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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 O'll NINE MILE POINT NUCLEAR STATION TECHNICAL DEPARTMENT PROCEDURE PROCEDURE NO ~ TDP-5 ADMINISTRATION OP OPERATIONAL ENGINEERING ASSESSMENT ITEMS DATE AND INITIALS APPROVALS SIGNATURES REVISION 0 REVISION l REVISION 2 Technical Support S e visor R. G. Randall Superintendent, 5
Technical Services J. R. Spadafore zz. P'-&C.
Technical Superintendent W. C. Drews C.
Summar of Pa es Revision 1 (Effective
~Pa ea Date 1-4 April 1986 NIAGARA MOHAWK POWER CORPORATION THIS PROCEDURE NOT TO BE USED AFTER SUBJECT TO PERIODIC REVIEW.
8b00280281 8b0415 PDR ADOCH, 05000410, i P PDR
TDP-5 AMINIS~TION OF OPERATIONAL ENGINEERING ASSESSMENT ITEMS 1.0 PURPOSE To provide guidance for the handling of the paper flow of Operational Engineering Assessment (OEA) items to assure complete and accurate closeout of potential operating problems.
2.0 REFERENCES
NUREG 0737, Item I.C.5 "Procedures for "
Feedback of Operating Experience to Plant Staff".
AP-3.4.2 "Administration of Technical and Safety Reviews (Operations Experience Assessment)".
Generic Letter 83-28 and NMPC Responses.
3.0 S CD PE 3.1 Operations assessment items include information on problems within the Nine Mile Point Station, such as Occurrence Reports (OR's) and License Event Reports and information from outside the station such as listed below:
NRC I & E Bulletins (Bulletins)
NRC I & E Circulars ( Circulars )
NRC I & E Notices (Notices)
GE Service Information Letters (SIL's)
GE Technical Information Letters (TIL')
GE Product Experience Reports (PER's and RICSIL's)
GE Service Advice Letters (SA's)
INPO Significant Operating Experience Reports(SOER's)
INPO Significant Event Reports (SEH.'s)
INPO Operation and Maintenance Reminders (0 & MR's)
NMPNS NPRDs Reports Miscellaneous Information Of these items, the following items are excluded from the detailed procedure portion of this procedure for the noted reasons and are handled as stated.
3.2 OR's are all forwarded to the Technical Support Supervisor, who reviews the report in detail and determines if the item should receive further OEA attention and also provides a third opinion as to the reportability to the NRC of the Occurrence Report. No documentation is required of this review because SORC reviews all OR's. If the item deserves further OEA attention, this procedure as a miscellaneous item.
it is handled per TDP-5 -1 April 1986
3.2.1 LERts are written based on OR's under the direction of the Technical Support Supervisor . The LER requires an engineering evaluation and remedial action, and documents these. Therefore, the provisions of this procedure and AP-3.4.2 are complied with in an alternative manner.
3.2.2 OSNRts are written by INPO, PER's and RICSIL's are written by GE with the intent of being informal good ideas, and are not intended to. be formal OEA items. The Technical Support Supervisor or his designee should review each 0&MR, PER and RICSIL, discard those that are not applicable to the NMPNS and forward the potentially applicable items to the appropriate department for their informal consideration. No documentation or followup is required.
3.2.3 NPRPe Reports are generated at other plants, reviewed by INPO and significant dtsns are published as SER's or SOER's. Since these are included in this procedure, no review of the INPO NPRDs Reports is required. NMPNS NPRD Reports are generated through OR's which are reviewed as indicated above.
4.0 PROCEDURE 4.1 The Technical Support Supervisor or Assistant Supervisor receives the item, reviews it, and logs it in a yearly numerical log by'tem title. (SA's, PER's and miscellaneous items are not numbered and are, therefore logged by date).
v 4.2 A priority for the item is established by the Technical Support ~
Supervisor or Assistant Supervisor. It is either:
A) Immediately assigned to an engineer, or B) Temporarily placed in an outstanding item file for subsequent assignment.
C) Routed to appropriate personnel to ascertain priority of action.
This priority is established taking into consideration the following factors:
- 1) Direct or potential applicability to the NMPNS.
- 2) Potential safety or availability impact.
- 3) Priority of other Technical Support assignments and available manpower (resources).
TDP-5 -2 April 1986
- 4. 2.1 The item is assigned to a member of the Technical Support Group or appropriate Department Head for assessment. Tools used for the determination of applicability include plant procedures, the Document Control Seek System, Storeroom Records, Department Records, Equipment Manuals, and conversations with appropriate staff members. Each SOER recommendation should be addressed individually.
4.2.2 When the item is fully addressed and can be closed out, a memo is written to the Technical Support Supervisor documenting the tools used in determining applicability and the results achieved, using Attachment A as a guide. The memo should be reviewed by the Supervisor or Assistant Supervisor prior to draft publication. The carbon copy list should include any individual referred to in the memo. A copy of each draft memo should be transmitted to the OEA Committee members in a packet prior to each OEA meeting for their review.
- 4. 2.3 When the OEA Committee accepts the disposition of the item, a notation should be made in the log of the date of the OEA Commitee meeting and the file number of the closeout memo. The memo is then reissued as final with a copy to each OEA Committee Member, NMPl Licensing, SORC Secretary, NC&V and any individual referred to in the memo. The final copy should also include a statement indicating the item was approved during the appropriate OEA meeting. One copy of the memo should then be filed by author and memo date. Another copy of the memo should be filed wth a copy of the OEA item by the Technical Support Supervisor or Assistant Supervisor by item name and number. However, the official file is not the one maintained by the Technical Support Supervisor. The official file is the one maintained by Document Control.
4.3 In-House Events which are judged to have generic implications should be transmitted to INPO via nuclear network.
4,4 SIL feedback forms shall be prepared and sent to GE. Annually, a computer sort of GE's SIL status shall be obtained and audited for each unit to ensure that all SILs are in NMPC's possession.
TDP-5 -3 April 1986
Attachment A EVALUATION REPORT FORMAT
- 1. Item Number: Record the item number under "subject".
- 2. Problem Summar : Summarize the basic problem(s)'ddressed in the operating experience report.
- 3. Evaluation: In regard to the above problem(s), discuss the following:
o applicability to the plant o potential consequences to the plant o any similar problems that have already occurred at the plant o primary lessons to be learned by the plant
- 4. Corrective Actions Taken: Indicate the corrective actions (if any) already in place. It is highly desirable that this report be written after any corrective actions necessary are completed so that this item may be closed. Item 5 below should only be used for long term or controversial recommendations.
- 5. Recommended Corrective Actions: Based on the evaluation results, recommend corrective actions necessary to resolve the problem(s) being addressed.
- 6.
References:
List pertinent references utilized in the .evaluation including organizations/individuals contacted.
- 7. Re ort Author and Date: Sign and date report.
- 8. Distribution: Indicate any individual referred to in the memo, as a Indicate standard OEA distribution plus any individual referred to in the memo, as a minimum (for final memo).
- 9. Equipment Components flagged as having potential problems are routed to licensing for inclusion on the excluded equipment list.
TDP-5 -4 April 1986
C
