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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] |
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TECHNICAL REVIEW AND COAAROL
'""EVALUATION OF NEED FOR SAFETY ANALYSIS Qf ACCORDANCE WITH 10 CFR 50.59 (Documents that require General Supt. approval per Tech Spec 6.8)
FOR DOOONENT NO. P CCrtrt cc. REF.~ DAZE W DF C The Author (A) and four SORC Members (Minimum 2 regular members, 2 alternates) are to respond to each of the questions belo~.
NO YES+
Does the document/revision result in a change to the facility A lF 0 or procedures described in the FSAR?++ 1 0 0 2 0 0 3 0 0 4, 0 0 Does the document/revision deviate from compliance to Tech
'- Specs, or is the margin of safety defined in the basis A W o 1 0 0 reduced? P 2 3 0 0 4 0 0 Does the document/revision increase the probability of A O occurrence, or the consequences of an accident, or malfunction 1 0 0 of equipment important to safety (Class 1) evaluated in the 2 0 0 FSAR increased? 3 0 0 4 0 O Does the document/revision create the possibility for an A 0 accident or malfunction of a different type than any evaluated 1 0 0 in the FSAR? 2 3 0 0
""" """+A""MAYBE" 4 0 0 lcoastitutes a "YES". response.
Recoamend Nuclear Engineering or Tech Services perform a safety LYSIS ta present to SORC (noted by a 'YES" 2 4 response:to any of the: above questions).
1 0 0 0,0 3
Recomaend of need full SORC ccmmittee review for Safety Analysis.
this Evaluation 1 0
2 0 0 3,40 approval - This not involve L//2 //
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REFERENCE azvizv DOCUMENTS ann con Tao'.
The items entered below have been included in the preparation and/or review of the attached reference document aad are presented in place of a specific check sheet for the document..
MAME The followiag persons were consulted about this procedure
~c Tl Procedure is in compliance with the folfo<<ing Technical Specifications
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BY Compliance with: ASME Bolter and is consistent with the following Station Pressure Vessel Code(s) or Site procedures:
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