pressure available, in order to provide a reference point for deternining epn/ psi throughout FP-III's underground loop.
The flow test was conducted utilizing two hydrants located within the northeast portion of the fire loop (North of 'Jaste Disposal Building & North of Maintenance Shop). Please refer to the attached sketch. Two 21"5 fire hoses (150' in length each) were connected to the flow hydrant. Attached to each hose was a standard Underwriters Laboratories (UL) playpipe (1 3/4" tip). Static and residual pres-sure readings were obtained using a calibrated pressure gage installed within the flow path.
The rate of flow in gallons per ninute (CPM) was determined by measurine, the velocity pressure of each strea, utilizing a calibrated pitet cao,e. The test findings were as follows:
Static Pressure 124 psi Residual Pressure 119 psi Hose #1 Pitot Reading 36 psi or 546 gpm Hose #2 Pitot Reading 40 psi or 575 gpm It was concluded that this remote hydrant is capable of delivering 1121 gem at a pressure of 119 psi.
RICHARD S. WARRISER bb4x 7/9/8Y
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Generation Fire Protection Engineerine Generation Engineering Department 8510310095 851007 PDR ADOCK 05000423 F PDR
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