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Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML17059C7911999-09-30030 September 1999
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
[Table view]
Category:TEST/INSPECTION/OPERATING PROCEDURES
MONTHYEARML18041A0731999-07-27027 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.
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
[Table view] |
Text
Enclosure 812 NINE MILE POINT NUCLEAR STATION TECHNICAL DEPARTMENT PROCEDURE PROCEDURE NO. TDP-6 NUCLEAR PLANT RELIABILITY DATA SYSTEM (NPRDS) FAILURE REPORTING DATE AND INITIALS APPROVALS SIGNATURES NPRDS Coordinator E. S. Tomlinson Supervisor-Reactor Re G. Smith Super Qnt echnical Services J. R. 'I'ere II ~ /~l Summar of Pa es Revision 1 (Effective 12/9/85 )
PAGES DATE 1-3 December 1985 NIAGARA MOHAWK POWER CORPORATION THIS PROCEDURE NOT TO BE USED AFTER DECKER 1989 SUBJECT TO PERIODIC REVIEW.
8b04280~ 8b04i5 84+"'050004ip PDR ADOCH" PDR P
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PDP-6 NUCLEAR PLANT RELIABILITY DATA SYSTEM (NPRDS) FAILURE REPORTING 1.0 PURPOSE This procedure outline's the steps necessary to ensure that all reportable equipment failures are identified and processed in accordance with the INPO NPRDS Reporting Procedures Manual.
2 ' REFERENCES OI-21 "Work Tracking System" NPRDS Reporting Procedures Manual Rev. 10 AP.5.0 3.0 RESPONSIBILITIES 3.1 Planning Clerk - The unit planning clerk will be responsible for ensuring that the NPRDS Coordinat'or receives all Work Requests (WR's) for review.
3 ~2 Unit Supervisor Reactor Analyst The Unit Supervisor will assign a technician to functionally report to the NPRDS Coordinator on a weekly basis.
3.3 General Office Clerk - The general office clerk will supply the NPRDS Coordinator with all operation department occurrence reports (OR's).
3.4 Reactor Analyst Technician << The technician will screen all WR's in accordance with INPO's NPRDS Reporting Procedures Manual. The technician will also review Occurrence Reports and the monthly operating reports to confirm that all reportable failures were found. The technician will also support the NPRDS Coordinator in his efforts by performing various assigned duties.
3.5 NPRDS Coordinator - The NPRDS Coordinator is responsible for maintaining the NPRDS failure reporting system such that failures are reported in a complete and timely manner. The coordinator shall supervise and assign the designated technician's work on a daily basis. The coordinator will review 'and sign all failure reports. As a check the coordinator will review the monthly operating report and
,LER's and confirm that all applicable failures were reported.
3 ' Document Control Clerk - The document control clerk will be responsible for entering the failure data into the INPO computer data base.
TDP-6 -1 December 1985
4.0 Procedure 4.1 The technician receives the WR's and Occurrence Reports from the NPRDS Coordinator.
4.2 Work requests shall be screened to identify reportable failures.
4.2.1 WR's shall first be sorted by system. If the component is it not part of one of the systems listed on attachment 81 is not reportable.
4.2.2 The remaining WR's shall be reviewed in accordance with guidelines given in the Reporting Procedures Manual. A listing of components in the current data base is available for reference. It should be noted that a component may be reportable upon failure and not listed in the base. All questions regarding a failure's reportability shall be directed to the NPRDS coordinator.
4.3 All WR's which are not reportable failures are stamped NOT APPLICABLE and initialled as reviewed.
4 ~4 The technician then fills out a failure report for each applicable failure and marks the box on the WR labeled NPRD with the appropriate NPRDS system code and his initials.
He shall also attach a photocopy of the WR to the failure report. The technician should consult with the NPRDS Coordinator for any questionable concerns.
4.5 The completed WR's shall be returned to the planning clerk in the same numerical order in which they were received.
4.6 The technician shall submit the completed failure reports to the NPRDS coordinator for review and approval.
4.7 After approval the reports are entered into the INPO data base by the document control clerk.
4.8 To verify complete reporting the technician will review the Occurrence Reports and Monthly Operating Reports.
4.9 As a check the NPRDS coordinator will review LER's and the Monthly Operating Reports.
TDP"6 -2 December 1985
Attachment 81 Reactor Vessel Reactor Recirculation Reactor Instrumentation Main Steam Shutdown Cooling Containment Spray Core Spray Emergency Condenser Feedwater - HPCI Condensate - Condensate Storage and Transfer Liquid Poison Control Rod Drive Drywell Coolers
,Service Water, Diesel Generator Cooling Water, Containment Spray Raw Water Reactor Building Closed Loop Cooling Emergency Ventilation Containment Vent and Purge Isolation Valves and Control Circuits Penetrations - Hatches Torus Monitoring and Vacuum Relief Main Steam Line Rad Monitors and Ventilation Rad Monitors Diesel Generator and Auxiliaries Electrical Distribution (All circuit breakers)
MG Sets - RPS Buses DC Power RPS Instrumentation neutron Monitoring TDP-6 -3 December 1985
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