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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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ATTACHMENT I PROPOSED TECHNICAL SPECIFICATION CHANGES RELATED TO MANACEMENT TITLE CHANGES (APPENDIX A)
POWER AUTHORITY OF THE STATE OF NEW YORK INDIAN POINT 3 NUCLEAR POWER PLANT DOCKET NO. 50-286 SEPTEMBER 28 , 1979 1126 074 7910100 30L P
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PRESIDENT & '
CHIEF OPERATING
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@i SAFETY REVIEW ,
y COMMITTEE 8
EXECUTIVE V.P. EXECUTIVE V.P.
& CHIEF 2NGINEER & DIRECTOR OF -l POWER OPERATIONS l
- DIRECTOR OF SAFETY / SECURITY l l
MANAGER NUCLEAR OPERATIONS l I
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cn RESIDENT __ __ _j y, MANAGER
- RESPONSIBLE FOR POWER AUTHORITY DIRECTION OF FIRE PROTECTION PROGRAF 1 bb ------------ADMINISTRATIVE FIGURE 6.2-1 CP' MANAGEMENT ORGANIZATION CHART FUNCTIONAL INDIAN POINT 3 NUCLEAR POWER PLANT a
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' TiUDITS 6.5.2.8 Audits of facility activities shall be performed under the cognizance of the SRC. These audits shall encompass:
- a. The conformance of facility operation to provisions contained within the Technical Specifications and applicable license conditions at least once per 12 months.
- b. The performance, training and qualifications of the entire facility staff at least once per 12 months.
- c. The results of actions taken to correct deficiencies occurring in facility equipment, structures, systems or method of operation that affect nuclear safety at least once per 6 months.
- d. The performance of activities required by the Operational Quality Assurance Program to meet the criteria of Appendix "B", 10 CFR 50, at least once per 24 months.
- e. The Facility Emergency Plan and implementing procedures at least once per 24 months.
- f. The Facility Security Plan and implementing procedures at least once per 24 months.
- g. Any other area of facility operation considered appropriate by the SRC or the President. I
- h. The Facility Fire Protection Program and implementing procedures at least once per two years.
- i. A fire protection and loss prevention inspection and audit shall be performed annually utilizing either qualified offsite licensee personnel or an outside fire protection firm.
- j. An inspection and audit of the fire protection and loss prevention program shall be performed by an outside qualified fire consultant at intervals no greater than 3 years.
AUTHORITY 6.5.2.9 The SRC shall report to and advise the President and Chief Operating Officer (to be refered to in the Tech. Spac. as President) on those areas of responsibility specified in Sections 6.5.2.7 and 6.5.2.8.
Amendment No. 6-11 1126 076
RECORDS 6.5.2.10 Records will be maintained in accordance with ANSI 18.7-1972. The e following shall be prepared, approved and distrubuted as indicated below:
- a. Minutes of each SRC meeting shall be prepared, approved and forwarded to the President within 14 days after the date l of the meeting.
- b. Reports of reviews encompassed by Section 6.5.2.7 above, shall be prepared, approved and forwarded to the President within }
14 days following completion of the review.
- c. Audit reports encompassed by Section 6.5.2.8 above, shall be forwarded to the President and to the management positions I responsible for the :_eas audited within 30 days after completion of the aulit.
CHARTER 6.5.2.11 Conduct of the committee will be in accordance with a charter, approved by the President, setting forth the mechanism for implementation of the l committee's responsibilities and authority.
6.6 REPORTABLE OCCURRENCE ACTION 6.6.1 The following actions shall be taken for REPORTABLE OCCURRENCES:
- a. The Commission shall be notified and/or a report submitted pursuant to the requirements of Specification 6.9.
- b. Each REPORTABLE OCCURRENCE requiring 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> notification to the Commission shall be reviewed by the PORC and a report sub-mitted by the Resident Manager to the Chairman of the SRC and Manager-Nuclear Operations.
6.7 SAFETY LIMIT VIOLATION 6.7.1 The following actions shall be taken in the event a Safety Limit is violated:
- a. The reactor shall be shut down and reactor operation shall only be resumed in accordance with the provisions of 10 CFR 50.36(c) (1) (i) .
- b. The Safety Limit violation shall be reported immediately to the Commission. The Chairman of the SRC and Manager-Nuclear Operations will be notified within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
- c. A Safety Limit Violation Report shall be prepared by the PORC.
This report shall describe (1) applicable circumstances preceding the occurrence, (2) effects of the occurrence upon facility com-ponents, systems or structures, and (3) corrective action taken to prevent recurrence.
Amendment No. 6-12 1126 077
ATTACHMENT II PROPOSED ENVIRONMENTAL TECHNICAL SPECIFICATION CHANGES MANAGEMENT TITLE CHANGES (APPENDIX B)
POWER AUTHORITY OF THE STATE OF NEW YORK INDIAN POINT 3 NUCLEAR POWER PLANT DOCKET NO. 50-286 SEPTEMBER 28 , 1979 1126 078
e PRESIDENT & CHIEF OPERATING OFFICER W -
E 02 SAFETY REVIEW Ci COMMITTEE 5
EXECUTIVE VICE PRESIDENT EXECUTIVE VICE PRESIDENT
& CHIEF ENGINEER & DIRECTOR OF POWER OPERATIONS DIRECTOR OF ENVIRONMENTAL PROGRAMS to STAFF
-- FIGURE 5.2-2 MANAGEMENT ORGANIZATION ENVIRONMENTAL rs) INDIAN POINT 3 NUCLEAR POWER PLANT Ch O
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4 ATTACHMENT III SAFETY EVALUATION RELATED TO MANAGEMENT TITLE CHANGES POWER AUTHORITY OF THE STATE OF NEW YORK INDIAN POINT 3 NUCLEAR POWER PLANT DOCKET NO. 50-286 SEPTEMBER 28, 1979 1126 080
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( Section I - Description of the Modification The position of General Manager and Chief Engineer has been retitled President and Chief Operating Officer. The position of Assistant General Manager-Engineering has been retitled Executive Vice President and Chief Engineer.
The position of Director of Power Operations has been changed to Executive Vice President and Director of Power Operations.
The Resident Managers will now report administratively to the Executive Vice President and Director of Power Operations.
The functional relationship between the Resident Manager and the Manager-Nuclear Operations remains unchanged.
Section II - Purpose of Modification The purpose of this modification is to comply with the require-ment of 10 CFR 50.59(c) to report all changes to the operating license.
Section III - Impact of the Change These changes in management titles 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 - Conclusions 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 1126 081
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