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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
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PRESIDENT EXECUTIVE VICE PRESIDENT
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MANAGER ONSITE i NUCLEAR POWER .
QUAUTY ASSURANCE Figure 6.2.1 Independent Safety Review ond Audit Orgonization Amendment No.
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GENERAL MANAGER GENERAL MANAGER GENERAL MANAGER GENERAL MANAGERe NUCLEAR POWER EtMRONMENTAL TECHNICAL ADM:NISTRArrVE GENERATION HEALTH AND SAFETY SUPPORT SERVICES OPERATIONS RAO:ATION PROTECTION CH!FT Pt. ANT FAJCLEAR TRAINING MANAGER & STAFF MANAGER & STAFT ENGINEER & STAFF MANAGER & STAFF I - l --
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REACTOR CHEMISTRY SAFETY ASSESSuCNT (3)
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- ResponsitM for the performance and monitoring of the Fire Protection Prograns WMR & STAFF Responsible for the Fire Protection Program Activities (CCR) - Centrol Contree Room Positen (s) - Coatines sh.ft Coverage AMENDMENT NO.
INSTRUMENT & CONTROL Figure 6.2.2 Facility Organization s
d Attachment B Safety Assessment Consolidated Edison Company of New York, Inc.
Indian Point Units No. 1 and 2 Docket Nos. 50-03 and 50-247 April, 1988 l
l
Safety Assessment 4 Discussion:
A proposed technical specification revision is set forth in Attachment A to this application. Several changes are being initiated by Consolidated Edison to incorporate certain administrative changes to the Facility Organization. The proposed revision is reflected in Figures 3.1 and 3.2 of the Indian Point Unit No. 1 Technical Specification and Figures 6.2.1 and 6.2.2 of the Indian Point Unit No. 2 Technical Specification.
The proposed revision to Figures 3.1 and 3.2 and 6.2.1 and 6.2.2 reflect several recent Consolidated Edison technical support organization and facility organization changes.
As reflected in Figure 3.1 and Figure 6.2.1, the Director, Power Generation Services, has been promoted to the title Assistant Vice President, Power Generation Fervices, reporting directly to the Senior Vice President, Central Operations. The Senior Vice President, Central Operations, reports to an Executive Vice President, whose responsibilities, while not indicated in the Figure, have been expanded. The offsite Engineering and Construction Organizations continue to support Indian Point while reporting to the Senior Vice President, Central Operations.
As reflected in Figure 3.2 and Figure 6.2.2, changes have also been accomplished in the Nuclear Power organization at Indian Point. The Chemistry Manager and staff, formerly reporting to the General Manager, Technical Support, now report to the General Manager, Environmental Health and Safety. Additionally, the Test and Terformance group now reports to the Chief Plant Engineer who continues to report to the General Manager, Technical Support. These changes are being made with the intent of more productively providing the desired technical support of the Indian Point facility.
Basis For No Significant Hazards Consideration Determination The proposed change does not involve a significant hazards consideration because Operating of Indian Point Unit Nos. 1 and 2 in accordance with this change would nots (1) involve a significant increase in the probability or consequences of an accident previously evaluated. This is an administrative change which reflects a recent facility re-organization with consolidation and realignment of responsibilities. The reorganization has been reviewed and a conclusion reached that this change does not increase the probability or consequences of an accident.
(2) create the possibility of a new or different kind of accident from any previously analyzed. It has been determined that a new or different kind of accident will not be possible due to this change. An administrative change such as a facility re-organization does not create the possibility of a new or different kind of accident.
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(3) involve a significant reduction in a margin of safety. The administrative change as described above in the safety assessment discussicn has been determined not to impact the preservation or reduction of any margin of safety.
The Conmission has provided guidance concerning the application of the standards for determining whether a significant hazards censideration exists by providing certain examples (48 FR 14070) of amendments that are considered not likely to involve significant hazards consideration.
Example (i) relates to a purely administrative change to Technical Specifications: for example, a change to achieve consistency throughout the Technical Specifications, correction of an error, or a change in nomenclature.
In this case, the proposed change described in Attachments A are related to Example (i) , i.e., a purely administrative change.
Therefore, since the application for amendment involves a proposed change that is similar to an example for which no significant hazards consideration exists, we have determined that the application involves no significant hazards consideration. The proposed changes have been reviewed by the Station Nuclear Safety Committee. This Committee concurs that these changes do not represent a significant hazards consideration.
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