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Category:TECHNICAL SPECIFICATIONS
MONTHYEARML20210G9261999-07-20020 July 1999
Proposed Tech Spec 3.2.1.i,revising Senior Reactor License Requirement for Operations Manager
ML20057E2241993-09-29029 September 1993
Proposed Tech Specs,Revising Frequency of Radioactive Effluent Release Rept from Semiannual to Annual
ML20057E2601993-09-29029 September 1993
Proposed Tech Specs,Clarifying Administrative Controls of High Radiation Area Keys
ML20056A7201990-07-27027 July 1990
Proposed Tech Spec Page 3.10-9
ML20043J0011990-06-21021 June 1990
Proposed Tech Specs Changes Re Removal of cycle-specific Parameter Limits,Per Generic Ltr 88-16
ML20245F8441989-07-25025 July 1989
Proposed License Conditions D & H,Reflecting Changes,Per Rev 10 to Physical Security Plan
ML20195H6361988-06-30030 June 1988
Proposed Tech Specs,Deleting Figures 3.1 & 3.2 from Unit 1 Tech Specs & Figures 6.2.1 & 6.2.2 from Unit 2 Tech Specs Per Guidance of Generic Ltr 88-06
ML20151P1361988-04-15015 April 1988
Proposed Tech Specs Figures 3.1,3.2,6.2.1 & 6.2.2 Reflecting Administrative Changes to Organization Charts
ML20236G4901987-07-27027 July 1987
Proposed Tech Specs,Deleting Section 3.2.6 & Adding Sections 4.1.7 & 4.1.8 Re Radiation Protection Requirements. Supporting Documentation Encl
ML20215A0801986-11-26026 November 1986
Proposed Tech Specs,Incorporating Changes in Facility Organization Structure & Title Changes for Members of Station Nuclear Safety Committee
ML20203P0201986-04-30030 April 1986
Proposed Tech Specs,Incorporating Anticipatory Reactor Trip on Turbine Trip
ML20141G7941985-12-19019 December 1985
Proposed Tech Specs,Ensuring Requirements for Radiation Protection Program Uniform for Units 1 & 2
ML20127E6481985-06-30030 June 1985
Proposed Tech Specs Incorporating Administrative Changes to Facility Organization & Limiting Unit 2 Overtime for Critical Shift Job Positions
ML19323B8671980-05-0505 May 1980
Proposed Tech Spec Change to Section 4.13 Re Containment Vent & Purge Sys & 3.8 for Refueling,Fuel Handling & Storage.Safety Evaluation Encl
ML19211C7551980-01-0404 January 1980
Proposed Changes to Tech Specs Section 3.4 Requiring Operability of All Three Auxiliary Feedwater Pumps During Power Operations.Util Safety Evaluation Encl
ML19209B5941979-10-0202 October 1979
Proposed Tech Spec Changes to License DPR-64,consisting of Changes to Mgt Organization Charts & Position Titles.Safety Evaluation Encl
ML19305A7351979-09-28028 September 1979
Proposed Page 44 to ETS Re Mgt Titles
ML1002605911979-09-28028 September 1979
Proposed Pages 247,251-253 & 259 to Tech Specs Re Mgt Titles
ML19259A5991979-01-0303 January 1979
Tech Specs Page Revisions to License DPR-26 Re Accumulator Water Volume & New Limit for Total Nuclear Peaking Factor. W/Encl Safety Evaluation
1999-07-20
[Table view]
Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML20210G9261999-07-20020 July 1999
Proposed Tech Spec 3.2.1.i,revising Senior Reactor License Requirement for Operations Manager
ML20211H6141999-01-17017 January 1999
Rev 8 to Security Force Training & Qualification Plan, for Indian Point 3 Nuclear Power Plant
ML20248L9891998-05-18018 May 1998
Rev 7 to, Security Force Training & Qualification Plan
ML20057E2241993-09-29029 September 1993
Proposed Tech Specs,Revising Frequency of Radioactive Effluent Release Rept from Semiannual to Annual
ML20057E2601993-09-29029 September 1993
Proposed Tech Specs,Clarifying Administrative Controls of High Radiation Area Keys
ML20056A7201990-07-27027 July 1990
Proposed Tech Spec Page 3.10-9
ML20043J0011990-06-21021 June 1990
Proposed Tech Specs Changes Re Removal of cycle-specific Parameter Limits,Per Generic Ltr 88-16
ML20248B2831989-09-0808 September 1989
Cycle 7 Startup Physics Test Rept,Indian Point Unit 3
ML20245F8441989-07-25025 July 1989
Proposed License Conditions D & H,Reflecting Changes,Per Rev 10 to Physical Security Plan
ML20195H6361988-06-30030 June 1988
Proposed Tech Specs,Deleting Figures 3.1 & 3.2 from Unit 1 Tech Specs & Figures 6.2.1 & 6.2.2 from Unit 2 Tech Specs Per Guidance of Generic Ltr 88-06
ML20246H9871988-04-30030 April 1988
Environ Qualification of Continental Wire & Cable Corp Instrumentation Cable Installed in Beaver Valley Power Station Unit 1
ML20151P1361988-04-15015 April 1988
Proposed Tech Specs Figures 3.1,3.2,6.2.1 & 6.2.2 Reflecting Administrative Changes to Organization Charts
ML20236G4901987-07-27027 July 1987
Proposed Tech Specs,Deleting Section 3.2.6 & Adding Sections 4.1.7 & 4.1.8 Re Radiation Protection Requirements. Supporting Documentation Encl
ML20207S2841987-03-13013 March 1987
Revised Emergency Plan Implementing Procedures,Including Rev 3 to IP-1028, Core Damage Assessment, Rev 6 to IP-1041, Personnel Monitoring for Eof,Tsc.Osc & Control Room Personnel & Rev 12 to IP-1050, Accountability
ML20207H1861986-12-23023 December 1986
Revised Emergency Plan Implementing Procedures,Including Rev 14 to IP-1021, Radiological Medical Emergency & Rev 4 to IP-1056, Directing Fire Fighting Personnel in Controlled Area
ML20215A0801986-11-26026 November 1986
Proposed Tech Specs,Incorporating Changes in Facility Organization Structure & Title Changes for Members of Station Nuclear Safety Committee
ML20210P5201986-09-22022 September 1986
Revised Emergency Plan Implementing Procedure IP-1050, Accountability
ML20203P0201986-04-30030 April 1986
Proposed Tech Specs,Incorporating Anticipatory Reactor Trip on Turbine Trip
ML20149D4851986-03-0505 March 1986
Rev 3 to Offsite Dose Calculation Manual
ML20205K3381986-02-20020 February 1986
Rev 15 to Book II of Emergency Plan Procedures,Including Table of Contents & Rev 4 to IP-1017 Re Recommendation of Protective Actions for Offsite Population
ML20141G7941985-12-19019 December 1985
Proposed Tech Specs,Ensuring Requirements for Radiation Protection Program Uniform for Units 1 & 2
ML20127E6481985-06-30030 June 1985
Proposed Tech Specs Incorporating Administrative Changes to Facility Organization & Limiting Unit 2 Overtime for Critical Shift Job Positions
ML20129F1611985-05-28028 May 1985
Public Version of Revised Emergency Plan Procedures, Including Rev 12 to Procedure IP-1030, Emergency Notification,Communication & Staffing & Rev 0 to Procedure IP-1052, Hazardous Waste Emergency
ML20127G3051985-03-25025 March 1985
Annual Drill Scenario
ML20100K2181985-03-20020 March 1985
Revised Emergency Plan Implementing Procedures,Including Rev 6 to IP-1001 Re Determining Magnitude of Release,Rev 5 to IP-1003 Re Obtaining Meterological Data & Rev 4 to IP-1004 Re Midas Computer Sys
ML20084N2411984-05-16016 May 1984
Rev 0 to Drill Scenario 4B
ML20083J7031983-12-12012 December 1983
Public Version of Revised Emergency Plan Implementing Procedures IP-1002 Re Determination of Release Magnitude, IP-1011 Re Offsite Monitoring & IP-1028 Re Core Damage Assessment
ML20081L9781983-10-28028 October 1983
Public Version of Revised Emergency Plan Implementing Procedures,Including Procedures IP-1011 Re Offsite monitoring,IP-1021 Re Radiological Medical Emergency & IP-1047 Re Operations Support Ctr
ML20080D2951983-08-0404 August 1983
Public Version of Revised Emergency Plan Implementing Procedures,Including Procedures IP-1010 Re in-plant/site Perimeter Surveys & IP-1025 Re Repair & Corrective Action Teams
ML20077H5771983-07-15015 July 1983
Public Version of Page 11 to Emergency Plan Procedure IP-1030, Emergency Notification & Communication Staffing & Rev 8 to Procedure IP-1070, Periodic Check of Emergency Preparedness Equipment
ML20072K8441983-05-27027 May 1983
Public Version of Revised Emergency Plan Implementing Procedures,Including Procedures IP-1002 Re Determination of Magnitude of release,IP-1011 Re Offsite Monitoring & IP-1047 Re Operations Support Ctr
ML20074A5031983-05-0202 May 1983
Rev 2 to Procedure SOP-SG-2, Secondary Plant Chemistry Control
ML20070L9291982-12-27027 December 1982
Public Version of Revised Emergency Plan Implementing Procedures,Including Procedures IP-1021 Re Radiological Medical Emergency & IP-1030 Re Emergency Notification, Communication & Staffing
ML20065U3581982-10-0505 October 1982
Public Version of Revised Emergency Plan Implementing Procedures,Including Procedures IP-1010 Re in-plant/onsite Perimeter Surveys & IP-1030 Re Emergency Notification, Communication & Staffing
ML20062K6851982-07-29029 July 1982
Public Version of Revised Emergency Plan Implementing Procedures,Including Procedures IP-1003 Re Obtaining Meteorological Data & 1004 Re Midas Computer Sys - Dose Assessment Models.Revision 13 to Index Encl
ML20050D4901982-03-16016 March 1982
Public Version of Revised Emergency Plan Procedures, Consisting of Revision 4 to Procedures Book II Re Initiating Conditions & Revision 3 to Procedure IP-1058 Re Earthquake Emergency.Revised Index Encl
ML1002718321982-02-0404 February 1982
Investigation of Relative Deterioration Temps & Hydrogen Chloride Evolution of Chlorinated Jacket Compounds by Means of Thermal Gravimetric Analysis & Differential Thermal Analysis.
ML20040F9131982-01-22022 January 1982
Public Version of Revised Emergency Plan Implementing Procedures,Including Page Changes to Procedures IP-1017, IP-1040 & IP-1056 & Table of Initiating Conditions & Emergency Action Levels
ML20040E0551982-01-18018 January 1982
Public Version of Revised Emergency Plan Implementing Procedures,Including Procedures IP-1003 Re Obtaining Meteorological Data & IP-1011 Re Offsite Monitoring Team.One Oversize Drawing Encl.Aperture Card Available in PDR
ML1002718231981-07-0707 July 1981
Analysis & Rept on Safety-Related Electrical Penetrations for Indian Point Plant 3.
ML1002718291981-06-0202 June 1981
LOCA Testing of Low Voltage Conductor Seal.
ML1002718211981-04-16016 April 1981
Ozone Resisting Silicone Rubber Cable Tests for Con Ed.
ML19347D4451981-03-31031 March 1981
Steam Generator Insp Program & Results,1980/1981 Refueling & Maint Outage.
ML19323B8671980-05-0505 May 1980
Proposed Tech Spec Change to Section 4.13 Re Containment Vent & Purge Sys & 3.8 for Refueling,Fuel Handling & Storage.Safety Evaluation Encl
ML19211C7551980-01-0404 January 1980
Proposed Changes to Tech Specs Section 3.4 Requiring Operability of All Three Auxiliary Feedwater Pumps During Power Operations.Util Safety Evaluation Encl
ML19209B5941979-10-0202 October 1979
Proposed Tech Spec Changes to License DPR-64,consisting of Changes to Mgt Organization Charts & Position Titles.Safety Evaluation Encl
ML19305A7351979-09-28028 September 1979
Proposed Page 44 to ETS Re Mgt Titles
ML1002605911979-09-28028 September 1979
Proposed Pages 247,251-253 & 259 to Tech Specs Re Mgt Titles
ML19269D1921979-02-28028 February 1979
Inservice Testing & Insp Program, Suppl 3
ML19259A5991979-01-0303 January 1979
Tech Specs Page Revisions to License DPR-26 Re Accumulator Water Volume & New Limit for Total Nuclear Peaking Factor. W/Encl Safety Evaluation
1999-07-20
[Table view] |
Text
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ATTACHMENT I DROPOSED TECHNICAL SPECIFICATIONS CHANGE RELATED TO AUXILIARY FEEDWATER SYSTEM (APPENDIX A)
POWER AUTHORITY OF THE STATE OF NEW YORK INDIAN POINT 3 NUCLEAR POWER PLANT DOCKET NO. 50-286 JANUARY 4, 1980 1742 209 8001140 /3
i 3.4 STEAM AND POWER CONVERSION SYSTEM Applicability Applies to the operating status of the Steam and Power Conversion System.
Obiective To define conditions of the turbine cycle steam-relieving capacity.
Auxiliary Feedwater System operation is necessary to ensure the capability to remove decay heat from the core.
Specification A. The reactor shall not be heated above 350*F unless the following conditions are met:
(1) A minimum ASME Code approved steam-relieving capability of h twenty (20) main steam valves shall be operable (except for testing).
(2) Three out of three auxiliary feedwater pumps must be operable.
(3) A minimum of 360,000 gallons of water in the condensate storage tank.
(4) System piping and valves directly associated with the above components operable.
(5) The main steam stop valves are operable and capable of closing in five seconds or less.
(6) Two steam generators capable of performing their heat transfer function.
I742 210 (7) City water system piping and valves directly associated with providing backup supply to the auxiliary feedwater pumps are operable.
Amendment No.
3.4-1
, B. If during power operations any of the conditions of 3.4.A above, except Item (2), cannot be met within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />, the operator shall start to shut-down and cool the reactor below 350 0F using normal operating procedures.
For Item (2) the operator shall shutdown (Ke r <0.99) and cool the reactor below 350 0F within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> if:
(a) only 2 out of 3 pumps are operable and the third pump is not restored to operable status within 7 days, or (b) only 1 out of 3 pumps is operable and a second pump is not restored to operable status within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />.
C. The gross turbine-generator electrical output at all times shall be within the limitations of Figure 3.4-1 or Figure 3.4-2 for the applicable condi-tions of turbine overspeed setpoint, number of operable low pressure steam dump lines, and condenser backpressure as noted thereon.
Basis A reactor shutdown from power requires removal of core decay heat. Immediate decay heat removal requirements are normally satisfied by the steam bypass to the condensers. Thereafter, core decay heat can be continuously dissipated via the steam bypass to the condenser as feedwater in the steam generator is converted to steam by heat absorption. Normally, the capability to feed the steam generators is provided by operation of the turbine cycle feedwater system.
The twenty main steam safety valves have a total combined rated capability of 15,108,000 lbs/hr. The total full power steam flow is 12,974,500 lbs/hr, therefore twenty (20) main steam safety valves will be able to relieve the total steam flow if necessary.
1742 211 Amendment No. 3.4-2 MS
In the unlikely event of complete loss of electrical power to the station, decay aeat removal would continue to be assured by the availability of either the steam-driven auxiliary feedwater pump or one of the two motor-driven auxiliary steam generator feedwater pumps,.and steam discharge to the atmosphere via the main steam safety valves and atmospheric relief valves, one motor-driven auxiliary feedwater pump can supply sufficient feedwater for removal of decay heat from the plant. The minimum amount of water in the condensate storage tank is the amount needed for 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> at hot shutdown. When the condensate storage supply is exhausted, city water will be used.
Two steam generators capable of performing their heat transfer function will provide sufficient heat removal capability to remove core decay heat after a reactor shutdown.
The limitations placed on turbine generator electrical output due to conditions of turbine overspeed setpoint, number of operable steam dump lines, and condenser back pressure are established to assure that turbine overspeed (during conditions of loss of plant load) will be within the design overspeed value considered in the turbine missile analysis, in the preparation of Figures 3.4-1 and 3.4-2, the specified number of operable L.P. steam dump lines is shown as one (1) greater than the minimum number required to act during a plant trip.
The limitations on electrical output, as indicated in Figures 3.4-1 and 3.4-2, thus consider the required performance of the L.P. Steam Dump System in the event of a single failure for any given number of operable dump lines.
1742 212 Amendment No. 3.4-3
ATTACHMENT II SAFETY EVALUATION RELATED TO AUXILIARY FEEDWATER SYSTEM 1742 213 POWER AUTHORITY OF THE STATE OF NEW YORK INDIAN POINT 3 NUCLEAR POWER PLANT DOCKET NO. 50-286 JANUARY 4, 1980
',Section I - Description of Modification The operating limitation for the Steam and Power Conversion System
. is being changed to require that all three auxiliary feedwater (AFW) pumps be operable during power operations and that the operator shall shutdown (Keff <0.99) and cool the reactor below 3500 F within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> if: (a) only 2 out of 3 pumps are operable and the third pump is not restored to operable status within 7 days,or (b) only 1 out of 3 pumps is operable and a second pump is not restored to operable status within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />. (Presently only two out of three AFW pumps are required to be operable during power operations and if this condition is not met, 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> are allowed before shutdown to 3500 F is started).
Section II - Purpose of Modification The purpose of this modification is to increase the predicted AFWS reliability by eliminating the possibility that one train will be out of service indefinitely.
Section III - Impact of the Change The requirement of having all three AFWS pumps operable during power operations will not alter the conclusion reached in the FSAR and SER accident analysis.
Section IV - Implementation of the Modification The modification as proposed will not impact the ALARA or Fire Protection Program at IP3.
Section V - Conclusion The incorporation of this modification: a) will not increase the probability nor the consequences of an accident or mal-function of equipment important to safety as previously evalu-ated in the Safety Analysis Report; b) will not increase the possibility for an accident or malfunction of a different type than any evaluated previously in the Safety Analysis Report; and c) will not reduce the margin of safety as defined in the basis for any Technical Specification.
Section VI - References (a) IP3 FSAR (b) IP3 SER I74,2 2l4
