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Category:TECHNICAL SPECIFICATIONS
MONTHYEARML20195D0451999-06-0303 June 1999 Proposed Tech Specs,Revised to Agree with Current Facility Defueled TS Format ML20206N2751999-05-11011 May 1999 Proposed Tech Specs Deleting Figure 5.1-1 BRP Site Map from Defueld TS Subsection 1.16,changing Definition of Site & Other Associated Editorial Changes ML20154M5431998-10-14014 October 1998 Proposed Defueled Tech Specs & Bases for Big Rock Plant ML20236T6681998-07-21021 July 1998 Proposed Defueled Tech Specs for Big Rock Nuclear Plant ML20248L5511998-06-0505 June 1998 Draft Proposed Tech Specs Rev,Incorporating Changes Responsive to 980416 RAI ML20138G2021997-04-30030 April 1997 Proposed Tech Specs,Illustrating Change to Current Facility License DPR-6 ML20138A9131997-04-22022 April 1997 Proposed Tech Specs,Withdrawing Petition to Implement Option B Performance Based Requirements to App J of 10CFR50 ML20134H6411996-11-0707 November 1996 Proposed Tech Specs Re New Air Compressor to Svc Air Segment of Svc & Instrument Air Sys ML20129C4871996-10-15015 October 1996 Proposed Tech Specs Allowing Use of Option B for Type a Test (Containment),Type B Test (Pneumatic Tests to Detect & Measure Local Leakage Rates Across Pressure Retaining, leakage-limiting Boundaries) & Type C Tests ML20056G3931993-08-24024 August 1993 Proposed Tech Specs Reflecting Revision to 10CFR50.36(a)(2) Changing Reporting Requirement for Effluent Releases from Semiannual to Annual ML20046D1671993-08-0606 August 1993 Proposed Tech Specs Supporting Change of Superintendent Titles to Manager ML20045F2401993-07-0101 July 1993 Proposed Tech Specs Requesting Addition of New Requirement, Table & Bases & Deletion of 4.7.11.1.1.b & 4.7.11.1.1.d from Surveillance Section ML20044G7881993-05-24024 May 1993 Proposed Tech Specs Supporting Replacement of Reactor Protection Sys CB-RE11 Undervoltage Breakers & Rev of Release Device Trip Range ML20035F2441993-04-14014 April 1993 Proposed TS Section 6.3.2 Re Qualifications of Either Chemistry & Health Physics Supervisor ML20034G4201993-03-0404 March 1993 Proposed Tech Specs Reflecting Implementation of Revised 10CFR20 Re Administrative Controls ML20128D7251993-01-29029 January 1993 Proposed Tech Specs Re Administrative Controls ML20059A2181990-08-14014 August 1990 Proposed Tech Specs,Reflecting Administrative & Organizational Changes ML20011D2991989-12-21021 December 1989 Proposed Tech Specs Re Hot startup,source-range Monitor channel,power-range Monitor Channel & in-core Flux Monitors ML20245K6991989-06-30030 June 1989 Corrected Proposed Tech Specs Paragraph 3.7 Re Containment Sphere Leakage Testing ML20247L1141989-05-25025 May 1989 Proposed Tech Specs Aligning Specs to Current 10CFR50 App J Requirements That Permits Removal of 24 H Duration Restriction of Integrated Leak Rate Test ML20204F8321988-10-10010 October 1988 Proposed Tech Specs Change Re Partial Stroke Testing Following Main Valve Seat Leakage Repairs ML20154S6481988-09-22022 September 1988 Proposed Tech Specs,Allowing Independent Review & Audit Functions to Be Accomplished by Independent Organizational Unit Rather than Standing Committee ML20154P2191988-09-21021 September 1988 Proposed Tech Specs Reflecting Editorial & Administrative Corrections to Provide Clarification & Consistency ML20154D4821988-09-0808 September 1988 Proposed Tech Specs,Removing Organization Charts from Tech Specs & Informing NRC of Onsite Organizational Changes ML20150C7921988-07-0505 July 1988 Proposed Tech Specs Re Reactor Depressurization Sys Isolation Valves ML20148H6331988-03-22022 March 1988 Proposed Tech Specs Re Reactor Depressurization Sys ML20237B9691987-12-14014 December 1987 Proposed Tech Specs,Removing Numerical Designator from I-type Fuel for Each Subsequent Fuel Operating Cycle ML20236N5501987-11-0909 November 1987 Proposed Tech Spec Figure 5.1 & Sections 6.1,6.2,6.3 & 7.3, Making Administrative Changes to Reflect Features & Terminology Used W/New out-of-core Power Range Nuclear Instrumentation.Power Range Monitor Sys Description Encl ML20236B1201987-07-22022 July 1987 Proposed Tech Specs Changes Consisting of Administrative Corrections ML20210V2981987-02-10010 February 1987 Corrected Page 11 to Tech Spec,Reflecting New Signature Dates ML20210E5601987-02-0606 February 1987 Proposed Tech Specs,Adding Operability & Surveillance Requirements for Alternate Shutdown Sys & Revising Specs for Active Fire Barriers & Fire Detection Instrumentation for Auxiliary Shutdown Bldg ML20210C6341987-02-0404 February 1987 Proposed Tech Spec Changes,Adding Table of Uncertainty Factors Associated W/Core thermal-hydraulic Parameters Heat Flux,Maplhgr,Max Bundle Power & Min Critical Power Ratio ML20212F0361986-12-30030 December 1986 Proposed Tech Specs Adding Second Scram Dump Tank Vent & Drain Valve ML20207C9801986-12-22022 December 1986 Proposed Tech Specs,Reducing Station Battery Design Time Interval from 8 to 2 H ML20215G0101986-12-17017 December 1986 Proposed Tech Spec Page Changes,Adding Operability & Surveillance Requirements for Alternate Shutdown Sys ML20215C7391986-12-0505 December 1986 Proposed Tech Specs Re Reactor Core & Controls ML20206M5151986-08-15015 August 1986 Proposed Tech Specs,Reflecting Features & Terminology Used W/New out-of-core source-range Nuclear Instrumentation. Source-range Monitor Sys Description & Block Diagram Encl ML20203P8041986-05-0101 May 1986 Proposed Tech Spec Table 6.2-1,reflecting Exemption from Requirement to Have Two Senior Reactor Operators on Shift ML20203F6521986-04-21021 April 1986 Proposed Tech Specs Re Operability & Surveillance Requirements for Alternate Shutdown Sys,Active Fire Barriers & Fire Detection Instrumentation for Auxiliary Shutdown Bldg ML20154K0261986-03-0404 March 1986 Proposed Tech Specs,Adding Operability & Surveillance Requirements for Alternate Shutdown Sys Installed Per 10CFR50,App R ML20138B2531985-10-0909 October 1985 Proposed Tech Specs,Revising Calibr of Portable Gamma & Neutron dose-rate Measuring Instruments ML20137V9891985-09-30030 September 1985 Proposed Tech Spec Changes,Adding Operability & Surveillance Requirements for Components of Alternate Shutdown Sys Installed in Accordance w/10CFR50,App R ML20132F4891985-09-24024 September 1985 Proposed Tech Specs,Revising Fuel MAPLHGR Limits,Per 850816 Request,In Order to Implement Operating Limits for Reload I1 Fuel ML20135B8141985-09-0303 September 1985 Proposed Changes to Tech Spec 5.2.2.a,eliminating Min Control Rod Withdrawal Rate Limit ML20134E3111985-08-16016 August 1985 Proposed Tech Specs Implementing Reactor Operating Limits for Reload I1 Fuel ML20133N1551985-08-0505 August 1985 Proposed Tech Spec,Implementing Staff Reorganization ML20132B7361985-07-19019 July 1985 Proposed Tech Specs for Containment Pressure Monitor & Containment Water Level Monitor ML20128B9291985-06-27027 June 1985 Proposed Tech Spec Changes Re Operation of Plant Between Refueling Shutdown W/O Potential of Requiring Surveillance to Be Performed That May Affect Plant Availability ML20125B4111985-06-0707 June 1985 Proposed Correction to Tech Spec Page 110,adding Section 6.5.2.2,inadvertently Omitted from 850130 Change Request ML20128E5141985-05-24024 May 1985 Proposed Revised Tech Specs Renumbering Definition Section 1.2.8 to 1.2.14 Re Administrative Controls 1999-06-03
[Table view] Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML20195D0451999-06-0303 June 1999 Proposed Tech Specs,Revised to Agree with Current Facility Defueled TS Format ML20206N2751999-05-11011 May 1999 Proposed Tech Specs Deleting Figure 5.1-1 BRP Site Map from Defueld TS Subsection 1.16,changing Definition of Site & Other Associated Editorial Changes ML20154M5431998-10-14014 October 1998 Proposed Defueled Tech Specs & Bases for Big Rock Plant ML20238E8141998-08-31031 August 1998 Revised Big Rock Point Defueled Emergency Plan ML20236T6681998-07-21021 July 1998 Proposed Defueled Tech Specs for Big Rock Nuclear Plant ML20248L5511998-06-0505 June 1998 Draft Proposed Tech Specs Rev,Incorporating Changes Responsive to 980416 RAI ML20217P3811998-02-28028 February 1998 Revised Defueled Emergency Plan ML20138G2021997-04-30030 April 1997 Proposed Tech Specs,Illustrating Change to Current Facility License DPR-6 ML20138A9131997-04-22022 April 1997 Proposed Tech Specs,Withdrawing Petition to Implement Option B Performance Based Requirements to App J of 10CFR50 ML20216A9611997-01-0101 January 1997 Rev 13 to Big Rock Point Radiological Effluent T/S Required Documents,Offsite Dose Calculations & Process Control Program ML20134H6411996-11-0707 November 1996 Proposed Tech Specs Re New Air Compressor to Svc Air Segment of Svc & Instrument Air Sys ML20129C4871996-10-15015 October 1996 Proposed Tech Specs Allowing Use of Option B for Type a Test (Containment),Type B Test (Pneumatic Tests to Detect & Measure Local Leakage Rates Across Pressure Retaining, leakage-limiting Boundaries) & Type C Tests ML20199J7411995-10-0303 October 1995 Rev 6 to Users Guide for Vectora CL-200 Polyethylene High Integrity Containers ML20058N6421993-10-11011 October 1993 Rev 16 to Vol of Administrative Procedures,Procedure 3.2.1, Maint Order Processing, Pages 21 & 22 ML20056G3931993-08-24024 August 1993 Proposed Tech Specs Reflecting Revision to 10CFR50.36(a)(2) Changing Reporting Requirement for Effluent Releases from Semiannual to Annual ML20046D1671993-08-0606 August 1993 Proposed Tech Specs Supporting Change of Superintendent Titles to Manager ML20058N6401993-07-15015 July 1993 Rev 20 to Procedure T7-28, Emergency Diesel Generator Auto Test Start ML20058N6331993-07-15015 July 1993 Rev 142 to Vol 3 of Operating Procedure - Sys SOP-14, Substation ML20045F2401993-07-0101 July 1993 Proposed Tech Specs Requesting Addition of New Requirement, Table & Bases & Deletion of 4.7.11.1.1.b & 4.7.11.1.1.d from Surveillance Section ML20044G7881993-05-24024 May 1993 Proposed Tech Specs Supporting Replacement of Reactor Protection Sys CB-RE11 Undervoltage Breakers & Rev of Release Device Trip Range ML20035F2441993-04-14014 April 1993 Proposed TS Section 6.3.2 Re Qualifications of Either Chemistry & Health Physics Supervisor ML20034G4201993-03-0404 March 1993 Proposed Tech Specs Reflecting Implementation of Revised 10CFR20 Re Administrative Controls ML20128D7251993-01-29029 January 1993 Proposed Tech Specs Re Administrative Controls ML20127N4321993-01-11011 January 1993 Third Interval ISI Program ML20141M5531992-03-10010 March 1992 Rev 8 to Vol 25 to Procedure Big Rock Point Radiological Effluent TS Required Documents,Offsite Dose Calculations & Process Control Program ML20059A2181990-08-14014 August 1990 Proposed Tech Specs,Reflecting Administrative & Organizational Changes ML20011D2991989-12-21021 December 1989 Proposed Tech Specs Re Hot startup,source-range Monitor channel,power-range Monitor Channel & in-core Flux Monitors ML20246J1841989-08-25025 August 1989 Rev 4,Vol 25 to, Big Rock Point Radiological Effluent Tech Spec Required Documents for Offsite Dose Calculation Manual & Process Control Program ML20245K6991989-06-30030 June 1989 Corrected Proposed Tech Specs Paragraph 3.7 Re Containment Sphere Leakage Testing ML20247L1141989-05-25025 May 1989 Proposed Tech Specs Aligning Specs to Current 10CFR50 App J Requirements That Permits Removal of 24 H Duration Restriction of Integrated Leak Rate Test ML20204F8321988-10-10010 October 1988 Proposed Tech Specs Change Re Partial Stroke Testing Following Main Valve Seat Leakage Repairs ML20154S6481988-09-22022 September 1988 Proposed Tech Specs,Allowing Independent Review & Audit Functions to Be Accomplished by Independent Organizational Unit Rather than Standing Committee ML20154P2191988-09-21021 September 1988 Proposed Tech Specs Reflecting Editorial & Administrative Corrections to Provide Clarification & Consistency ML20154D4821988-09-0808 September 1988 Proposed Tech Specs,Removing Organization Charts from Tech Specs & Informing NRC of Onsite Organizational Changes ML20207C2291988-07-13013 July 1988 Rev 7 to Suitability,Training & Qualification Plan. W/ ML20150C7921988-07-0505 July 1988 Proposed Tech Specs Re Reactor Depressurization Sys Isolation Valves ML20154L7961988-05-26026 May 1988 Simulation Facility Plan for Big Rock Point to Meet 10CFR55.45(b) ML20153G0861988-04-13013 April 1988 Rev 2 to Procedure Change Form, Offsite Dose Calculations Manual ML20153G1041988-04-12012 April 1988 Radiological Effluent T/S Required Documents,Offsite Dose Calculations & Process Control Program ML20155A5221988-04-0606 April 1988 Rev 30 to Procedure T30-22, ECCS Valve Tests ML20148Q4681988-03-31031 March 1988 Rev 2 to Guidance for Development of Simulation Facility to Meet Requirements of 10CFR55.45 ML20148H6331988-03-22022 March 1988 Proposed Tech Specs Re Reactor Depressurization Sys ML20147E3701988-01-14014 January 1988 Rev 6 to Suitability,Training & Qualification Plans ML20215M3281987-12-31031 December 1987 Emergency Plan Exercise Scenario ML20237B9691987-12-14014 December 1987 Proposed Tech Specs,Removing Numerical Designator from I-type Fuel for Each Subsequent Fuel Operating Cycle ML20236P0671987-11-13013 November 1987 Rev 1 to Big Rock Point IGSCC Insp Program ML20236N5501987-11-0909 November 1987 Proposed Tech Spec Figure 5.1 & Sections 6.1,6.2,6.3 & 7.3, Making Administrative Changes to Reflect Features & Terminology Used W/New out-of-core Power Range Nuclear Instrumentation.Power Range Monitor Sys Description Encl ML20236B1201987-07-22022 July 1987 Proposed Tech Specs Changes Consisting of Administrative Corrections ML20214N9801987-05-29029 May 1987 Rev 0 to Health Physics Procedure HP 10.9, Big Rock Point Radiological Environ Program Sample Collection & Shipment ML20213A1761987-04-22022 April 1987 Rev 5 to Suitability Training & Qualification Plan 1999-06-03
[Table view] |
Text
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u 1100 B2 00 TABLE 6.2-1 O UR e
3$
Minimum Shirt Crew Composliljn)
O The minimum shirt crew shall be as follows except when plant conditions specified in paragraph (a) or (b) below have been g{
estabilshed (see Note (1) below) or when an unexpected absence occurs (see Note (2) below):
TW 1 Shirt Supervisor - SOL hlhlU' 2 Operators - OL 1 Operator - Nonf icensed a.
Cold Shutdown and ShutdowD (As Defined by Section 1.2) 1 Shirt Supervisor - SOL 3
1 Operator - OL 1 Operator - Nonf icensed b.
Refuelino Operations (See Note (3) Below) 1 Sh i f t Supe rv i so r - SOL 1 Ope ra to r - OL 2 Operators - Nonlicensed SOL - Senior Operator Licensed in accordance with 10 CFR 55.
OL - Opera tor Licensed in accordance with 10 CIR 55.
(1)During control rod motion associated with reactor start-up (to a power level > 5 percent), one licensed operator shall observe the control rod manipulation to ensure established control rod withdrawal procedures are adhered to.
(2)ln the event that any member of a minimum shirt crew is absent or incapacitated due to illness or injury, a quairled replacement shall report on site within two hours.
(3)Does not include additional personnel required when core alterations are being conducted. See 6.2.2.e.
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