ML18037A015
From kanterella
Jump to navigation
Jump to search
| ML18037A015 | |
| Person / Time | |
|---|---|
| Site: | Nine Mile Point  |
| Issue date: | 06/30/1984 |
| From: | STONE & WEBSTER ENGINEERING CORP. |
| To: | |
| Shared Package | |
| ML18037A014 | List: |
| References | |
| RTR-NUREG-0737, RTR-NUREG-737 GL-82-33, PROC-840630, NUDOCS 8407050199 | |
| Download: ML18037A015 (2) | |
Similar Documents at Nine Mile Point | |
|---|---|
Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML17059C7911999-09-30030 September 1999
[Table view]Proposed Tech Specs Re Rev B to Conversion of Unit 2 Current TS to ITS ML20211P5931999-09-10010 September 1999 Marked-up Tech Specs Pages Reflecting Conforming Administrative License Amend Associated with Proposed Transfer of Facilities to Amergen Energy Co,Llc ML20211H2231999-08-26026 August 1999 Proposed Tech Specs,Supporting Implementation of Noble Metal Chemical by Raising Reactor Water Conductivity Limit in TSs 3.2.3.a,3.2.3.c.1 & 3.2.3.b ML18041A0731999-07-27027 July 1999 Rev 1 to NMP2-ISI-006, Second Ten Year Interval Inservice Insp Program Plan for Nine Mile Point Nuclear Power Station Unit 2. ML20206P2661998-12-30030 December 1998 Proposed Tech Specs Making Application of Emergency Condenser Vent Ng Activity Monitor Channel Operability Requirement & Daily Sensor Check SR Consistent with Conditions Stated in LCO 3.1.3.a Re Emergency Cooling Sys ML20197K1041998-12-0404 December 1998 Revised Proposed TS Bases Reflecting Previous Removal of Condenser Low Vacuum Scram Function from TS as Well as Plant Design & Changes to EDG Ratings,Design Basis Load Limits & Loading Profiles ML20196H0671998-11-30030 November 1998 Proposed Tech Specs,Correcting LCO & Associated Bases for TS Section 3.1.2, Liquid Poison Sys, That Had Been Incorporated Into TS as Part of NMP Unit 1 TS Amend 101 ML20196D2081998-11-24024 November 1998 Proposed Tech Specs B 2.1.1, Fuel Cladding - Safety Limit, B 3.2.5 & 4.2.5, Reactor Coolant Sys Leakage Rate ML20154R1101998-10-16016 October 1998 Proposed Ts,Revising LCO 3.7.1.1 & Associated Actions & SRs to Provide Assurance That Four SW Pumps Are Operable & Are Operating within Acceptable Sys Parameters,With Divisional Cross Connect Valves Open ML20217N7911998-04-24024 April 1998 Revised Pages 2-1,3/4 4-1 & B2-1 to Replace Previously Submitted Pages Contained within Attachment a of 971215 Proposed Change to TS to License NPF-49 ML20202G3751998-02-0505 February 1998 Proposed Tech Specs Pages,Reflecting References to 10CFR50.55a(f) & (G) as Well as Terminology Used in Second Ten Year Isi/Ist,Beginning on 980405 ML20197H3371997-12-15015 December 1997 Proposed Tech Specs Revising SLMCPR from 1.07 to 1.09 for Two Recirculation Loop Operation & from 1.08 to 1.10 for Single Loop Operation ML20211M5231997-10-0707 October 1997 Proposed Tech Specs Section 4.9.6,reflecting New Setpoints Due to Difference in Weights of Two Existing Triangular Refueling Platform Masts ML20217G9011997-07-31031 July 1997 Proposed Tech Specs Changing Wording in Action 36 of TS Table 3.3.3-1, Emergency Core Cooling Sys Actuation Instrumentation ML20148A7751997-04-30030 April 1997 Proposed Change to Tech Specs,Removing Section 3.3.7.3 & Associated Surveillance Section 4.3.7.3,associated Tables 3.3.7.3-1 & 4.3.7.3-1,Bases Section 3.4.3.7.3 & Revising Section 0.0 (Index) Pages VII & Xvii ML17059B2911996-09-0404 September 1996 NMP Nine Mile Point Nuclear Station Unit 2,Pump & Valve First Ten-Yr Inservice Testing Program Plan. ML20116D8121996-07-26026 July 1996 Proposed Tech Specs Re Option B of App J to 10CFR50 ML20115H1521996-07-12012 July 1996 Proposed Tech Specs Section 6.2.2.i Re App a ML20117F9501996-05-15015 May 1996 Proposed Tech Specs Section 3/4.3.2 Re Isolation Actuation Instrumentation ML20101F4281996-03-20020 March 1996 Proposed TS 3/4.3.1 Re RPS Instrumentation,Deleting Operability Requirements for APRM Neutron flux-upscale, Setdown & Inoperative Functions in Operational Conditions (Oc) 3 & 4 & Modifying Operability Requirements in Oc 5 ML20101D7551996-03-15015 March 1996 Proposed Tech Specs Section 4.6.2 Re Depressurization Sys - Suppression Pool ML20097D2391996-02-0707 February 1996 Proposed Tech Specs Re Administrative Controls ML20100C1021996-01-25025 January 1996 Proposed Tech Specs Table 3.3.3-1 Re Emergency Core Cooling Sys Actuation Instrumentation ML20096G8401996-01-17017 January 1996 Proposed Tech Specs,Representing Revs to Specs 3/4.3.1, 3/4.3.2,3/4.3.3,3/4.3.4.2 & Associated Bases to Relocate Response Time Limit Tables from TSs to Plant USAR ML20094B5421995-10-25025 October 1995 Proposed Tech Specs Re Position Title Changes & Reassignments of Responsibilities at Upper Mgt Level ML20091Q9571995-08-28028 August 1995 Proposed TS 3.6.1.7,increasing Time 12-inch & 14-inch Containment Purge Sys Supply & Exhaust Valves May Be Open in Operational Condition 1,2 & 3 from 90 H Per 365 Days to 135 H Per 365 Days & Deleting Expired Footnotes for Clarity ML20081E2491995-03-0909 March 1995 Proposed Tech Specs,Revising SR 4.6.1.2.a,allowing Second Primary Containment ILRT (Type a) to Be Performed at Refueling Outage 5 or 72 Months After First Type a Test ML17059B0221995-02-15015 February 1995 Rev 0 to UT-NMP-311V0, Procedure for Manual Ultrasonic Exam of Nozzles Inner Radius & Bore. ML17059B0211995-02-10010 February 1995 Rev 0 to UT-NMP-309V0, Procedure for Manual Ultrasonic Exam of Planar Flaw Sizing for Nozzle Inner Radius & Bore Regions. ML17059B0201995-02-10010 February 1995 Rev 0 to UT-NMP-703V0, Procedure for Geris 2000 Ultrasonic Exam of RPV Nozzle Inner Radius & Bore Regions. ML17059A8881995-01-18018 January 1995 Rev 0 to Field Disposition Instruction 0245-90800, Shroud. ML20077N1591995-01-0606 January 1995 Proposed Tech Specs Re Min Gallons of Fuel Oil Required in Day Tanks & Storage Tanks ML20077N2071995-01-0606 January 1995 Proposed Tech Specs Re Deletion of Certain Instruments Not Classified as Category 1 ML20078Q9241994-12-13013 December 1994 Proposed Tech Specs Re Change to Table 3.6.1.2-1 That Will Allow Maximum Leakage of 24.0 Scfh for Each of Eight MSIVs ML20077E1561994-12-0202 December 1994 Proposed TS Page 3/4 1-20,reflecting Rev of SLCS Relief Valve Setpoint to Show Influence of Back Pressure & Rev of Bases Page B3/4 5-2 to Show That Hpsc Sys Designed to Supply 517 Gpm Flow Rate at 1,200 (Instead of 1,175) Psid ML20078J3781994-11-14014 November 1994 Proposed Tech Specs Reducing Leak Rate Test Pressure for Safety Related ADS Nitrogen Receiving Tanks from 385 Psig to 365 Psig ML17059A5661994-11-0909 November 1994 Rev 2 to Emergency Plan Maint Procedure EPMP-EPP-08, Maint, Testing & Operation of Oswego County Prompt Notification Sys. ML20078E0331994-10-28028 October 1994 Proposed Tech Specs 1.0, Definitions, 3/4.3.2, Isolation Actuation Instrumentation & 3/4.9.3, Control Rod Position ML20078B9841994-10-21021 October 1994 Proposed Tech Specs SR 4.8.1.1.2.e.8,reflecting Addition of Footnote Re 24 H Functional Test of DGs ML20073L8781994-10-0505 October 1994 Proposed TS Table 3.3.7.1-1 Re Radiation Monitoring Instrumentation ML20072U3491994-09-0202 September 1994 Proposed Tech Specs Re 18 Month Operability Test of Svc Water Pumps Sys & Resistance Test of Intake Deicing Heater Sys ML17059A4471994-09-0101 September 1994 Proposed Tech Specs Section 3.2.2, Minimum Reactor Vessel Temperature for Pressurization, & Associated Bases ML20072P6211994-08-26026 August 1994 Proposed TS 3/4.6.1.3, Primary Containment Air Locks, Allowing Continued Plant Operation If Interlock Becomes Inoperable as Long as Operable Door Locked Shut & Periodically Checked as Being Locked Shut ML17059A4241994-07-0606 July 1994 Rev 14 to Nine Mile Point Nuclear Station Unit 1 Odcm. ML20071G2771994-07-0101 July 1994 Proposed Tech Specs Surveillance Requirements 4.6.5.1.c.1 & 4.6.5.1.c.2 ML20029D4001994-04-27027 April 1994 Proposed Tech Specs Re Drawdown Time Testing & Inleakage Testing for Secondary Containment Integrity ML18040A2941993-12-17017 December 1993 Rev 13 to Nine Mile Point Nuclear Station Unit 1 Odcm. ML20058N3491993-12-14014 December 1993 Proposed Tech Specs 3/4.8.2, DC Sources, 3/4.8.4, Electrical Equipment Protective Devices & Bases for 3/4.6.3, Primary Containment Isolation Valves ML17059A0971993-10-25025 October 1993 Rev 4 to NMP2-IST-001,NMP,Nine Mile Point Nuclear Station, Unit 2,Pump & Valve First Ten-Yr Inservice Testing Program Plan. ML20056G9391993-09-0202 September 1993 Proposed Tech Specs Section 3/4.1.3.5, CR Scram Accumulators 1999-09-30 Category:TEST/INSPECTION/OPERATING PROCEDURES MONTHYEARML18041A0731999-07-27027 July 1999
[Table view]Rev 1 to NMP2-ISI-006, Second Ten Year Interval Inservice Insp Program Plan for Nine Mile Point Nuclear Power Station Unit 2. ML17059B2911996-09-0404 September 1996 NMP Nine Mile Point Nuclear Station Unit 2,Pump & Valve First Ten-Yr Inservice Testing Program Plan. ML17059B0221995-02-15015 February 1995 Rev 0 to UT-NMP-311V0, Procedure for Manual Ultrasonic Exam of Nozzles Inner Radius & Bore. ML17059B0201995-02-10010 February 1995 Rev 0 to UT-NMP-703V0, Procedure for Geris 2000 Ultrasonic Exam of RPV Nozzle Inner Radius & Bore Regions. ML17059B0211995-02-10010 February 1995 Rev 0 to UT-NMP-309V0, Procedure for Manual Ultrasonic Exam of Planar Flaw Sizing for Nozzle Inner Radius & Bore Regions. ML17059A8881995-01-18018 January 1995 Rev 0 to Field Disposition Instruction 0245-90800, Shroud. ML17059A5661994-11-0909 November 1994 Rev 2 to Emergency Plan Maint Procedure EPMP-EPP-08, Maint, Testing & Operation of Oswego County Prompt Notification Sys. ML17059A4241994-07-0606 July 1994 Rev 14 to Nine Mile Point Nuclear Station Unit 1 Odcm. ML18040A2941993-12-17017 December 1993 Rev 13 to Nine Mile Point Nuclear Station Unit 1 Odcm. ML17059A0971993-10-25025 October 1993 Rev 4 to NMP2-IST-001,NMP,Nine Mile Point Nuclear Station, Unit 2,Pump & Valve First Ten-Yr Inservice Testing Program Plan. ML20056G6691993-02-25025 February 1993 Rev 8 to Odcm ML17056C2971992-06-30030 June 1992 NMPNS - Unit 2 Odcm. ML17056B9841992-06-26026 June 1992 Rev 9 to Nine Mile Point Nuclear Station Unit 1 Odcm. ML18038A4851991-10-0101 October 1991 Rev 3 to First 10-Yr ISI Program Plan. W/910930 Ltr ML17058A9561991-05-0202 May 1991 Rev 5 to Administrative Procedure AP-3.7.1, Unit 2 Radwaste Process Control Program. ML18038A3531991-05-0101 May 1991 Rev 3 to NMP2-IST-001, Niagara Mohawk Power Corp,Nine Mile Point Nuclear Station Unit 2 - Pump & Valve First Ten Year Inservice Testing Program Plan. W/910501 Ltr ML20070U3621991-04-0101 April 1991 Cover Page to Rev 1 to Issue 2 to Nuclear Security Training & Qualification Plan ML17058A9541991-03-0606 March 1991 Rev 4 to Administrative Procedure AP-3.7.1, Unit 2 Radwaste Process Control Program. ML18038A3271990-06-30030 June 1990 Rev 3 to Nine Mile Point Requalification Program Action Plan. ML17056B9831990-06-15015 June 1990 Rev 8 to Nine Mile Point Nuclear Station Unit 1 Odcm. ML17056A9671990-04-0303 April 1990 Rev 8 to Odcm. ML18038A3241990-02-28028 February 1990 Rev 5 to Odcm. ML17056A9661990-02-27027 February 1990 Rev 7 to Odcm. ML18038A2921989-09-12012 September 1989 Rev 3 to Administrative Procedure AP-3.7.1, Unit 2 Radwaste Process Control Program. ML17055E5581989-03-0202 March 1989 Rev 1 to Restart Action Plan. ML19325C1741989-02-14014 February 1989 Rev 1 to AP-3.7.1, Process Control Program. ML17055E4771989-01-16016 January 1989 Second 10-Yr Interval Inservice Testing Program. ML18038A4231988-05-31031 May 1988 Rev 6 to Offsite Dose Calculation Manual. W/Two Oversize Figures ML17056A9651988-02-23023 February 1988 Rev 6 to Odcm. ML20059F8751988-02-0505 February 1988 Rev 4 to Odcm ML20236G8161987-07-31031 July 1987 Revised Preservice Insp Plan for Nuclear Piping Sys & Reactor Pressure Vessel ML20236G8111987-07-31031 July 1987 Revised Preservice Insp Plan for Nuclear Piping Sys & Component Supports ML18038A2721987-05-21021 May 1987 Rev 3 to Offsite Dose Calculation Manual. ML18038A2491987-04-13013 April 1987 Revised Emergency Procedures,Consisting of Rev 5 to Emergency Action Procedure EAP-1, Activation & Direction of Emergency Plan, & Rev 9 to Emergency Plan Implementing Procedure EPP-20, Emergency Notification. W/870413 Ltr ML20205S2311987-03-31031 March 1987 Rev 0 to Pump & Valve Inservice Testing Program ML18038A4221987-02-27027 February 1987 Rev 4 to Offsite Dose Calculation Manual. W/Two Oversize Figures ML20211P4501986-12-13013 December 1986 Rev 0 to Preoperational Test Procedure N2-POT-1-2, Msivs ML17055D1821986-08-19019 August 1986 Rev 0 to Administrative Procedure AP-3.7.1, Process Control Program. ML18038A1671986-05-31031 May 1986 Rev 1 to Offsite Dose Calculation Manual. W/One Oversize Encl ML17055B5331986-04-11011 April 1986 Rev 1 to Technical Dept Procedure TDP-5, Administration of Operational Engineering Assessment Items. ML17055B5431986-04-0101 April 1986 Rev 0 to Maint Instruction Procedure S-MI-GEN-002, Maint Instructions for Writing Procedures. ML17055B5301986-03-20020 March 1986 Rev 0 to Site Administrative Procedure AP-6.1, Procedure for Mod & Addition. ML17055B5441986-03-14014 March 1986 Rev 1 to Nuclear Training Procedure NTP-11, Licensed Operator Retraining. ML17055B5421986-03-14014 March 1986 Rev 1 to Nuclear Training Procedure NTP-10, Training of Licensed Operator Candidates. ML17055B5171986-03-10010 March 1986 Rev 4 to Administrative Procedure AP-2.0, Production & Control of Procedures. ML17055B5411986-03-10010 March 1986 Rev 3 to Vol IV to SWEC Pp 94, Review of Changes & Effect on Environ/Mechanical/Seismic/Hydrodynamic Qualification of Equipment. ML17055B5461986-03-0202 March 1986 Rev 2 to Maint Instruction Procedure MI-4.0, Maint Instructions for Review & Implementation of Technical Requirements in Maint Procedures. ML17055B5251986-03-0101 March 1986 Draft Rev 4 to Administrative Procedure AP-4.0, Administration of Operations. ML17055B5381986-02-28028 February 1986 Rev 0 to Technical Dept Procedure TDP-8, Post-Maint Testing Criteria. ML20140D3341986-02-28028 February 1986 Rev 2 to Offsite Dose Calculation Manual. W/Two Oversize Maps 1999-07-27 |
Text
Ago Avaiiablo Ou
>5peetare Card SUBMIT PLAN TO NRC I
PREPARE DCRDR SPEC.
SELECT HFE CONSULTANT NRC REVIEW OF PLAN 6/30/84 START REVIEW DCRDR TEAM ORIENTATION I
OPERATING EXPERIENCE REVIEW PERSONNEL AVAILABLE FOR QUESTIONNAIRE 6 INTERVIEWS I INVENTORY 9/1 SURVEY IO/1 I CONTROL ROOM 6 PANELS AVAILABLE TASK ANALYSIS VALIDATION Tl (DRAFT) EMERGENCY (WALK THROUGHS)
'APPRTURE VERIFICATION OPERATING PROCEDURES (EOPs) AVAILABLE I CARB 1/I /85 I/15 OPERATING CREW AVAILABLE ASSESSMENT G IMPROVEMENT I
SUBMIT FINAL REPORT TO NRC PREPARE FINAL REPORT 2/I 3/21 f LOAD NRC REVIEW FUEL OF FINAL REPORT 4/21 10/21 LEGEND: FIGURE 1-1 Ql HFE CONSULTANT SUBMIT TASK COMPLETION REPORT ACTIVITY SCHEDULE DETAILED CONTROL ROOM DESIGN REVIEW TIME INTERVALS IN WEEKS (DATES TENTATIVE) NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT -UNIT 2
j J
'E I
I
\
0>>
Retrieved from "https://kanterella.com/w/index.php?title=ML18037A015&oldid=1953036"