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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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ATTACHMENTI j
l PROPOSED TECHNICAL SPECIFICATION CHANGE l
i i
CONSOLIDATED EDISON COMPANY OF NEW YORK, INC.
INDIAN POINT UNIT NO.1 DOCKET NO. 50-3 JULY 20,1999 9900030232 990720 PDR ADOCK 05000003 PM p
\
- f. The Nuclear Facilities Safety Committee shall function to provide independent review and audit of designated activities in areas of nuclear engineering, chemistry, radiochemistry, metallurgy and non-destructive testing, instrumentation and control, radiological safety, mechanical and electrical engineering, administrative controls and quality assurance activities, and radiological environmental effects,
- g. All fuel handling shall be under the direct supervision of a licensed operator.*
- h. The Senior Watch Supervisor is responsible for operations at the Unit No.1 facility.
- i. The qualification requirements of the Operations Manager and the Assistant Operations Manager are provided in Sections 6.2.2 and 6.3 of Appendix A to the Indian Point Unit No. 2 Facility Operating License No. DPR-26.
- Licensed operator for IP-2 3.3 Ooeratina Instructions and Procedures 3.3.1 No fuel will be loaded into the reactor core or moved into the reactor containment building without prior review and authorization by the Nuclear Regulatory Commission.
3.3.2 Detailed written instraction setting forth procedures used in connection with the operation and maintenance of the nuclear power plant shall conform to the Technical Specifications.
3.3.3 Operation and maintenance of equipment related to safety when there is no fuel in the reactor shall be in accordance with written instructions.
Amenoment No. Page 7
ATTACHMENTII SAFETY ASSESSMENT CONSOLIDATED EDISON COMPANY OF NEW YORK, INC.
INDIAN POINT UNIT NO.1 DOCKET NO. 50-3 JULY 20,1999
SECTION I - Descrantlan of Chanae Con Edison transmitted (Reference 1) proposed changes to the Indian Point 2 Technical Specifications which included a revision to Section 6.2.2.h and to Section 6.3.1 to change the senior reactor operator license requirement for the Operations Manager. This application provides a proposed amendment to the Indian Point 1 Technical Specifications to provide a similar change to Section 3.2.1.i.
Currently Indian Point Unit No.2 Technical Specification 6.2.2.h states:
"The Operations Manager shall hold a senior reactor operator license."
Reference 1 proposes to change the Indian Point Unit No.2 Technical Specification 6.2.2.h to:
"The Operations Manager or Assistant Operations Manager shall hold a senior reactor operator license."
Currently Indian Point Unit No.2 Technical Specification 6.3.1 states:
"Each member of the facility staff shall meet or exceed the minimum qualifications of ANSI N18.1-1971 for comparable positions, except for the Radiation Protection Manager who shall meet or exceed the minimum qualifications of Regulatory Guide 1.8, September 1975."
Reference 1 proposes to change the Indian Point Unit No.2 Technical Specification 6.3.1 to:
"Each member of the facility staff shall meet or exceed the minimum qualifications of ANSI N18.1-1971 for comparable positions, except for (1) the Operation Manager's and the Assistant Operation Manager's SRO license requirement which shall be in -
accordance with Technical Specification 6.2.2.h, and, (2) the Radiation Protection Manager who shall meet or exceed the minimum qualifications of Regulatory Guide 1.8, September 1975."
Currently Indian Point Unit No.1 Technical Specification 3.2.1.i states:
"The' Operations Manager shall held a senior reactor operator license.*
"The qualification requirements of the Operations Manager and the Assistant Operations Manager are provided in Sections 6.2.2 and 6.3 of the Indian Point Unit No. 2 Technical Specifications."
Page 1 of 4
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I SECTION H - Evaba*lan of Chanae Presently I'ndian Point Unit No.1 Technical Specification 3.2.1.i and Indian Point Unit No. 2 Technical Specification 6.2.2.h have identical requirements. The proposed change, coupled with the changes proposed in Reference 1, will maintain the same requirements in both Technical Specifications Indian Point Unit No. 2 Technical Specification 6.2.2.h currently requires the Operations Manager (OM) to hold a Senior Reactor Operator's (SRO) license. In Reference 1 Con Edison proposed to modify this requirement to have the OM or the Assistant Operations Manager (AOM) hold an SRO license. ~ Current practice at Indian Point 2 is to have two SRO licensed positions in charge of shift activities. These two positions are the Senior Reactor Operator and the Senior Watch Supervisor (SWS). The AOM is directly in the reporting hierarchy between the SWS and the OM. The day-to-day activities of the Operations Department are carried out under the direction of the AOM. Thus, by requiring either the OM or the AOM to hold an SRO license, there is assurance that the SWS will report to an individual with an SRO license.
Indian Point Unit No. 2 Technical Specification 6.3.1 currently requires that facility staff meet or exceed all the requirements of ANSI N18.1-1971 (" Selection and Training of Nuclear power Plant Personnel"). Section 4.2.2 of ANSI N18.1-1971, states:
"At the time of . . . appointment to the active position the operations manager shall hold a Senior Reactor Operator's License." ,
While, ANSI N18.1-1971 makes no mention of an Assistant Operations Manager, NUREG-1431, Rev.1 (" Standard Technical Specifications - Westinghouse Plants"),
Section 5.2.2.f. states:
"The Operations Manager or Assistant Operations Manager shall hold an SRO license." !
Thus the Reference 1 proposed changes to Indian Point Unit No. 2 Technical Specifications 6.2.2.h and 6.3.1 are consistent with Section 5.2.2.f of NUREG-1431. Since the OM and the AOM will still be required to. meet or exceed all of the other ANSI N18.1-1971 minimum requirements, there is assurance that the OM and the AOM will be knowledgeable and
- qualified individuals. By requiring that either the OM or the AOM hold an SRO license, there
- is assurance that high-level management withiri the Operations Depr.rtment will maintain a knowledge of current plant systems and operation.
Therefore, the Con Edison proposal (Reference 1) to modify the requirement to have the OM and the AOM meet all the qualification requirements of ANSI N18.1-1971 except for the SRO j license requirement which would be in accordance with the Technical Specifications, will allow I an individual who does not hold a current SRO license to be appointed as Operations Manager or Assistant Operations Manager provided all the other qualification requirements of ANSI N18.1-1971 are met.
l Page 2 of 4 i U
SECTION III - No Slenificant H= wards Evnlaa*lon The proposed change does not involve a significant hazards consideration because:
- 1) Does the propo. sed license amendment involve a significant increase in the probability or in the consequences of an accident previously evaluated?
No. This proposed change is administrative in nature. In addition, this proposed change is consistent with the statement in NUREG-1431, Rev.1, 1 Section 5.2.2.f. This change does not affect possible initiating events for accidents previously evaluated or alter the configuration or operation of the facility. The Limiting Safety System Settings and Safety Limits specified in the I current Technical Specifications remain unchanged. Therefore, the proposed change would not involve a significant increase in the probability or in the consequences of an accident previously evaluated.
- 2) Does the proposed amendment create the possibility of a new or different kind of accident from any accident previously evaluated?
No. This proposed change is administrative in nature. The safety analysis of the facility remains complete and accurate. There are no physical changes to the facility and the plant conditions for which the design basis accidents have been evaluated are still valid. The operating procedures and the emergency procedures are unaffected. Consequently no new failure modes are introduced as a result of the proposed change. Therefore, the proposed change would not ;
create the possibility of a new or different kind of accident from any accident I previously evaluated.
- 3) Does the proposed amendment involve a significant reduction in a margin of safety?
No. This proposed change is administrative in nature. Since there are no changes to the operation or the physical design of the facility, the Updated Final Safety Analysis Report (UFSAR) design basis, accident assumptions, or Technical Specification Bases are not affected. Therefore, the proposed change does not involve a significant reduction in a margin of safety.
Therefore, the proposed change to the Technical Specifications does not involve a significant hazards consideration. In addition, the proposed change to the Technical Specifications has been reviewed by both the Station Nuclear Safety Committee (SNSC) and the Con Edison Nuclear Facility Safety Committee (NFSC). Both Committees concur that the proposed change does not represent a significant hazards consideration.
Page 3 of 4
SECTION IV - Reference
- 1. Coit Edison letter from A. A. Blind, to the USNRC Document Control Desk,
Subject:
" Proposed Amendment Consisting Of Administrative Changes To The Technical ;
Specifications," dated January 22,1999.
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Page 4 of 4
